Text

Transmittal of 2016 Annual Radioactive Effluent Release Report
	ML17116A053
Person / Time
Site:	Watts Bar
Issue date:	04/26/2017
From:	Simmons P; Tennessee Valley Authority
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	Download: ML17116A053 (277)
	v • d • e

Tennessee Valley Authority, Post Office Box 2000, Spring City, Tennessee 37381-2000 April 26,2017 10 CFR 50 36a(aX2) 10 CFR 72.1 04(a)

U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Watts Bar Nuclear Plant, Unlt '1 and Unit 2 Facility Operating License Nos. NPF-90 and NPF-96 NRC Docket Nos. 50-390 and 50-391

Subject:

Watts Bar Nuclear Plant 20f 5 Annua! Radioactive Effluent Release Report The purpose of this letter is to provide the Tennessee Valley Authority (TVA) Watts Bar Nuclear Plant (WBN) Annual Radioactive Effluent Release Report (ARERR) for the period of January 1, 2016 to December 31 , 2016. The enclosed annual report is being submitted to the Nuclear Regulatory Commission (NRC) in accordance with Title 10 of the Code of Federal Regulations (10 FR) 50.36a and the Watts Bar Nuclear Plant (WBN), Unit 1 and Unit 2, Technical Specification (TS) 5.9.3, that requires the ARERR be submitted prior to May 1st of each year.

The enclosure provides the required effluent release data. This report includes information related to the lndependent Spent Fuel Storage lnstallation (lSFSl) which went into service for the first time at WBN in October of 2016. Attachment 1 to the enclosure 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 the enclosure provides corrections to previous annual reports. Attachment 4 of the enclosure provides a copy of Revision 1 the Two-Unit ODCM. This revision was in effect as of october 22,2015, and is provided in accordance with rechnical Specificatio n 5.7 .2.3.

Changes to the Process Control Program (PCP) are reported in conjunction with the ARERR in accordance with Section 2.4 of the PCP. No changes have been made to the PCP since the last annual report.

U.S. Nuclear Regulatory Commission Page2 April26,2017 There are no new regulatory commitments associated with this letter. Please direct any questions concerning this matter to Gordon Arent, WBN Licensing Director at (423) 365-2004.

Respectfully, ,/

Paul Simmons Site Vice President, Watts Bar Nuclear Plant

Enclosure:

Watts Bar Nuclear Plant - 2016 Annual Radioactive Effluent Release Report cc (Enclosure):

U.S. Nuclear Regulatory Commission, Region ll NRC Senior Resident lnspector - Watts Bar Nuclear Plant NRC Project Manager - watts Bar Nuclear Plant,

Enclosure Watts Bar Nuclear Plant 2016 Annual Radioactive Etrluent Release Report (Effluent and Waste Disposal Annual Report)

Attachments Attachment 1 - Deviations from ODCM Controls / Surveillance Requirements Attachment 2 - Radioactive Effluent Monitoring lnstrumentation lnoperable for Greater than 30 days Attachment 3 - Corrections to Previous ARERRs Revision Attachment 4 - Two-Unit Offsite Dose Calculation Manual Revision 1

Enclosure Watts Bar Nuclear Plant 2016 Annual Radioactive Effluent Release Report (Effluent and waste Disposal Annual Report)

Attachments Attachment 1 - Deviations from ODCM Controls / Surveillance Requirements Attachment 2 - Radioactive Effluent Monitoring lnstrumentation lnoperable for Greater than 30 days Attachment 3 - Corrections to Previous ARERRs Revision Attachment 4 - Two-Unit offsite Dose calculation Manual Revision 1

Enclosure Watts Bar Nuclear Plant Annual Radioactive Effluent Release Report - 24ffi E-:1

2016 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-'t31, iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 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 equal to 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-131, 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 equal to 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, Part 20 (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-M pCilmltotal activity.

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

a. Less than or equalto 1.5 mrem to the total body and less than or equalto 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.

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201 6 Watts Bar Nuclear Plant 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-04 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), Pu blication 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 avercge beta and gamma energies (E) for gaseous effluents as described in Regulatory Guide 1.21 Revision 1, "Measuring, Evaluation, and Reporting Radioaetivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants," are not applicable.

4. 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 and 2.2-2.

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 anive 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 concentrations are used to determine the curies of tritium released from Condensate Demineralizer Tank.

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2016 Watts Bar Nuclear Plant Effluent and Waste Disposal Annual Report Continuous Releases (Turbine Building Station Sump (TBSS), Steam Generator Blowdowns (SGB), and Groundwater Sump (GWS))

During periods of no significant identified primary to secondary leakage, the volume released from the TBSS and SGB's are obtained. The TBSS tritium concentration is determined via weekly grab samples. The feedwater tritium concentrations are used to determine the curies of tritium released from SGB's. The GWS is sampled monthly and analyzed for gross gamma and tritium on a monthly basis and for Sr-89, Sr-90 and Ni-63 on a quarterly basis. The total ac{ivity released is obtained by determining the concentration of each nuclide and then multiplying by the volume discharged to arive at the curie activity for each nuclide.

Monitoring Wells Watts Bar has six (6) radiologicalenvironmentalmonitoring program (REMP) on-site groundwater monitoring wells and also 21 non-REMP monitoring wells to support monitoring the onsite groundwater plume for the presence or increase of radioactivity. WBN contracts ARCADIS to perform investigations of the impac{ tritium has on groundwater and to perform site characterizations, area of impact, and preliminary human health and ecological risk screening.

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2016 Watts Bar Nuclear Plant Effluent and Waste Disposal Annual Report Monitoring Wells (Continued)

The non-REMP monitoring wells are sampled semi-annually for gamma and tritium. These wells continue to exhibit a stable trend and a historical average decreasing with time. The tritium concentrations obtained in 2016 from these monitoring wells are listed below. Newwells MW-06 thru MW-10 were installed and sampled during July 2016. More frequent sampling to establish baseline conditions. Well K sample was also anallzed for Sr-89, Sr-90, Fe-55, and Ni-63, with no detectable results.

a4fit2016 9t21nArc Well lD Activity pCi/L Activity pCi/L D Dry 498 E Dry 236

\,

A Dry 414 H Line Blockage Line Blockage

<214 522 J <214 1442 K 3286 2976 L 1459 1 138 M Line Blockage 3S0 o <214 429 P <214 410 a <214 <228 R 645 908 S 282 633 V <214 <228 Well lO 7t1tafi1$ 9t24t2016 12t21t2416 Activity pCiJL Activity pCi/L Activity pCill MW-06 <222 <228 267 MW-07 <222 262 322 MW-08 <222 <228 239 MW-09 608 520 1 693 MW.1O <222 <228 252 Doses from l-131 Water lngestion Pathway The REMP specified in Table 3.12-1from NUREG 1301, "Offsite 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.

Therefore, the evaluation confirms 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.

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watts *rfil3,"rr Prant Effluent and Waste Disposal Annual Report Doses from l-131 Water lngestion Patlrway {Continued}

Quarter 1 2 3 4 Totals I-131 Ci 0,00E+00 g.ggf+00 0.00E+00 0.00E+00 0.00E+00 Child/Thyroid {mrem} 6.ggf+00 0.00E+00 0,00E+00 0.00E+00 g.gSf+00 Pop u ation/Thyroid { m rem}

I 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0"00E+00 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-'t31 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 Exhausts due to purging containment is determined by using the purge monitor response in combination with containment air samples obtained prior to each 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 contiainment 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 faclor of three.

The quantity of noble gases released through the Shield Building Exhausts due to the batch release of waste gas decay tanks are determined by sampling each tank prior to release. Total activity released is determined from total pressure change recorded of 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 Exhausts and Auxiliary Building Exhaust and from the Condenser Vacuum Exhausts 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 charcoal samples are taken from the Shield Building Exhausts, Auxiliary Building Exhaust, and Condenser Vacuum Exhausts once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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 faetor of three.

Carbon-14 in Gaseous Releases The Carbon-14 produclion and effluent source term estimates were based on EPRI methodology provided in EPRI Report 1A21106, "Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents,'dated December 2OlA.ltwas determined in 2016 that 13.8 curies of Carbon-14 was generated at WBN. However, only 98% is considered released as gas and only the carbon dioxide lorm {2oo/o) of that is used in the gaseous dose calculations.

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2016 Watts Bar Nuclear Plant Etfluent and Waste Disposal Annual Report

5. Batch Releases Value 1st Half 2nd Half Units A. Liquid {Radwaste only}

1. Number of releases 55 91 Each

2. Total time period of releases 10281 21937 Minutes

3. Maximum time period of release 450 535 M inutes

4. Average time period of releases 187 24L Minutes

5. Minimurn time period for release 95 70 M inutes

6. Average dilution stream flow during 78,747 L4,8T9 CFS release periods B. Gaseous {Batches only - containment purges, and waste gas decay tanks)

L. Number of releases 37 26 Each

2. Total time period of releases 224595 L7837 Minutes

3. Maximum time period for release 54178 7807 Minutes

4. Average time period for releases 6070 686 Minutes 5, Minimum time period for release 7 7 Minutes

6. Abnorrnal Releases Value Units 1st Half Lnd Half A. Liquid Number of Releases 00 Total Activity Released 0.00E+00 0.008+G0 Ci B. Gaseous Number of Releases 1* 5*

Total Activity Released 5.38E-04 1.59E-03 Ci

" Steam Generator PORV releases E-7

2016 Watts Bar Nuclear Plant Effluent and Waste DisposalAnnual Report Release Type: Gaseous (Steam)

Release Point: Unit 1 Steam Generator PORV's Date{s} of Release: A312212016 11:31 through 0312512416 1 1:55 This evaluation is for the release to the environment that occurred from the Unit 1 Steam Generator PORVS.

Following the automatic reactor trip due to actuation of the Over Temperature Delta T. The PORV valves were opened and closed during periods of time. CR 1 152462 documents this event.

The following is data used to show no dose impad of the release:

o While allthe PORVs were not open continuously during this period, the evaluation assumed the release was continuous from allfour PORVS.

e There have been no gamma emitting radionuclides identified in any Secondary Coolant samples.

r The feedwater tritium results obtained onO312112016 indicated a tritium concentration of 1.00E-06 pCi/ml. This tritium concentration is assumed to have been the initial concentration with no additional tritium introduced into the steam generator(s) during the release period.

All of the tritium initially present in the steam generator{s) was assumed to have been released through the PORVs during the date range listed above.

The volume of each steam generator was taken from Westinghouse Guidelines for Secondary Water Chemistry. The listed normalwater levelvalue of 4750 ft3 was used as a conservative value. This calculation conservatively assumes that the total volume of all four generators was released and that all the tritium present in that initial volume was released. The calculation for the total tritium activity released is as follows:

4750 fi3/generator " 2.832E+04 mllft3 4 generators = 5.38E+08 ml 1.00E-06 pCi/ml

5.38E+08 ml = 5.38E+02 pCi of H3 or 5.38E-04 Ci of H3 The activity of 5.38E-04 curies was added to the 1st Quarter Table 4'A, 'Curies Released in Gaseous Ground Level Releases," and the 1st Quarter doses in Table 6-A,'Dosesfrom Airborne Effluents." The addition of the 5.38E-04 curies of tritium did not have any impact on changing the dose values for the 1st quarter of 2016.

lndividual Doses First Quarter Pathway Dose Quarterly Lirnit Percent of Limit Location External Gamma Air 0.00E+00 mrad 5 mrad Nl1 550 meters Beta Air 0.00E+00 mrad 10 mrad N/1 550 meters Suhmersion Total Body 0.00E+00 mrad N/A N/A N14474 meters Skin 0.00E+00 mrad N/A N/A N14474 meters Organ Doses Child/Thyroid 6.428-07 rnrem 7.5 mrem SE/1409 meters Child/Total Body 6.42E-07 mrem 7.5 mrem SE/1409 meters Population Doses Total Body Dose 2.47E-OO man-rem Maximum Organ Dose (Organ) 2.47E-OO man-rem (Thyroid, Liver, Bone, GlT, Lung, Kidney)

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2016 Watts Bar Nuclear Plant Effluent and Waste DisposalAnnual Report ABNORMAUUNPLAN N ED RELEASES Release Type: Gaseous (Steam)

Release Point: Unit 2 Steam Generator PORV's Date(s) of Release: 08/03/2016 10:'12 through 1012912016 11:32 This evaluation is for the release to the environment that occurred from the Unit 2 Steam Generator PORV's after initial criticality. Dates are listed as follows:

813116-Anl16 was a planned manualshutdown for MCR evacuation trip test per 2-PAT-8.5.

8113116-A122/16 was a planned manual shutdown from hydrogen issues on generator.

8123116-A125/16 was a unplanned manual trip due to lowering speed on 2A MFP. CR 1206191.

8130116-9125/16 was automatic trip from 28 Main Bank transformer fire. CR '1208823.

10122116-10129116 was planned manualtrip for 2A Main Bank transformer.

The following is data used to determine the curies and dose impacts as a result of the release:

o There have been no gamma emitting radionuclides identified in any Secondary Coolant samples.

r The averaged feedwater tritium results obtained from July 20-October 3 indicated a tritium concentration of 5.91E-07 pCi/ml. There were no previous Unit 2 feedwater tritiums above detection limits prior to July. This tritium concentration is assumed to have been the initial concentration with no additional tritium introduced into the steam generator(s) during the release period. All of the tritium initially present in the steam generator(s) was assumed to have been released through the PORVs during the date range listed above.

The volume of a steam generator was taken from Westinghouse Guidelines for Secondary Water Chemistry. The listed normalwater levelvalue of 4250 ft3 was used as a conservative value. This calculation conservatively assumes that the total volume of four steam generators was released and that all the tritium present in that initial volume was released. The calculation for the total tritium activity released is as follows:

4250 ft3lgenerator " 2.832E+04 ml1ft3

4 generators = 4.81E+08 ml 5.91E-07 pCi/rnl

4.81E+08 ml = 2.85E+02 pCi of H3 or 2.85E-04 Ciof H3 The activity of 2.85E-04 curies is per event. Taking this activity times the four trips or shutdowns would conservatively account for 1 . 14E-03 curies in 3rd quarter and one trip for 2.85E-04 curies in 4th quarter released. This was added to 3rd - 4th Quarter Tables 4-C and 4-D, "Curies Released in Gaseous Ground

.Doses from Airborne Effluents." The Level Releases,'and the 3rd - 4th Quarter doses in Tables 6-8, addition of the total I .42E,03 curies of tritium did not have any impacl on changing the dose values for the 3rd - 4th quarters of 2016.

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2016 Watts Bar Nuclear Plant Effluent and Waste Disposal Annual Report Unit 2 Steam Generator PORVs 08/03 t2A16 through fi1291201 0 lndividual Doses Third Quafier Pathway Dose Quarterly Limit Percent of Limit Location External Garnma Air 0.00E+00 mrad 5 mrad N/1 550 meters Beta Air 0.008+00 mrad 10 mrad N/1 550 meters Submersion Total Body 0.00E+00 mrad N/A N/A N/4474 meters Skin 0.00E+00 mrad N/A N/A N14474 meters Oruan Doses Child/Thyroid 2.478-06 mrem 7.5 mrem SE/1409 meters Child/Total Body 2.478-06 mrem 7.5 mrem SEl1409 meters Pooulation Doses Total Body Dose 7.00E-06 man-rem Maximum Organ Dose (Organ) 7.00E-06 man-rem (Thyroid, Liver, Bone, GlT, Lung, Kidney) lndividual Doses Fourth Quarter Patlrway Dose Quarterly Limit Perc*nt of Lirnit Location External Gamma Air 0.008+0S mrad 5 mrad N/1 550 meters Beta Air 0.00E+00 mrad 10 mrad N/1 550 meters Subrnersion Total Body 0.008+00 mrad N/A N/A N14474 meters Skin 0.008+00 mrad N/A N/A N14474 rneters Organ Doses Child/Thyroid 6.S78-07 mrem 7.5 mrem SE/1409 meters Child/Total Body 6.S7f *AT rnrern 7 .5 mrem SE/1409 meters Population Doses Total Body Dose 1.88E-06 man-rem Maximum Organ Dose (Organ) 1.88E-06 man-rem (Thyroid, Liver, Bone, GlT, Lung, Kidney)

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2016 Watts Bar Nuclear Plant Effluent and Waste Disposal Annual Report TABLE 1.4 Liquid Effluents - Summation of All Releases During the period Starting: 1-Jan-2016 Ending: 30-Jun-2016 Est. Tot Type Of Effluent Units Quarter 1 Quarter 2 Errot o/*

A. Fission & Activation Products

1. Total Release (Not lncluding Tritium, ci 2.56E-03 1.81E-03 25Yo Gases, Alpha)

2. Average Diluted Goncentration During pCi/ml 3.52E-10 1.068-10 Period

3. Percent Of Applicable Limit % 'r' 't B. Tritium

1. Total Release ci 5.068+01 1.278+02 LB%

2. Average Diluted Concentration During rrCi/ml 6.96E-06 7.428-a6 Period

3. Percent Of Applicable Limit % *

C. Dissolved And Entrained Gases

1. TotalRelease ci 4.92E-05 5.51E-04 39%

2. Average Diluted Concentration During pcilml 6.768-12 5.89E-12 Period

3. Percent Of Applicable Limit % 3.38E-06 2.9sE-06 D. Gross Apha Radioactivity

1. Total Release Curies 0.000E+00 0.000E+00 N/6**

E. TotalWaste Volume Released Liters 1.51E+08 1.87E+08 2%

{Pre-Dilution}

F. Volurns Of Dilution Water Used Liters 7 .27 t+09 L.7 LE+10 12%

G, Radwaste Volume Released Liters 1.01t+06 1.38E+06 12%

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

Applicable limits are expressed in terms of dose. See Table 7-A 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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2016 Watts Bar Nuclear Plant Effluent and Waste DisposalAnnual Report TABLE 1-B Liquid Effluents - Summation of All Releases During the period Starting: 1-Jul-2016 Ending: 31-Dec-2016 Est. Tot Type Of Effluent Units Quarter 3 Quarter 4 Error o/o A. Fission & Activation Products

1. Total Release (Not lncluding ci 3.25E-03 4.20E-03 25o/o Tritium, Gases, Alpha)

2. Average Diluted Concentration pci/ml 2.71E-13 2.71E-13 During Period

3. Percent Of Applicable Limit % !t

B. Tritium

1. Total Release ci 1.15E+03 6.31E+02 Lg%

2. Average Diluted Concentration pcilml 9.59E-08 4.08E-08 During Period

3. Percent Of Applicable Limit % * 't C. Dissolved And Entrained Gases

1. Total Release ci 9.88E-04 4.32E-04 3f/o

2. Average Diluted Concentration pci/ml 8.23E-14 2.79E-14 During Period

3. Percent Of Applicable Limit % 4.128-08 1.40E-08 D. Gross Apha Radioactivity

1. Total Release ci 0.00E+00 0.00E+00 N/6**

E. TotalWaste Volume Released Liters 4.32E+08 2.27E+Og 2%

{Pre-Dilution}

F. Volume Of Dilution Water Used Liters 1.20E+13 1.55E+13 t2%

G. Radwaste Volume Released Liters 2.37E+06 1.66E+06 12%

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

Applicable limits are expressed in tenns of dose. See Table 7-B 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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2016 Watts Bar Nuclear Plant Effluent and Waste Disposal Annual Report TABLE 2-A Curies Released in Liquid Effluents During the period Starting: 1-Jan-2016 Ending: 31-Mar-201 6 CONTINUOUS BATCH TOTAL H-3 2.69t-0L 5.03t+01 5.05[+0],

FISSION & ACTIVATION PRODUCTS co-58 0.00E+00 3,.17tr-03 1.17[-03 c0-60 0.00E+ff0 2.978-44 2.87E-04 FE-55 0.00E+00 1.04E-03 3..04t-03 sB-L22 0.00E+00 4.14[-05 4.14E-06 sB-125 0.00E+00 1.52E-05 1.52E-05 SR-89 0.00E+00 3.75E-05 3.76E-05 TOTALS 0.00E+00 2.55E-03 2.55E-03 DISSOLVED AND ENTRAINED GASES xE-133 0.00E+00 4.92E-05 4.92E-05 TOTALS 0.00E+00 4.92E-05 4.92E-05 Zeroes in this table indicate that no radioactivity was present at detectable levels.

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201 6 Watts Bar Nuclear Plant Effluent and Waste Disposal Annual Report TABLE 2.8 Curies Released in Liquid Effluents During the period Starting: 1 -Apr-201 6 Ending: 30-Jun-201 6 CONTINUOUS BATCH TOTAL H-3 L.67 E-01 L.27 E+02 L27E+AZ FISSION & ACTIVATION PRODUCTS CO-58 0.008+00 1.06E-03 1.06E-03 C0-60 0"00[+00 4,77t-44 4.77*44 C5-L37 0.00[+00 9.59t-06 9.59E-06 FE-55 0.00[+00 2.28t-44 2.288-44 M N-54 0.008+00 2.30[-05 2.30[-05 58-L25 0.00[+00 1.65E-05 1.66E-05 TOTALS 0.00E+00 1.81,E-03 1.81E-03 DISSOLVED AND ENTRAINED GASES XE-133 0.00E+00 1.01E-04 1.01E-04 TOTALS 0.008+00 L.0LE-04 1.01E-04 Zeroes in this table indicate that no radioactivity was present at detectable levels.

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2016 Watts Bar Nuclear Plant Effluent and Waste Disposal Annual Report TABLE 2-C Curies Released in Liquid Effluents During the period Starting: 1-Jul-2016 Ending: 30-$ep-201 6 CONTINUOUS BATCH TOTAL H-3 2.80t-01 L.15E+03 l,.L5E+03 FISSION & ACTIVATION PRODUCTS co-58 0.00E+flO 3.31t-04 3.31E-04 c0-60 0.0SE+00 8.07[-04 8.07E-04 FE.55 0.CI0E+00 1.60E-03 1.60t-03 FE-59 0.00E+00 3.95E-06 3.958-06 r-134 0.00E+00 1.708-06 1.70r-05 MN-54 0.00E+00 4.39E-05 4.39[-05 NB-95 0.00E+00 1.098-05 1.08[-05 NB-97 0.00E+00 1,.288-06 1.28t-06 RU-105 0.00E+00 1.19E-05 3,.18tr-05 sB-125 0.00E+00 2.64E-04 2.S4[-04 sN-113 0.00E+00 9.49E-07 9.49[-07 SN.117M 0.00E+00 1.10t-06 3,.3.0E-06 ZN-65 0.00E+00 4.09[-06 4.09E-06 Nt-53 0.00E+00 1.70[-04 ],TAE-A4 TOTALS 0.00E+00 3.25t-03 3.25E-03 DISSOLVED AND ENTRAINED GAS*$

xE-133 0.00E+00 9.69E-04 9.69E-04 xE-135 0.00E+00 1.27E-05 1.27E-05 xE-138 0.00E+00 6.68E-06 6.58E-06 TOTALS 0.00E+00 9.88E-04 9.88E-04 Zeroes in this table indicate that no radioactivity was present at detectable levels.

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2016 Watts Bar Nuclear Plant Effluent and Waste Disposal Annual Report TABLE 2-D Curies Released in Liquid Effluents During the period Starting:'l-Oct-201 6 Ending: 31 -Dec-201 6 CONTINUOUS BATCH TOTAL H-3 2.24[-01 5.31E+02 6.31E+02 FISSIOH & ACTIVATION PRODUgTS co-58 0,00E+00 1.55r-04 1.55r-04 co-50 0.0S[+00 9.86t-04 9.85[-04 CR-51 0.00E+00 3..29[-05 1.29E-05 cs-137 0"00E+00 5.19[-05 5.19E-05 FE.55 0.00E+00 2.A78-43 2.A2E-43 FE.59 0.00E+00 7.798-46 7.798-46 MN.54 0.00E+00 5.388-05 5.38E-05 MN-55 0.00E+00 1.858-06 1.85E-06 N8.95 0.00E+00 2.29E-05 2.29E-05 sB-125 0.00E+00 8.52E-04 9.52E-04 sN-113 0.00E+00 4.40E-06 4.40E-06 w-187 0.00E+00 6.25E-06 6.25E-06 Y-92 0.00E+00 2.57E-05 2.57E-05 ZN-55 0.00E+00 4.63E-06 4,63E-06 TOTALS 0.00[+00 4.20E-03 4.20E-03 DISSOLVED AND ENTRAINED GAST$

xE-133 0.00E+00 4.24E-04 4.24r.-44 xE-135 0.S0E+00 4.05E-05 4.05E-05 xE-135M 0.S08+00 4.48E-06 4.48E-06 TOTALS O.0OE+00 4.32E-04 4.32E-04 Zeroes in this table indicate that no radioactivity was present at detectable levels.

E-16

2016 Watts Bar Nuclear Plant Effluent and Waste DisposalAnnual Report TABLE 3.4 Gaseous Effluents - Summation of All Releases During the period Starting: 1-Jan-2016 Ending: 30Jun-2016 Est. Tot Type Of Effluent Units Quarter 1 Quafter 2 Error olo A. Fission & Aetivation Froducts

1. Total Release ci 5.19E+00 2.88E+01 22%

2. Average Release Rate For Period pCilsec 5.50E-01 3.55E+00

3. Percent Of Applicable Limit % * '*

B. Radioiodines

1. TotalRelease ci 0.00E+00 0.00E+00 N/4**

2. Average Release Rate For Period pCi/sec 0.00E+00 0.00E+00

3. Percent Of Applicable Limit % 't

C. Particulates

1. Particulates (Half-Lives>8 Days) ci 4.46E-06 0.00E+00 Ls%

2. Average Release Rate For Period pCi/sec 5.67E-o7 0.00E+00

3. Percent Of Applicable Limit % * *

4. Gross Alpha Radioactivity Ci 0.00E+00 0.00E+00 N/4**

D. Tritium

1. Total Release ci 4.55E+00 8.15E+00 LL%

2. Average Release Rate For Period pCi/sec 5.79E-01 1.04E+00

3. Percent Of Applicable Limit % 't

E. Garbon-l4

1. Total Release ci 2.58E+00 2.78E+00 N/A

2. Average Release Rate For Period pCi/sec 3.29E-01 3.54E-01

3. Percent Of Applicable Limit % * 't 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.

E-17

2016 Watts Bar Nuclear Plant Effluent and Waste Disposal Annual Report TABLE 3,8 Gaseous Effluents - Summation of All Releases During the period Starting: 1-Jul-2016 Ending: 31-Dec-2016 Est. Tot Type Of Effluent Units Quarter 3 Quarter 4 Error olo A. Fission & Activation Products

1. Total Release ci 8.05E-01 1.21E+oo 22%

2. Average Release Rate For Period pCilsec 1.01E-01 1.52E-01

3. Percent Of Applicable Limit % * 'r B. Radioiodines

1. Total Release ci 3.798-07 2.s2E-06 12%

2. Average Release Rate For Period uCi/sec 4.778-08 3.77E-o7

3. Percent Of Applicable Limit % 'r 't G. Particulates

1. Particulates (Half-Lives>8 Days) ci 0.00E+00 0.00E+00 15%

2. Average Release Rate For Period pCilsec 0.00E+00 0.00E+00

3. Percent Of Applicable Limit % ;t '{'

4. Gross Alpha Radioactivity ci 0.00E+00 0.00E+00 Nfi**

D. Tritium

1. TotalRelease ci 1.78E+01 1.23E+o1 lL%

2. Average Release Rate For Period pCi/sec 2.248+00 1.55E+oo

3. Percent Of Applicable Limit % * :*

E. Carbon-l4

1. Total Release ci 3.23E+00 5.19E+00 N/A

2. Average Release Rate For Period pCilsec 4.05E-01 6.53E-01

3. Percent Of Applicable Limit % 'i

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

Applicable limits are expressed in terms of dose. See Table 68 of this report.

- N/A - Errors in measurements are not reported for these values since none were identified during the reporting period.

E- 18

2016 Watts Bar Nuclear Plant Effluent and Waste Disposal Annual Report TABLE 4.4 Curies Released in Gaseous Ground Level Relea$e$

During the period Starting: 1-Jan-2016 Ending: 31-Mar-201 6 CONTINUOUS BATCH TOTAL FISSION GASES KR-85 0.008+00 4.63E-47 4.63[-07 xE-135 0.00E+00 3.3.8E-02 3. L8[-02 xE-133 0.00E+00 2.3.5 E-01 2.158-01 AR-41 0.00E+00 4.95f+00 4.9ir+oo TOTALS 0.00E+00 5.19[+00 5.L9[+00 IODINES 0.00E+00 0.00[+00 0.00E+00 PARTICULTATE$

8R.82 2.76E-47 0.00[+00 2.76E-47 co-50 4.45E-05 0.00E+00 4.45E-06 TOTALS 4.73E-05 0.00E+00 4.73E-06 H-3 4.55E+00 0.00E+00 4.55E+00 C-14 {Total} 2.58E+00 0.00E+00 2.58E+00 C-14 tCO2 Form) 5.16E-01 0.00E+00 5.1$tr-01 Zeroes in this table indicate that no radioactivity was present at detectable levels.

E-19

201 6 Watts Bar Nuclear Plant Effluent and Waste Disposal Annual Report TABLE 4*B Curies Released in Gaseous Ground Level Releases During the period Starting: 1-Apr-2016 Ending: 30-Jun-201 6 CONTINUOUS BATCH TOTAL FISSION GASES KR-85 0.00E+00 3..45E-05 1.45E-06 XE.135M 0.00E+00 2.10E-01 2.10E-01 xE-135 0.00E+00 4.80E-03. 4.80E-01 xt-133M 0.00E+00 9.87 E-01 9.87E-01 xE-133 0.00E+00 5.46E+00 5.46E+00 AR.41 0.00E+00 2.L7E+At 2.17E+01 TOTALS 0.00E+00 2.88E+01 2.88E+01 IODINES 0.00E+00 0.00[+00 0.00E+00 PARTICULTAT=S 8R.82 6.33.r-06 0.00E+00 6.31E-05 TOTALS 6.33.r-06 0.008+00 6.318-05 fl-3 8.15E+00 0.00E+00 8.1,5E+00 C-14 {Total} 2.78[+00 0.00E+00 2.78E+00 C-14 tCO2 Form) 5.578-01 0,00E+00 5.57E-01 Zeroes in this table indicate that no radioactivity was present at detectable levels.

E-20

201 6 Watts Bar Nuclear Plant Effluent and Waste Disposal Annual Report TABLE 4.C Curies Released in Gaseous Ground Level Releases During the period

$tarting: 1-Jul-2016 Ending: 30-Sep-2016 CONTINUOUS BATCTI TOTAL FISSION GASES KR-85 0.008+00 4.628-47 4.628-47 KR-85M 0.00E+00 9.50E-05 9.50E-06 XE.133M 0.00E+00 3..63.E-04 L.61E-04 xE-135 0.00E+00 s.90E-04 6.90E-04 xE-133 0.008+00 9.79E-03 9.79E-03 AR.41 0.00[+00 7.95E-01 7.95E-01 TOTALS 0.00E+00 8.06E-01 8.06E-01 IODINES t-133 3.79E-07 0.00E+00 3.798-07 TOTALS 3.79E-07 0.00E+00 3.79E-07 PARTICULTATES 8R.82 8.078-07 0.00E+00 8.07E-07 TOTALS 8.07E-07 0.00E+00 8.07E-07 H-3 3..78E+01, 0.00E+00 3..78E+0L C-14 {Total} 3.23E+00 0.00E+00 3.23E+00 C-14 {COZ Form) 5.458-0L 0.00E+00 5.45E-01 Zeroes in this table indicate that no radioactivity was present at detectable levels.

E-21

2016 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-2A16 Ending: 31-Dec-2416 CONTINUOUS SATCH TOTAL FI$$ION GASES KR.85M 0.00[+0il s.75E-05 6.75E-05 KR-88 0.00[+00 8.86E-05 g.g6E-05 xE-133M 0.00[+CI0 1.96E-04 1.95E-04 xE-137 0.00[+00 8.35E-04 8.35E-04 xE-135 0.00E+00 \.22E-03 1.22E-03 xE-133 1.05E-0L 7.62E-03 1.14E-01 KR.85 0.00E+00 8.88E-03 8.88E-03 xE-138 0.00E+00 3.78E-02 3.78E-O2 AR-4L 0.00E+00 1.04E+00 1.04E+00 TOTALS 1.06E-0L L.L0E+00 L.ztE+00 IODINES t-133 2.52E-06 0.00E+00 2.52E-05 TOTALS 2.528-06 0.00E+00 2.52E-05 PARTICULTATES 8R.82 3.25[-09 0.00E+00 3.26E-09 TOTALS 3.25t-09 0.00E+00 3.26E-09 l{-3 L.23E+01 0.00E+00 1.23E+01 C-14 {Total} 5.19E+00 0.00E+00 5.19E+00 C-14 {CO2 Form} 1.04E+00 0,008+00 1.04E+00 Zeroes in this table indicate that no radioactivi$ was present at detectable levels.

E-22

2016 Watts Bar Nuclear Plant Effluent and Waste Disposal Annual Report TABLE 5.4 soLtD WASTE (RADlOACTlVE SHTPMENTS)

A. Solid Waste Shipped Offsite for Burial or Disposal (not lrradiated Fuel)

1. Tvpe of U\laste UNIT 12 Mottth Est. (Ci)

Period Error Yo a, Spent resins, filters, sludges, evaporator m3 4.503E+00 NIA bottoms, etc. Ci 1.150E+01 +l- 254/o

b. Dry Active Waste, Compressible Waste m3 2.260E+02 NIA Contarninated Equipment, etc. Ci 7.S608-02 +l- 25$/a m3 0.00 NIA

c. lrradiated Components, Control Rods, etc.

Ci 0.00 N/A

2. Estiqate of Maior Nuclide Cofft,p$r$jtiqn,.

{bv tvpe of wagtg}

{percent cutoff = 1.0 percent}

a. Spent resins, filters, sludges, evaporator tf uclide Percent Ci bottoms, etc. (nuclides determined by measurement H-3 1.822o/o 0.209 Cr-S1 1 .6134/o 0.1 85 Mn-54 2.725o/o 0.313 Fe-55 8.2340/a 0.947 Co-58 61 .802o/a 7,107 Co-60 11.2124/a 1.289 Ni-s3 9.004% 1.035 sb-125 1.847o/a 0.212

b. Dry Active Waste, Compressible Waste tl,u,c,lid,e Percent #,i Contaminated Equipment, etc. {nuclides determined by estimate)

Cr-S1 11.008% 0.0084 Co-58 33.084Ya 0.0253 Fe-55 18,8280/a 0.0144 Co-60 17 .7 45o/a 0.0136 Ni-63 10.858% 0.0083 sb-125 1.477o/o 0.0011 Cs- 137 1.A264/o 0.0008 Zr-95 1.4294/o 0.0011 Nb-95 2.2384/o 0.0017

c. lrradiated Components None N/A N/A E-23

2016 Watts Bar Nuclear Plant Effluent and Waste Disposal Annual Report TABLE 5.8 soLrD WASTE (RADTOACTIVE SHIPMENTS)

3. Solid Waste Disposition Number of Shipments Mode of Transnortation Destination 1 Motor Freight Energy Solutions Facility - Clive, UT I Motor Freight Waste Control Specialist - Andrews, TX 20 Motor Freight TOXCO - Oak Ridge, TN to Clive, UT or Chestnut Ridge

4. lrradiatedFuelShipments {Disposition)

Number of Shipments Tvpe Quantitv Mode of Transoortation Destination None N/A NIA N/A

5. Solidification of Waste Was solidification performed? No lf yes, solidification media: NIA E-?4

2016 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 ODCM. Measured plant releases for the reporting period are used to estimate these doses. Dispersion of radioactive effluents in the environment is estimated using meteorologicaldata and riverflow data measured during the period. ln this report, the doses resulting from releases are described and compared to limits established for WBN.

Dose Limits The ODCM specifies limits for the release of radioactive effiuents, 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 en$ures that radioactive effluent releases are As Low As Reasonably Achievable.

Dose Galculations 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, 1.11 1 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 NUREGICR-10O4. The values chosen willtend to overestimate the dose to this'maximum" person. The expected dose to aclual individuals is lower. The calculated doses are presented in Tables 6-A, 6-8, 7-A, and 7'8.

Doses From Airborne Effluents For airborne effluents, the public can be exposed to radiation from several sources: direct radiation from the radioactivity in the air, direcl 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 from the atmosphere onto vegetation and' subsequently eaten by milk and beef animals.

Airbome Discharqe Points All releases from WBN are considered ground-level releases. The ground-levelJoint 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 E-36 through E-63.

E-25

2016 Watts Bar Nuclear Plant Effluent and Waste Disposal Annual Report Radiological lmpact Meteorolooical Data Meteorological variables at WBN are measured mntinuously. 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 n/s (1.5 mph). Stability classes are determined from the verticaltemperature difference between two measurement levels.

ExternalExposure 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 Extemal 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.

Qrqan 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 beef, 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 contamination, 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 equalto the total body dose.

Doses from airborne effluents are presented in Tables &A and &B.

E-26

2016 Watts Bar Nuclear Plant Effluent and Waste Disposal Annual Report Radiological lrnpact Land Use Suruev e016 Land n Usese uurye S

Receptor Receptor Distance GPS Coordinates Terrain Adj.

Nurnber TyJre* $ector {ml N W Factor 1 NR N 4474 35,64275 84"79600 1.5 2 NR NNE 3750 35.63226 84.77014 1.8 3 NR NE 3399 35.62474 w.76l-12 2.3 4 NR ENE 3072 35.61506 84.75984 1.9 E

t/, NR E 4388 35.59959 w.74191 1.8 b NR ESE 4654 35.58139 44,74604 1.8 7 NR $E 1409 35.59439 84.77861 1.5 I NR ssE 1646 35.58963 84.78191 1,5 o NR Q

\, 1 550 35.58879 84.79047 1.8 10 NR ssw 1 832 35.58690 84.79567 1.9 11 NR SW 81 00 N/A N'A 1.7 12 NR WSW 2422 35.59270 84.81403 1.7 13 NR W 2901 35.60557 u.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 6295 35.65835 84"80361 1,1 18 NG NNE 5030 35.64057 84.75969 1.6 19 t{G NE 366I 35.62830 84,78470 2.2 20 NG ENH 3072 35.61506 84.75984 1.9 21 NG E 4650 35.60406 84"73881 1.S 22 NG rsE 7297 35.58398 84,71296 1.7 23 NG SE 1409 35.59439 84.77861 1.5 24 NG ssE 1711 35.58799 84.78504 1,5 25 NG S 2349 35.58178 84.79313 2,0 26 NG ssw 2286 35.58312 94.49693 2,0 27 NG sw 81 00 NIA N'A 1.7 28 NG W$W 3080 35,59324 84.82214 1.7 29 NG W 31 38 3s.60768 84.82446 1.1 30 NG WNW 2956 35,61417 84.81982 2.2 31 NG NW 2065 35.61308 84.80929 1.5 32 NG NNW 4742 35.64449 84.801 19 1.0 33 MC ESE 6706 35.57698 84^72141 1,7 34 MC ssw 2826 35.57806 84.79750 2.0

NR: Nearest Residence, NG: Nearest Garden, MC: Milk Cow New locations and/or Tenain Adjustment Factors are represented by being bolded" E-27

2016 Watts Bar Nuclear Plant Effluent and Waste DisposalAnnual 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 well as the parameters input to the models, are described in detail in the WBN ODCM.

Liquid Release Paints and River Data Radioactivity concentrations in the Tennessee River are calculated assuming that releases in liquid effluents are continuous. All routine liquid releases from WBN, 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 anyrhere 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 WBN, is an individual who obtains all of his drinking water at Dayton, TN, consumes fish caught from the Tennessee River between WBN and Chickamauga Dam, and spends 500 hours0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months 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 7-A and 7-B, along with the average river flows past the plant site for the periods.

Population Doses Population doses for highest exposed organ due to airborne effluents are calculated for a projected 2040 population distribution of 1,523,385 persons living within a 50-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 external pathways and inhalation are based on the 50-mile human population distribution.

Population doses for total 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 recreational data on the number of shoreline visits at downstream locations.

Population dose estimates for airborne and liquid effluents are presented in Tables 6-A, 6-8, 7-A and 7-8.

E-2&

2016 Watts Bar Nuclear Plant Effluent and Waste Disposal Annual Report Radiological lmpact Direct Radiation Extemal gamma radiation levels were measured by Landauer lnLight (optically stimulated luminescence dosimeters (OSLDS) deployed around WBN as part of the offsite Radiological Environmental Monitoring Program. The quarterly gamma radiation levels determined from these dosimeterc during this reporting period averaged 17.25 mR/quarter at onsite (at or near the site boundary) stations and 16.25 mR/quarter at offsite stations or 1.0 mR/quarter higher onsite than at ofhite 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 mRlquarter higher than the levels offsite. 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 srnall 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 boundaryfor an entire work year (2000 hours0.0231 days 0.556 hours 0.00331 weeks 7.61e-4 months ). Results from onsite dosimeter measurements indicated that the highest annual dosimeter reading outside Radiological Control Area was 144 mrem. Using this value, subtracting an annual background value of approximately 69.0 mrem/year (see previous seclion), 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 17.1 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 individualfrcm WBN radioactive effluents and allother 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 (for any organ other than the thyroid) from airborne effluents for each quarter from ground contamination, inhalation and ingestion, the totalbody 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.

E-29

2016 Watts Bar Nuclear Plant Effluent and Waste Disposal Annual Report TABLE 6-A Doses from Airborne Effluents First Quarter l,nflividual DoEgS Pathway Dose Quarterly Percent of Location X'Q D'Q Lirnit Limit External Gamma Air 1.51E-02 mrad 5 rnrad E.11280 meters 1.33E-05 1.34E-08 Beta Air 5,43E-03 mrad t0 mrad El128A meters 1.33E-05 1.34E-08 Submersion Total Body 6.11E-03 mrad N/A N/A SE/1409 meters 5.50E-oS 9,108-09 Skin 9.00E-03 mrad N/A N/A SE/1409 meters 5.50E-06 9.10H-09 Organ Doses' (Max) Child/Bone 5.73E-01 mrem 7.5 mrem 7,644/a SE/1409 meters 5.50E-06 9.10E-09 Childffhyroid 1.248-01 mrem 7.5 mrem 1,65o/a SE/1409 meters 5.50E-06 9.108-09 Child/Total Body 1.248-01 mrem 7.5 mrem 1.65% SE/1409 meters 5.50E-06 9.108-09 Population *gqqs Total Body Sose 2.46E-01 man-rem Maximum Organ Dose (Organ) 1.14E+00 man-rem (Bone)

Second Quarter lndivi$ual Doseq Pathway Dose Quarterly Percent of Location X'Q D/Q Limit Limit External Gamma Air 1.13E-01 mrad 5 rnrad 2.260/o E.11280 meters 2.34r-05 1.66E-08 Beta Air 4.53E-02 mrad 10 mrad El128A meters ?.34E-05 1.66E-08 Subrnersion Total Body 2.44f-02 mrad N/A N/A SEl1409 meters 5.1 1E-06 7.92E-09 Skin 3.64E-42 mrad N/A N/A SE/1409 meters 5.1 1H-06 7.92F-09 Organ Doses

{Max) Child/Bone 7,50E-01 mrem 7 .5 mrern 10. 1o/o ENEI3A72 meters 5.s0E-06 3.23E-09 Child/Thyroid 1.748-01 mrem 7.5 mrem 2.324/a ENE/3472 meters 5.50E-06 3.23E-09 Child/Total Body 1.74F-01 mrem 7.5 mrem 2.32*1o f Nfl3072 meters 5.50E-06 3.23E-09 Population Doses Total Body Dose 3.92E-01 man-rem Maximum Organ Dose (Organ) 1.71E+00 man-rem (Bone)

Population doses can be compared to the natural background dase for the entire 50-mile population of about 210,000 man-rem/year (based on 140 mrem/yr for naiural background).

lOrgan Doses include contributions from Carbon 14 as carbon dioxide E-30

2016 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 X'Q D'Q Limit Lirnit External Gamma Air 4.17E-03 mrad 5 rnrad ESE/1 250 meters 2.38r*05 1.45E-08 Beta Air 1.48E-03 mrad 10 mrad ESE/1 254 meters 2.388-05 1.45E-08 Subrnersion Total Body 1.64E-03 mrad N/A N/A SE/1409 meters 1.008-05 8.30E-09 Skin 2.41 E-03 mrad N/A N/A SEl1409 meters 1.00E-05 8.30E-09 Organ Doses' (Max) Child/Bone 1,31 E+00 mrem 7.5 mrem 17,54/a SE/1409 meters 1.00E-05 8.30E-09 Child/Thyroid 2.95E-01 mrem 7.5 mrem 3.93% SEl1409 meters 1.00E-05 8.30H-09 Child/Total Body 2.95E-01 mrem 7.5 mrem 3.93% SE/1409 meters 1.00E-05 8.30H-09 Popu,lation Dosg#.

Total Body Dose 4.82E-01 man-rem Maximum Organ Dose (Organ) 1.97 E+00 man-rem (Bone)

Fourth Quarter lndividual Doses Pathway Dose Quarterly Percent of Location X'Q D'Q Lirnit Limit External Gamma Air 6.78E-03 mrad 5 mrad ESE/1250 meters 2,9SH-05 1.98E-08 Beta Air 2.51 E-03 mrad 10 mrad ESE/1 250 meters 2.s0r-05 1.98E-08 Subrnersion Total Body 2.31 E-03 mrad N/A N/A SEl1409 meters 1.07E-05 8.61E-09 Skin 3.427-03 mrad N/A N/A SE/1409 meters 1.07E-05 9,61 E-09 Organ Doses' (Max) Child/Bone 2.30E+00 mrem 7 -5 mrern 30.6% Sil1409 meters 1.07E-05 8.61E-09 Childffhyroid 4.84E-01 mrem 7.5 mrem 6,454/o Sf/1409 meters 1.07E-05 8.61 E-09 Childffotal Body 4.84E-01 mrem 7.5 mrem 6.45% Sil1409 rneters 1.07E-05 8.61E-09 Pooulation Doses Total Body Dose 7.25E-O1 man-rem Maximum Organ Dose (Organ) 3.30E+00 man-rem (Bone)

Population doses can be compared to the natural background dose forthe entire $O-mile population of about 210,000 man-rem/year (based on 14A mrem/yrfor natunlbackground).

lOrgan Doses include contributions from Carbon 14 as carbon dioxide E-3 I

2016 Watts Bar Nuclear Plant Effluent and Waste Disposal Annual Report TABLE 7.A Doses from Liquid Effluents First Quarter lndividual Doses (mrem)

Aae Group Orqan Dose Quarterly Limit Percent of Limit chitd Total Body 1.50E-A4 1.5 mrem chitd Bone 1.60r-04 5 mrem ChiId Thyroid 1.50E-04 5 mrem Average Riverflow past WBN (cubic feet per second): 50,341 Po?,ulation Dos-g$

Total Body Dose 1.2AE-02 man-rem Maximurn Organ Dose (Organ) 1.20E-02 man-rem (Bone)

Second Quarter lndividual Doses (rnrernl Ace Group Organ Dose Quarterly Limit Percent of Limit chitd Total Body 2.308-03 1.5 mrem chitd Bone 2.30E-03 5 mrem chitd Thyroid 2"30H-03 5 mrem Average Riverflow past WBN (cubic feet per second): 8,005 Population Doses TotalBody Dose 1.80E-01 man-rem Maximum Organ Dose (Organ) 1.80E-01 man-rem (Bone)

Population doses can be compared to the natural background dose for the entire Sfumile population of about 210,000 man-rem/year (based on 144 mrem/yr for natural background).

E-32

watts trr',l 1,3*"r Plant Effluent and Waste Disposal Annual Report TABLE 7.8 Doses from Liquid Effluents Third Quarter lndividual Doses (mrem)

Age Group Orqan Dose Quarterly Limit Percent of Limit chitd Total Body 9.70H-03 1.5 mrem chitd Bone 9.808-03 5 mrem child Thyroid 9.708-03 5 mrem Average Riverflow past WBN {cubic feet per second): 15,748 Population Doses Total Body Dose 8.90E-01 man-rem Maximum Organ Dose (Organ) 8.90E-01 man-rem (Bone)

Fourth Quarter ln-4iyidual P-flqes {mren*

Age Group Organ Dose Quarterly Limit Percent of Limit ChiId Total Body 6.10E-03 .5 mrem Adult Bone 6.20E-03 5 mrem child Thyroid 6.00H-03 5 mrem Average Riverflow past WBN (cubic feet per second): 14,181 Population Doses TotalBody Dose 5.50E-01 man-rem Maximum Organ Dose (Oryan) 5.50E-01 man-rem (Bone)

Population doses can be campared to the natural background dose for the entire Sfumile population of about 21A,A00 man-rem/year (based on 140 mrem/yrfor naturalbackground).

E-33

2016 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 Total Body or any Organ (except thyroid)

Total body 6.11E-03 2.44=-02 1.S4E-03 2.31E-03 air (submersion)

Critical organ 5.73E-01 7.56E-01 1.31 E+00 2,30E+00 dose (airborne)

Total body 1.50E-04 2.30E-03 9.708-03 $.10E-03 dose (liquid)

Maximum 1.608-04 2.30E-03 9.80E-03 6.20E-03 organ dose (liquid)

Direct 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Radiation Dose Total 5.79H-01 7.85E-01 1.33E+00 2.31E+00 Cumulative Tota Dose {mrem} 5.01 E+00 Annual Dose Limit {mrem} 25 Percent of Lirnit 2A.0a/o Thyroid Total body 6.11E-03 2.448-42 1.64E-03 2.31H-03 air (submersion)

Thyroid dose 1.24E-01 1.74F-01 2,95E-01 4.94E-01 (airborne)

Total body 1.50E-04 2.30E-03 9.70E-03 6.10E-03 dose (liquid)

Thyroid dose 1.508-04 2.308-03 9.70E-03 6.00E-03

{liquid)

Total 1.30E-01 2,03E-01 3.'l6E-01 4.98E-01 Cumulative Tota Dose (mrem) 1 .15E+00 Annual Dose Limit (mrern) 75 Percent of Lirnit 1.53%

E-34

2016 Watts Bar Nuclear Plant Effluent and Waste Disposal Annual Report lndependent Spent Fuel Storage lnstallation The Tennessee ValleyAuthority (TVA) selected the Holtec lnternational Storage Module (HI-STORM)

FloodAffind (FW) Multi-Purpose Canister (MPC) Storage System for storage of spent fuel at the Watts Bar Nuclear (WBN) Plant lndependent Spent Fue[ Storage lnstallation (lSFSl). The HI-STORM FW MPC Storage System has been reviewed and approved by the Nuclear Regulatory Gommission (NRC) and Certificate of Compliance (CoC) number 1032 Title 10 CFR 72.104, Criteria for radioactive materials in effluents and direct radiation from an lSFSlor Monitored Retrievable Storage lnstallation (MSRI), requires that the annual dose equivalent to any real individual, located beyond the controlled area, must not exceed 25 millirem (mrem) to the whole body, 75 mrem to the thyroid, and 25 mrem to any other critical organ, as a result of exposure to direct radiation from ISFSI operations.

WBN successfully placed its first loaded HI-STORM FW on the ISFSI pad on October 5,2016. The TVA ISFSI storage pad is located within the plant's protected area. The storage pad is designed to adequately support both static and dynamic loads of 80 loaded Holtec HI-STORM FW MPC Storage Systems.

Currently, the storage pad contains six canisters.

The off-site dose for normal operating conditions to a real individual beyond the controlled area boundary is limited by 10 CFR 72.104(a) to a maximum of 25 mrem/year whole body, 75 mrem/year thyroid, and 25 mrem/year for other critical organs, including contributions from all nuclear fuel cycle operations. For this report, total site releases include the WBN ISFSI as part of plant operations. By its design, there were no liquid or gaseous effluents from the operation of the ISFSI during 2016.

Radiological Environmental Monitoring Program assessment of direct radiation exposure by dosimeters at or near the site boundary is 3.Tmremlyr for onsite locations. As stated in the WBN ODCM and per this report, the dose to a member of the public inside the unrestricted boundary is then performed. Results from onsite dosimeter measurement and subtracling fourth quarter average background indicated that the highest dosimeter reading at the boundary of the protected area was I 1.4 mrem for the north location 17025.

Based on the above measurements performed during this reporting period, lt can be concluded that the radiation exposure due to the lSFSl, combined with all other fuel cycle operations, will not exceed the regulatory requirements of 25 mrem/year in 't0 CFR 72.104(al and 40 CFR Part 190.

E-35

201 6 Watts Bar Nuclear Plant Effluent and Waste Disposal Annual Report

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When 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 Environmental Operating Report described in ODCM Administrative Control 5.1. The methodology and parameters used to delermine the potential annual dose to a MEMBER OF THE PUBLIC shall be indicated in this report.

I,1'BN TWO.UNIT OFFSITE DOSE CALCULATION Revision { 0 MANUAL {ODCM} Page 38 of 205 1'2 CONTROLS AND SURVEILLANCE REOUIREMENTS 1'2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING 1 12.3.1 MONITORING PROG RATI/I ACTION (CONTINUED):

c. With milk or fresh leafy vegetation samples unavailable from one or more of the sample locations required by Table 2.3-1, identify 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 identifying the cause of the unavailability of samples and justifying the selection of the new location(s) for obtaining samples. The provisions of SR 2.0.4 arc not applicable. SURVEILLANCE REOU IREMENTS 2.3.1 The radiological environmental monitoring samples shall be collected pursuant to Table 2.3-'l 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 and2.3-4. lsouRcE NoTE 6I

WBN TWO.UNIT OFFSITT DOSE CALCULATION Revision I 0 MANUAL {ODCM} Page 39 of 205 Tabte 2.3 MlNlMuM REQUIRED RADIOLOGICAL ENVIRONiiENTAL MONITORING PROGRAM (Page '1 of 5) Exposure Pathway and/or Number of Samples and Sampling and Tlpe and Frequency of Sarnple Sample Locationsl Collection Frequency Analyses

1. DIRECT RAD ATION Forty routine monitori ng 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 general 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 ienters, 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 l-1 31 analysis weekly Particulates the three UNRESTRICTED sample collection AREA BOUNDARY locations weekly, o[ more Particulate sampler: in different sectors of the frequently if required Gross beta highest calculated annual by dust loading. radioactivity analys is average ground-level D/Q; following filter One sample from the vicinity changeo and gamma of a community having the isotopic analysist of highest calculated annual cornposite (by average ground levet D/Q; location quarterly) and One sample from a control location, a$ for example 15 - 30 km distant and in the least prevalent wind direction3

WBN TWO.UNIT OFFSITE DOSE CALCULATION Revision I 0 MANUAL {ODCM} Page 40 of 205 Table2.3-1-MlNlMuM REQUIRED RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAIII (Page 2 of 5) Exposure Pathway and/or Number at Samples and Sampling and Tlpe and Frequency of Sample Sample Locations Collection Frequency Analyses

3. WATERBORNE Surface One sample upstream. Composite sample Gamma isotopic One sample downstream. over a 1-month analysiss monthly; period.T composite for tritium analysis quarterlv.

Ground Samples from one or two At least once per 92 Gamma isotopict and sources only if likely to be days tritium analysis affected I quarterlv. Drinking One sample of each of one to Composite sample Gross beta and three of the nearest water over a one month gamma isotopic supplies that could be period.T analysest monthly. affected by the dischargee Composite for tritium analysis quarterlv. Shoreline One Sample from Semiannually Gamma isotopic' 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 anni,rally Sediment Pond

4. INGESTION Mitk Samples from milking Semimonthly when Gamma isotopic" 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 pa$ture; there are none, then CIne monthly at other times.

additional sample from milking anirnals in each of one to three areas between 5 to I km distant where doses are calculated to be qreater v than 1 mrem/yr'o One sample from milking animals at a control location 15-30 km distant and in the least prevalent wind d irection.3

WBN TWO.UNIT OFFSITE DO$E CALCULATION Revision 1 0 MANUAL (ODCM) Page 41 of 205 Table 2.3-1 MINIMUM REQUIRED RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (Page 3 of 5) Exposure Pathway andror Number of Samples and Sampling and Type and Frequency of Sample Sample Locations' Collection 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 recreationally 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 discharoe. Food One sample of each principal At time of harvest' Gamma-isotopic Products class of food products frorn analysiss on edible any area within 5 miles of the portion. 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 locations 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 least prevalent wind direction if milk sampling is not oerformed as outlined in 4.a. above,3

WBN TWO.UNIT OFFSITE DOSE CALCULATION Revision I 0 MANUAL (ODCM) Page 42 of 205 Table 2.3-l - MINIMUM REQUIRED RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (Page 4 of 5) TABLE NOTATION 1 Specific parameters of distance and direction sector from the centerline of the Unit 1 Shield Building stack, and additional description wfiere pertinent, shall be provided for each and every sample location in Table 2.3-1 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.'l . 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 justifying the selection of the new location(s) forobtaining samples. 2 Reserved for future use. 3 The purpose of this sample is to obtain background information. lf it is not pr:actical to establish control locations in accordance with the distance and wind direction criteria, other sites that provide valid background data may be substituted. 4 Airborne particulate sample filters shall be analyzed for gross beta radioactivity 24 hours 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 epntrol samples, gamma isotopic anallais shall be performed on the individual samples. 5 Gamma isotopic analysis means the identification and quantification of gamma-emitting radionuclides that may be attributable to the effluents from the WBN planl 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.

WBN TWO.UNIT OFF$ITE DOSE CALCULATION Revision t 0 MANUAL {ODCM} Page 43 of 205 Table 2.3 i,llNlMUM REQUIRED RADIOLOGICAL ENVIRONMENTAL MONITORING 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.g., monthly) in order to assure obtaining a representative sample. The composite sample shall be preserved according to plant procedures as appropriate. I Groundwater samples shall be taken when this sourse is tapped for drinking or inigation 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. However, sampling is being performed as specified in Table 9.1. 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 shallbe monthly. Attention shall be paid to including samples oftuberous and rootfood products.

WBN TWO.UNIT OFFSITE DOSE CALCULATION Revision I 0 MANUAL (ODCM) Page M of 205 Table2.3 REPORTING LEVELS FOR RADIOACTIVITY CONCENTRATIONS lN ENVIRONMENTAL SAMPLES Airborne Food Water Particulate or Fish Products Analysis (pCi/L)3 gase$ (p0i/m3ls (pCi/Kg, wetla Milk {p0ill}3 {pCi/Kg, wet}a H-3 20,000 N/A N/A NIA N/A Mn-54 1,000 N/A 30,000 NIA N/A Fe-59 400 NIA 10,000 N/A N/A Co-58 1,000 N/A 30,000 N/A NIA Co-60 300 N/A 10,000 N/A N/A Zn-65 300 NIA 20.000 N/A N/A Zr-Nb-95 400 N/A N/A NIA N/A t-1 31 22 0.9 N/A 3 100 Cs-1 34 30 10 1,000 60 1,000 Cs-1 37 50 2A 2,000 7A 2,000 Ba-La-140 200 N/A N/A 300 N/A 1 Reserved for future use. 2 For drinking water samples. lf no drinking water pathway exists, value of 20 pCi/L may be used. a Uufiply the values in this column by 10-e to convert to units of pCi/ml. a Multipty the values in this column by 10-e to convert to units of pCi/g (wet). 5 Multiply the values in this column by 10-12 to convert to units of pCi/cc.

WBN TWO.UNIT OFFSITE DOSE CALCULATION Revision 1 0 MANUAL (ODCM) Page 45 of 205 Table 2.3-3. DETECTION CAPABILITIES FOR ENVIRONMENTAL SAITIPLE NXIUYSIS,,,. LOWER LtinTs oF DETECTTON 1Ur-O;' (Page 1 of2) Airborne Particulate Food Yllater or Gases Fislr {pCj/Kg, Milk Products $ediment Analwis (pCiJL)g {pCi/m3}8 wet)' (pCi/L)G (pCi/Kg, wet)7 {pCi/Kg,dry}t gross beta 4 0.01 N/A NIA N/A NIA H-3 20004 NIA NIA NIA N/A N/A Mn-54 15 NIA 130 N/A N/A N/A Fe-59 30 N/A 284 N/A NIA N/A Co-58. 60 15 NIA 130 N/A N/A NIA Zn-65 30 NIA 260 N/A NIA N/A Zr-95 30 N/A N/A N/A N/A N/A Nb-95 15 N/A NIA NIA N/A N/A t-131 15 0.07 N/A 1 60 N/A Cs- 134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba-140 60 N/A NIA 60 N/A NIA La- 140 15 N/A N/A 15 N/A N/A TABLE NOTATION 1 This list does not mean that only these nuclides are to be considered. Other nuclides that are identifiable, together with those of the above nuclides, shall also be analyzed and reported in the Annual Radiological Environmental Operating Report pursuant to Administrative Control 5.1. 2 Required detection capabilities for DOSIMETERs used for environmental measurements shall be in accordance with the recommendations of Regulatory Guide 4.13. 3 The LLO is defined, for the purpose of these specifications, as the smallest concentration of radioactive material in a sample that will yield a net count, above system background, that will be detected with 95% probability with only a 5o/o probability of falsely concluding that a blank observation represents a "real" signal. (Reference 8) For a particular measurement system (which may include radiochemical separation): 4'66s0 LI-D= , . Ev 2.22v ery( i"at) Where: LLD = the "a priori" lower limit of detection (pCi per unit mass or volume) ss = the standard deviation of the background counting rate or of the counting rate of a blank sample a$ 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

WBN TWO-UNIT OFFSITE DOSE CALCULATION Revision I 0 MANUAL {ODCM} Page 40 of 205 TAbIE 2.33. DETECTION CAPABILITIES FOR ENVIRONMENTAL SAIIIPLE ANALYSlsi.2. LOWER LTMTTS OF DETECTTON 1r-r-O;s (Page 2 of 2) Y = the fractionalradiochemical yield, when applicable l = the radioactive decay constant for the particular radionuclide (s{) At = the elapsed time between midpoint of environmentalsample collection and time of counting (s). Tlpical values of E, V, Y, and At should be used in the calculation. It should be recognized that the LLD is defined as an gpglg$ (before the fact) limit representing the capability of a measurement slatem and not an a posteriori (after the fact) limit for a particular measurement. Analysis will be performed in such a manner that 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 Mu[iply the values in this column by 10-s to convert to units of pCi/ml. 7 Muftipty the values in this column by 10-e to convert to units of pCi/g(wet). I Mu[iply the values in this column by 1Q-12 to convert to units of pCi/cc. Table 2.34- DETECTION CAPABILITIES FOR GROUNDWATER HARD-TO-DETECT NUCLTDES - LOI'I,ER LtMtTS OF DETECTTON (LLD) ANALYSI$ I,I,ATER {pCi,L}, Fe-55 200 Ni-63 30 Sr-89 5

                                                                             ,l Sr-90 Gross Alpha                                   4 1 Multiply the values in this column by 10-s to conveft to units of prCi/ml.

WBN TWO.UNIT OFFSITE DOSE CALCULATION Revision I 0 MANUAL (ODCM) Page 47 of 205 1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS 1 /2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING 1I2.3.2LAND USE CENSUS CONTROLS 1.3.2 A Land Use Census shall be conducted and shall identifo within a distance of 8 km (5 miles) the location in each of the 16 meteorological sectors of the nearest milk animal, the nearest residence, and ihe nearest garden'of greater than 50 m2 1500 ff ) producing fresh leafy vegetation.

       " Broad leaf vegetation sampling of at least three different kinds of vegetation may be performed at the UNRESTRICTED AREA BOUNDARY in each of $ro different direction sectors wiih the highest predicted DlQs in lieu of the garden census. Controls for broad leaf vegetation sampling in Table 2.3-1 Part 4.c., shall be followed, including analysis of control samples.

APPLICABILITY: At all times. ACTION:

a. With a Land Use Survey identifying a location(s) that yields a calculated dose or dose commitment greater than the values cunently being calculated in Control2.2.2.3, pursuant to ODCM Administrative Controls 5.1 and 5.2, identify the new location(s) in the next Annual Radioactive Effluent Release Report.

b. With a Land Use Census identifying a location(s) that yields a calculated dose or dose commitment (via the same exposure pathway) 20% greater than at a location from which samples are cunently 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 progmm given in ODCM Section 9.0, if samples are available. The sampling location(s), excluding the controlstation location, having the lowest calculated dose or dose commitnent(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 lhe next Annual Radioaclive 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.

SURVEILLANCE 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.

VTIBN TWO.UNIT OFFSITE DOSE CALCULATION Revision I 0 MANUAL (ODCM) Page 48 of 205 1/2 CONTROLS AND SURVEILLANCE REQUIREMENTS 1'2.3 RADIOLOGICAL ENVIRONMENTAL MONITORING 1 12.3.3 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 conespond to samples required by Table 2.3-1. APPLICABILITY: At all times. ACTION: With analyses not being performed as required above, report the corrective actions being taken to prevent a recurrence 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. SURVEILLANCE REOU IREMENTS 2.3.3 The lnterlaboratory Comparison Program shall be described in ODCM Section 9.4. 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.'t.

WBN TWO.UNIT OFFSITE DOSE CALCULATION Revision 1 0 MANUAL {ODCM} Page 49 of 205 BA$ES FOR SECTIONS 1.0 AND 2.A C9NTROL$ Aryp $URVETLLANCE REQUTREMENTS NOTE The BASES contained in succeeding pages summ arize the reasons for the Controls in Sections 1.0 and 2.A, but are not part of these Controls.

WBN TWO.UNIT OFFSITE DOST CALCULATION Revision 1 0 MANUAL (ODCM) Page 50 of 205 BASES FOR SECTIONS 1.0 AND 2.O.CONTROLS AND SURVEILLANCE REQUIREMENTS ,tn.l INSTRUMENTATION 1 I'12.1,1 RADIOACTIVE LIQU ID EFFLU ENT MONITORI NG INSTRUM ENTATION The radioactive liquid effluent lnstrumentation 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 OPERABILITY and use of this instrumentiation is consistent with the requirements of General Design Criteria 60, 63, and &l of Appendix A to 10 CFR 50. 1 12,1.2 RADIOACTIVE 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 practical to 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 Section 7.'t to ensure that the alarm/trip will occur prior to exceeding the dose rate limits of ODCM Control 1.2.2.1. The OPERABILITY and use of this instrumentation is consistent with the requirements of General Design Criteria 60, 63, and 64 of Appendix A to 10 CFR 50. 1 12.1.3 M ETEOROLOGICAL INSTRUMENTATION'DATA The OPERABILITY of the meteorological instrumentation ensures that sufficient meteorologicaldata 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, ANSI/ANS-3.11-2000, 'Standard for Determining Meteorological lnformation at Nuclear Power Sites,n 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 sensor calibration 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.

WBN TWO.UNIT OFFSITE DOSE CALCULATION Revision 1 0 MANUAL {ODCM} Page 51 of 205 1/2.2 RADIOACTIVE EFFLUENTS 1 12.2.1 LIQUID EFFLUENTS I 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 2 to 10 CFR 20.1001-20.2402. lt provides operationalflexibilityfor releasing liquid effluents in concentrations to follow the Section ll^A and ll.C design objectives of Appendix lto 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 objectives of Appendix l, 10 CFR 50, to a MEMBER OF THE PUBLIC, and (2) restrictions authorized by 10 CFR 20.1301(e). The concenlration limit for dissolved or entrained noble gases is based upon the assumption thatXe-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 radioactive 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-215 (June 1975). 1t2.2.t.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 Controlwill be considered to demonstrate compliance with the 0.1 rem limit of 10 CFR 20.1301(a)(1) 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 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 appropdate 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 l,' 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 l,' April 1 977. This Control applies to the release of radioactive materials in liquid 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 to each of the radioactive producing units sharing the Radwaste Treatnent System.

WBN TWO.UNIT OFFSITE DOSE CALCULATION Revision 1 0 MANUAL {ODCM} Page 52 of 205 For determining conformance to controls, these allocations from shared Radwaste Treatmenl Systems are to be added to the releases specifically attributed to each unit to obtain the total release per site. For those nuclides whose activilies are detennined 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 LIOUID RADWASTE TREATMENT SYSTEM The OPERABILITY of the LRTS ensures that this system will be available for use whenever liquid effiuents require treatment prior to release to the environment. The Controlthat the appropriate portions of this system be used when specified provides assurance that the releases of radioactive materials in liquid effluents will be kept'as low as reasonably achievable." This requirement implements the requirements of 10 CFR 50.36a, General Design Criteria 60 of Appendix Ato 10 CFR 50 and the design objective given in Section ll.D of Appendix lto 10 CFR 50. The specified limits goveming 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 II2,2.2.1DOSE 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 operationalflexibility for releasing gaseous effluents to satisfy the Section ll.A and ll.C design objectives of Appendix I to 10 CFR 50. For MEMBERS OF THE PUBLIC who may at times be within the GONTROLLED or RESTRICTED AREAS, the occupancy of that MEMBER OF THE PUBLIC will usually be sufficiently low to compensate for the reduced atmospheric dispersion relative to that for the 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 restrict, at all times, the corresponding gamma and 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 mremly to the skin. These limits also restrict, at all times, the conesponding 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 maierial 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, !!{$f@, Cuffie, L. A., "Limits for Qualitative Detection and Quantitative Determination - Application to Radiochemistry," Anal. Chem.40, 586-93 ('t968), and

WBN TWO.UNIT OFFSITE DOSE CALCULATION Revision 1 0 MANUAL (ODCM) Page 53 of 205 Hartwell, J. K., "Detection Limits for Radioanalytical Counting Techniques," Atlantic Richfield Hanford Company Report ARH-SA-215 (June 1975). 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 perfonn the calculations in ODCM Sections 7.2. 1I2.2.2.2DOSE - 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 FR 23374. 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 lll.A of Appendix I that conformance with the guides of Appendlx 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 7.3 for 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

't.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 11, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors," Revision 1, July 1977. The equations provided for determining the air doses at and beyond the UNRESTRICTED AREA BOUNDARY are based upon the historical average atmospheric conditions.

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 contribuiions 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 Treaiment Synstems are to be added to the releases specifically attributed to each unit to obtain the total release per site. 112.2.2.9 DOSE - IODINE-131, IODINE-I33, C-14, TRITIUM, AND RADTONUCLTDES tN PARTTGULATE FORM WTH HALF.LIVES GREATER THAN 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 controlwillbe considered to demonstrate compliance with the 0.1 rem limit of 10 CFR 20.1301(a)(1) per 56 FR23374. The ACTION to be taken provides the required operating flexibility 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 actual release rates of the subject materials are consistent with the methodologies provided in NUREG/CR-1004, 'A StatisticalAnalyeis of Selected Parameters for Predicting Food Chain Transport and lnternal Dose of Radionuclides," October 1979 and Regulatory Guide 1.109, "Galculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purposes of Evaluating Compliance with 10 CFR Part 50,

WBN TWO-UNIT OFFSITE DOSE CALCULATION Revision I 0 MANUAL (ODCM) Page 54 of 205 Appendix l,' Revision '1, October 1977 and Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water Cooled Reactors,u Revision 1, July 't977. These equations also provide for determining the actual doses based upon the historical average atmospheric conditions. The release rate controls for l-13't, l-133, C-14, tritium and particulate radionuclides with half-lives greater than eight daya 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 airbome radionuclides, (2) deposition of radionuclides onto green leafy 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. 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 pedod to perform the calculations in ODCM Section 7.4. 1 12.2.2.4 GAS EOUS RADYI'ASTE TREATM ENT SYSTE i,I The OPERABILITY 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 Appendix A to 10 CFR 50, and the design objectives given in Section ll.D of Appendix lto 10 CFR 50. The specified limits goveming 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, ihe 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 speciflcally 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 GFR 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 willdescribe 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 fuel cycle sources is negligible, with the exception that dose contributions from other nuclear fuel cycle facilities at the same site or within a radius of I 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 Reportwith a requestfor a variance (provided the release conditions resulting in violation of 40 CFR 190 have not already been conected), in accordance with the provisions

WBN TWO.UNIT OFFSITE DOSE CALCULATION Revision 1 0 MANUAL (ODCM) Page 55 of 205 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 I 0 CFR 20, as addressed in ODCM Controls 1 .2.1.1 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 canying out any operation that is part of the nuclear fuel cycle. Demonstration of compliance with the limits 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 20.1301. 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. RADIOLOGICAL ENVIRONMENTAL MONITORING ',2.3 1 12.3.1 MONITORING PROGRAI/l 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 I to 10 CFR 50 and thereby supplements the Radiological Effluent Monitoring Program by verifying 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 operational experience. The required detection capabilities for environmentat 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 q p{9{ (before the fact) Iimit representing the capability of a measurement system and not as q 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, .l!$s3!.Q, 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-215 (June 1975). 112.3.2 LAND USE GENSUS 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-to-door survey, mail survey, telephone suryey, aerial survey, or by consulting with local agricultural authorities shall be used. This census satisfies the requhements of $ection lV.B.3 of Appendix I to 10 CFR 50. Restricting the census to gardens of greater than 50 m2 provides assurance that significant exposure pathways via leafy vegetables will be identified and monitored since a garden of this size is the minimum required to provide the quantity (26 kg/y) of leafy vegetables assumed in Regulatory Guide 1 .1 09 for consumption by a child. To determine this minimum garden size, the following assumptions were used, 1) that 20% of the garden was used for growing broad leaf vegetation (i.e., similar to lettuce and cabbage), and 2) a vegetation yield of 2 kg/m2.

WBN TWO.UNIT OFFSITE DOSE CALCULATION Revision 1 0 MANUAL (ODCM) Page 56 of 205 1 12,3.9 INTERLABORATORY COMPARISON The Control for 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 assurance 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.

WBN TWO.UNIT OFFSITE DOSE CALCULATION Revision 1 0 MANUAL {ODCM} Page 57 of 205 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 ACTION ACTION shall be that part of a Confol that prescribes remedial measures required under designated conditions. 3.2 CHANNEL CALIBRATION A CHANNEL CALIBRATION shall be the adjustment, as neoessary, of the channel such that it responds within the necessary range and accuracy to known values of input. The CHANNEL 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. Whenever a sensing element is replaced, &e 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 totalchannelsteps such that the entire channel is calibrated. 3.3 CHANNEL CHECK A CHANNEL CHECK shall be the qualitative assessment, by observation, of channel behavior during operation. This determination shall include, where possible, comparison of the channel indication and status to other indications or status derived from independent instrument channels measuring tre 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 verify 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 SITE BOUNDARY, access to which can be limited by the licensee for any reason (see Figure 3.1). 3,6 DOSE EQUIVALENT I.I3I DOSE EQUIVALENT l-'t31 shall be that concentration of l-131 (pOilg) that alone would produce the same thyroid dose as the quantity and isotopic mixture of l-131 , l-'t 32, l-133, l-134, and l-'l 35 actually present. The thyroid dose conversion factors used for this calculation shall be those listed in Table E-7 of NRC Regulatory Guide '1.109, Revision 1, October 1977.

WBN TWO-UNIT OFFSITE DOSE CALCULATION Revision { 0 MANUAL {ODCM} Page 58 of 205 3.0 DEFINITIONS 3.7 FREQUENGY NOTATION The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall conespond to the intervals defined in Table 3.1. 3.8 MEMBER(S) OF THE PUBLTC MEMBER(S) OF THE PUBLIC, as defined in 10 CFR 20, is any individualexceptwhen that individual is receiving an occupationaldose. 3.9 MODE A MODE shall conespond to any one inclusive combination of core reactiviiy 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. 3.10 OPERABLE . OPERABILIW A system, subsystem, train, component, or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function(s), and when all necessary attendant instrumentation, controls, normal or emergency electrical power, cooling and seal water, lubrication and other auxiliary equipment that are required for the system, subsystem, train, component, or device to perform its specified function(s) are also capable of performing their related support function(s). 3.11 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 purify the confinement. 3.12 RATED THERMAL POWER RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 3459 MWt for Unit 1 and 3411 MWt for Unit 2. 3.13 REPORTABLE EVENT A REPORTABLE EVENT shallbe any of those conditions specified in Section 50.73 of 10 CFR 50. 3.14 RESTRICTED AREA/RESTRICTED AREA BOUNDARY 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 quarters, but separate rooms in a residential building may be set apart as a RESTRICTED AREA (see Figure 3.1).

WBN TWO.UNIT OFFSITE DOSE CALCULATION Revision I 0 MANUAL {ODCM} Page 59 of 205 3.0 DEFINITIONS 3.15 SITE BOUNDARY The SITE BOUNDARY is defined in 10 CFR 20 as that line beyond which the land or property is not owned,leased, orotherwise controlled bythe licensee (see Figure 3.1). FoTWBN ODCM purposes, the SITE BOUNDARY and the UNRESTRICTED AREA BOUNDARY are identical. 3.I6 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 intemal test circuits. 3.1 7 UNRESTRICTED AREA'UNRESTRICTED AREA BOUNDARY 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. For WBN ODCM purposes, the SITE BOUNDARY and the UNRESTRICTED AREA BOUNDARY are identical. 3.18 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 andlor HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust stream prior to the release to the environment (such a system is not considered to have any effect on noble gas effluents). Engineered Safety Feature (ESF) atmospheric cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components. 3.19 WASTE GAS HOLDUP SYSTEM AWASTE 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 environmeni.

WBN TWO.UNIT OFFSITE DOSE CALCULATION Revision 1 0 MANUAL (ODCM) Page 60 of 205 Table 3.1 - FREQUENCY NOTATION NOTATION FREOUENCY 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. 0 At least 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 TWO.UNIT OFFSITE DOSE CALCULATION Revision 1 0 MANUAL (ODCM) Page 61 of 205 Table 3.2 - OPERATIONAL MODES REACTIVITY CONDITION, % RATED THERMAL AVERAGE COOLANT MODE Ker POWER* TEMPERATURE

1. Power Operation > 0.99 > Salo NIA

2. Startup > 0.99 S 1a/o NIA

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

4. Hot Shutdown** < 0.99 N1A 350'FrT*u*>200'F

5. Cold Shutdown"" < 0.99 NIA < 2000F

6. Refueling""* N/A N1A 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.

WBN TWO-UNIT OFFSITE DOSE CALCULATION Revision 0 0 MANUAL (ODCM) Page 62 of 242 WATTS BAR NUCLEAR PI*ANT RESTRICTED AREI,I BOUfTIOARY Figure 3.1 WBI.I Site Area lldap

WBN OFFSITE DOSE CALCULATION MANUAL Revision 0 0 {oDCM} Page 63 of 242 4.0 - (NOT USED) 5.0 ADMIN ISTR.ATIVE CONTROLS 5.1 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT As required by WBN TS 5.9.2, Routine Annual Radiological Environmental Operating Reports eovering the operation of both units during the previous calendar year shall be submitted pdor to May 15 of each year. The annual radiological environmental operating reports shall include summaries, interpretalions, and an analysis of trends of the result$ 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 Control 1.3.2. The annual radiological environmental operating 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 lntedaboratory Comparison Program and the conective 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 conducling 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.!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 byTable 2.13 was not achievable. 5.2 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT As required by WBN TS 5.9.3, a Radioactive Effluent Release Report covering the operation of both units 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 LightWater-Cooled Nuclear Power Plants," Revision 1, June 1974, with data summarized on a quarterly basis following the format of Appendix B thereol as applicable. Additional requirements for reporting solid waste are specified in the Process Control Program. 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. 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 WBN Technical

WBN TWO.UNIT OFFSITE DOSE CALCULATION Revision I 0 MANUAL {ODCM} Page 64 of 205 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 corrected 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 effuents released from the unit or station during the previous calendar year. This same report shall also include an assessmenl 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 concurent 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. ISOURCE 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 fuel cycle 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 occuned during the reporting period.

WBN TWO.UNIT OFF$ITE DOSE CALCULATION Revision I 0 MANUAL (ODCM) Page 65 of 205 5.3 OFFSITE DOSE CALCULATION 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 shall contain:

a. Sufficient information to support the change together with the appropriate analyses or evaluations justifying 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 lto 10 CFR 50 and not adversely impact the accuracy or reliabillty 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 for the 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 Special Reports shall be submitted in accordance with 10 CFR Part 50.4. ISOURCE NOTE 16] 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.

WBN TWO.UNIT OFF$ITE DOSE CALCULATION Revision 1 0 MANUAL (oDCM) Page 60 of 205 5.6 CHANGES TO RADWASTE TREATMENT SYSTEM Licensee-initiated major changes to the Radwaste Treatment Slatems (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 shallcontain:

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 slnstems;

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 Analpis 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.

WBN TWO.UNIT OFFSITE DOSE CALCULATION Revision 1 0 MANUAL {ODCM} Page 67 of 205 6.0 - LIQUID EFFLUENTS INTRODUCTION Radioactive liquid effluents from WBN enter the UNRESTRICTED AREA through the diffusers into the Tennessee River. There are four plant syslems from which radioactive effluents are released. These are the Liquid Radwaste Treatment Sptem (LRTS), the Gondensate 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 flow 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 1.2.1.1 are not exceeded. Each monitor has an alarm/trip setpoint which will alarm if the monitor's setpoint is exceeded. Alarm and tip functions are not provided by separate devices, therefore the alarm/trip 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 alarmftrip 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, SGBD, and groundwater sump 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.'l 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. For continuous releases, the pathways are sampled for radioactivity periodically, as described in ODGM Section 6.1.'t. The samples are anallaed 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 calculational methodologies are based on the guidance provided in NUREG-0133 (Reference 3) and Regulatory Guide 1.109 (Reference 4). 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 (Reference 4).

WBN TWO.UNIT OFF$ITH DOSE CALCULATION Revision I 0 MANUAL (ODCM) Page 68 of 205 RELEASE POINTS Liquid Radwaste Treatment System The LRTS processes liquid from the Reactor Building and Auxiliary Building Floor Drains, the CVCS Holdup Tanks, the Laundry/Hot Shower Tanks, the Waste Condensate Tanks and Chemical Drain Tank. 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) and the Tritiated Water Storage Tank (TWST). The Monitor Tank has a capacity of 20,462 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 TTVST has a capacity of 500,000 gal and can be released at a maximum design flow rate of 140 gpm. The Monitor Tank, CDCT, and TWST 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. Gondensate 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 lhe 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 capacityof 11,000 gal and a maximum design discharge flow rate of 115 gpm. Each of these tanks is defined as a release point for the system. When 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 flow 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 lo eilher the Meial 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 generatorwhen discharging to the Cooling Tower Blowdown. SGBD is recycled or is released to the CTBD line and monitored by radiation monitors 1,2-RE-90-120 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.

WBN TWO.UNIT OFFSITE DOSE CALCULATION Revision 1 0 MANUAL TODGM) Page 69 of 205 6.1 LIQUID RELEASES 5.1.1 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, turbine building sump, and groundwater sump are considered continuous. For continuous releases, daily grab or composite samples will be taken on days when releases are being made and analped 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 composlte 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 Goncentration Limits (ECL)-Sum 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_ rC'

     ? ECLi

{s.1} where: R = the sum of the ratios for the release poinl. ECLI = the ECL of radionuclide i, pCilml, from 10 CFR 20, Appendix B, Table 2, Column 2. Ci = 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 either the Turbine Building Sump or the Groundwater Sump will be < 10 at the sump.

WBN TWO.UNIT OFFSITE DOSE CALCULATION Revision I 0 MANUAL {oDCruI} Page 70 of 205 The following relationship is used to ensure that this criterion is met: f,R, +f2R? +{rRu +f4R4 Rr:ws

R*s + < 10.0 (6.2) where:

Rows = sum of the ECL ratios of the groundwater sump as determined by equation 6.1. Rrss = sum of the ECL ratios of the turbine building sump as determined by equation 6.1 . t,t,z,z,a = effluent flow rate for radwaste, condensate demineralizer system and the steam generator blowdowns, respectively, gpm. Rr,z,s,a = 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 llnalysis 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. ISOURCE NOTE 101 6.2 INSTRUMENT SETPOINTS Liquid effluent monitor setpoints are determined to ensure that the concentration of radioactive material released at any time from the site to UNRESTRICTED AREAS does not exceed ten times the ECL limits referenced in ODCM Control 1.2.1.1 and to identify 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 $ection 6.2.1 N/A 6.2.1 0-RE-90-1 34 0-RE-90-140 0-RE-90-141 Radwaste 0-RE-g0-122 Sect an 6.2.2 S*"* 6.2.2 Condensate 0-RE-gA-225 Section 6.2.2 S*", 6,2.2 Demineralizer TBS 0-RE-gA-?l? Section 6.2.2 s*r, 6.2.2 SGBD 1-RE-90-1 20 Section 6.2.2 S*"* 6.2.2 2-RE-90-120 1-RE-90-121 2-RE-9A421

WBN TWO-UNIT OFFSITE DOSE CALCULATION Revision I 0 MANUAL (oDCM) Page 71 of 205 6.2.1 Process Discharge Point Monitor Setpoints (0-RE-90-133,-134,-140,-141) The setpoints for the ERCW monitors (0-RE-90-133,-134,-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 control this value. 6.2.2 Release Point Monitor Setpoints (0-RE-90-122; 0-RE-90-225; 0-RE-90-212; 1 ,2-RE-90-120,-1211 The radiation monitor for batch release points, the Liquid Radwaste System and the Condensale 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 identify any gamma-emitting release that is larger than expected and would have the potential to 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 control this 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 identify any gamma-emitting release that is larger than expected and would have the potential to exceed the ODCM Control 1.2.1 ^1 concentration limite afier 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 controlthese 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 activity 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, lhe monitor is normally returned to the default setpoint).

1. lf SER ( Soeraurt < S*"* Reported = Sdetaurt

2. lf SER ( Srnr, < Sa.r"* RePorted = Sg*

3. If SER ) S*r,. Reported = $*",

6.2.2.1 Expected Response An expected response (ER) is calculated for the monitor for each release: ER = BKG + I(8. C. ) (6.3)

'l l' I

where: BKG = monitor background, cpm. The monitor's background is controlled at an appropriate limit to ensure adequate sensitivity in accordance with site procedures. Ei = monitor efficiency for nuclide i, cpm per pCi/ml. This term may also be refened to as a response or calibration factor. C1 = tank concentration of nuclide i, pCi/ml.

WBN TI'IIO.UNIT OFFSITE DOSE CALCULATION Revision 1 0 MANUAL (ODCM) Page 72 at 205 6.2.2.2 Expected Response Setpoint An expected response setpoint SEp is calculated for the monitor for each release: Sm = XZEST +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 $etpoint A second sepoint 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 1.2.1.1 limits after dilution. This setpoint ensures that the release will be stopped if it exceeds this limit. The maximum calculated setpoint calculation must satisfy the following relationship from NUREG-0133: sf

--(c (F+f) where:

C = the effluent concentration limitfrom 10 CFR 20 Appendix B, Table 2, Column 2, in pCilml, represented by a value of 1. 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 volumehic 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 1.2.1.1 when 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 equal to the limit, the setpoint s can be replaced by: S=QD*q where

c. = the actual effluent concentration, pCi/ml.

Dr"q = the required dilution factor.

WBN TWO.UNIT OFFSITE DOSE CALCULATION Revision 1 0 MANUAL (oDCM) Page 73 of 205 The required dilution can be defined as: R IO SF where: R = the sum of the ratios for gamma-emifting radionuclides, as determined by equation 6.'t. 10 = a value ra*rich 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": a<- - 10SF (F+0 -a - 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, S."r, in cpm for a release point, the following equation is used: to sr(f + (AF

F)) (rn Sr** ={ fR -BKG)+BKG (6"5) 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 for that release point to the total CTBD flow. The CTBD flow allocation fractions for these release points are routinely: Radwaste 0.6 Condensate dem ineral izer o.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 forthe Radwaste System may be set equalto one. ER = expected monitor response, cpm, as calculated in Equation 6.3. BKG = background, cpm.

WBN TWO.UNIT OFF$ITE DOSE CALCULATION Revision I 0 MANUAL {ODCM} Page 74 of 205 6.3 CUMULATIVE 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 (1-1'l years), infant (0-1 years) (Reference 4); and the following organs: bone, liver, total body, thyroid, skin, kidney, lung, and Gltract. Using the methodology presented in NUREG-O133, 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 &e 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 AS in Regulatory Guide 1.109. Dose factors for these three pathways are calculated as described in Section 6.7. For pathways with no age ff 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 irrigated with Tennessee River water are not considered significant pathways for the area surrounding WBN (References 9 and 10), so they are not considered in the dose calculations. The maximum individualdose from drinking water is assumed to be that calculated at the location immediately downstream from the diffuser. The maximum individualdose 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 downstream of the plant outfall. The general equation for the dose to an organ j is: Di=IATTCiD (6.6) i where: A,j = th" total dose factor to the total body or any organ j for nuclide i, mrem/h per pCilml. The total dose factor is the sum of the dose factors for water ingestion, fish ingestion, and shoreline recreation, as defined in Section 6.7. T = the length of time period over which the concentrations and the flows are averaged, h. C; = the average concentralion of fadionuclide i, in undiluted liquid effluent during the time period T from any liquid release, pCilml. D = the near field average dilution factor for C; during any effluent release. D is calculated by the following equation:

   =f                                                                                                       (6'7) o.lo x RF 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 quartedy riverflow recorded from the period 1985-94). From the four age groups considered, the maximum oryan 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.

WBN TWO.UNIT OFFSITE DOSE CALCULATION Revision I 0 MANUAL (oDCM) Page 75 of 205 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 occuned 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 WBN FSAR shall be maintained and operated to keep releases ALARA. A flow diagram forthe LRTS is given in Figure 6.2. 6.5 DOSE PROJECTIONS ln accordance with ODCM Surveillance Requirements2.2.1.3.1 and2.2.1.3.2, dose projections willbe performed at least once per 31 days using the equation below: o = {(.lb)*rr}+c (6.8) ld ) where: D = the 31-daydose projection, mrem. a = the cumulative dose for the quarter, mrem. $ = the projected dose for this release, mrem. c = any anticipated additional dose in the next month from other sources, mrem. ( = current number of days into the quarter up to the time of the release under consideration.

WBN TWO.UNIT OFF$ITE DOSE CALCULATION Revision 1 0 MANUAL (ODCM) Page 76 of 205 6.6 DOSE CALCULATIONS 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 for this analysis is based on the methodology presented in Regulatory Guide 1.109 and is desoibed in this section. The releases are assumed, for this calculation, to be continuous over the 90 day period. The near-field dilution factor, D;qp, used for the quarterly calculations is: 1 Drr = (for receptors upstream of Tennessee River Mile 510.0) (6.9) and I D* = (for receptors downstream of Tennessee River Mile 510.0) (6.10) RF where: RF = the average actual riverflow for the location at which the dose is being determined, cfs. 0.10 = the fraction of the riverflow available for dilution in the near field, dimensionless (Reference 1 1). Note: TRM 510.0 is the point at which the effluent is considered to be tully mixed with the riverflow (Reference 11).

WBN TWO.UNIT OFFSITE DOSE CALCULATION Revision 1 0 MANUAL (ODCM) Page 77 of 205 6.6.1 Water Ingestion Water ingestion doses are calculated for each water supply identified within a 50 mile radius downstream of WBN (Table 6.1). The water ingestion dose equation is based on Regulatory Guide 1.109, Equation 1: o ['*=M.']Io, A*, ery(- }.,t0)

   =u t     F     )"'

For WBN, the dilution factor (MfF) 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 (&s"i) are incorporated into the dose factor (as described in Section 6.7.1). The resulting equation for the water ingestion dose, j Q, in mrem, to organ is: Di =to6 (e.aop- og)T 4rrei Dxr ery(-s.o+rM 4t) (6.11) I where: 106 = @nversion factor, pCi/Ci. 9.80E-09 = conversion factor, cfs per ml/h. Awarj = dose factor for water ingestion for age group a, nuclide i, and organ j, mrem/h per pCilml, as calculated in Section 6.7.1. Qi = quantity of nuclide i released during the quarter, Ci. Drur = dilution factor, as described above, cfs-1. A; = radiological decay constant of nuclide i, s-1 Oable 6.2). td = decay time for waler 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, sld. 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 1.109, Equation 2:

      /u^^l,l^ \

o= t rei B; erou exd-L;t6) [ro, J For WBN, the dilution factor (My'F) is replaced by the near field dilution factor (D*.) described by Equations 6.9 and 6.10, and the usage factor (U"o), bioaccumulation factor (Bi), and dose conversion factors (Ap";1) are incorporated into the dose factor (as described in Section 6.7.2). The resulting equation for the fish ingestion dose D;, in mrem, to organ j is: Di =106 (9.80F- 09) IAr*, Qr Dxr ery(8.64804,!to) (6.12) IJ."'"' = conversion factor, pci/ci. 9.80E-09 = conversion factor, cfs per ml/h. 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. ei = quantity of nuclide i released during the quarter, Ci. DNr = dilution factor, as described above, cfs-1.

WBN TWO.UNIT OFFSITE DOSE CALCULATION Revision I 0 MANUAL (0DCM) Page 78 of 205 tr; = radiological decay constant of nuclide i, s-1 fiable 6.2). td = 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, sld. 6.6.3 Shoreline Recreation Recreation doses are calculated for each identified reach within a 50 mile radius downstream 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 WBN, the dilution factor MfF is replaced by the near field dilution factor (Dxp) described by Equations 6.9 and 6.10, and the usage factor (Uap), shoreline width factor (SWF), radioactive half-life (Ti), dose conversion factor (AnaU) and the second exponential term are incorporated into the dose factor (as described in Section 6.7.3). The resulting equation for the shoreline recreation dose D1, in mrem, to organ j is: Di =106 (9.80E- 09) TA*: Qi Dr.nr ery(-8.64E 04 4t) (6.13) wttaere:

          = conversion factor, pci/ci.

9.80E-09 = conversion factor, cfs per ml/h. 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. Qi = quantity of nuclide i released during the quarter, Ci. DNr = dilution factor, as described above, cfs-1 \ = radiological decay constant of nuclide i, s-1 lTable 6.2;. ld = 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.

I'VBN TWO.UNIT OFFSITE DOSE CALCULATION Revision I 0 MANUAL (ODCM) Page 79 of 205 6.6.4 Total Maximum Individual Dose The total maximum individual quarterly total body dose for each age group a, D(tb)", is obtained using the following equation: D(tb)" = Oru + Dr + Dn (5.14) where: Dlar = the highest total body water ingestion dose for age group a from among all the public water supplies Dp = the highest total body fish ingestion dose for age group a from among all the reaches D3 = 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}a;, is obtained using the following equation: D(org)aj = Dyy .' Dr

DR (6.1 5) where:

Dw = the highest water ingestion dose for age group a and organ j from among all the public water supplies Dp = the highest fish ingestion dose for age group a and organ j from among all the reaches Dn = 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).

WBN TIfYO-UNIT OFFSITE DO$E CALCULATION Revision I 0 MANUAL (ODCM) Page 80 of 205 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: n=kIPoP* IDj,- fP, lllo For WBN, the average individual doses (D;ma) are determined by obtaining the ratio of the average consumption rate to the maximum consumption rate and multiplying this bythe maximum individualdose. For water ingestion, the general equation used for calculating the population doses, POPWTR, in person-rem for a given Public Water Supply (P\AIS) is: POPWT\ = l0-'I POP,,IF" ATM\Y TWDOS,q (6.16) n=l a=l where: POPWTRj = water ingestion population dose to organ j, person-rem. fP" = fraction of population in each age group a (from NUREG CR-1004, table 3.39). Adult = 0.665 Child = 0.167 lnfant = 0.015 Teen = 0.153 POP, = population at PWS m. The 4 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 Ur" in Table 6.3. Average water ingestion rates, in Uy, (from Reference 4, Table E-4) are: Adult = 370 Child = 260 lnfant = 260 Teen = 260 TWDOS614 = 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 he calculation assumes that all fish caught within a 50-mile radius downstream of WBN are consumed by local population. The totalfish harvest is calculated by multiplying lhe average fish harvesl 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 S0-mile radius downstream is: pop{ -10 *- 310-3 4s3.6Hvsr ApR t I':l*t, i FISH. fP_ (6.17) where: POPF; = total fish ingestion population dose to organ j, person-rem. HVST = fish harvest for the Tennessee River, 3.77 lbs/acre/y edible weight (Reference 12). APR = size of reach, acres (Table 6.1). TFDOS36 = total fish ingestion dose to organ j for reach r, for the age group a, (calculated as described in Section 6.6.2), mrem. fP" = 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 E4) are:

WBN TWO.UNIT OFFSITE DOSE CALCULATION Revision I 0 MANUAL {ODCM} Page 81 of 205 Adult = 6.9 Child = 2.2 Teen = 5.2 lnfant = 0.0 453.6 = conversion factor, g/lb. 10-3 = conversion factor, rem/mrem. 10-3 = conversion factor, kg/9. 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 average visit (HRSVIS). The general equation used for calculating the population doses, POPR, in person-rem is: l.l

      ' =*ITSHDOq POPRT                                ${VrS,    HRSVTS.                                              (6.18) l0'8760f,+1 where:

POPR = total recreation population dose for all reaches to organ j, person-rem. TSHDOSd = 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. 103 = cnnvercion factor, mremlrem. 8760 = conversion factor, h/y.

WBN TWO.UNIT OFFSITE DOSE CALCULATION Revision I 0 MANUAL {ODCM} Page 82 of 205 6.7 LIQUID DOSE FACTOR EQUATION$ The general form of the liquid dose factor equation from NUREG-0133 is: A,: -ko + u.B{ + u,B*]Dn [* where: k0 = conversion factors. Uw = water consumption rate, Uy. Dw = dilution factor from the near field area within one-quarter mile of the release point to the potable water intake for water consumption, dimensionless. Up = fish consumption rate, kg/y. BFi = bioaccumulation factor for nuclide i in freshwater fish, pCi/kg per pCill. Ul = invertebrate consumption rate, kg/y. DF; = ingestion dose conversion factor, mrem/pCi. Since the value of the term U1 is negligible, WBN 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,j :ko (uru +uu Bn)nn +k, uR c" DFGi where: ko,t = conversion factors' Up = recreation usage factor, hly. Cs = accumulation factor for buildup of activily in sediment, p0i/m2 per pCi/L. DFQ = dose factor for standing on contaminated ground, mremlh 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 - Awai (mremlh per pCilml) 106lo',Dqu u,uu warj A.rr^,r : (6.19) g76a where: pF",i = 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 = conversion factor, pCi/pCi. 103 = conversion factor, mlll. 8760 = conversion factor, h/y.

WBN TWO.UNIT OFFSITE DOSE CALCULATION Revision I 0 MANUAL (oDCM) Page 83 of 205 6.7.2 Fish lngestion Dose Factor - AFarj (mrem/h per pCi/ml) 106103 D% u* B, Aru,j : (6.20) 8760 where: gF"U = ingestion dose conversion factor for nuclide i, age a, organ j, mrem/pCi, (Table 6.4). Ur" = fish consumption rate for age group a, kg1y, (Table 6.3). Bi = bioaccumulation factor for nuclide i, pCilkg per pCi/L, (Table 6.5). 100 = conversion factor, pCi/pCi. 103 = conversion factor, mUL. 8760 = conversion factor, h/y. 6.7.3 Shoreline Recreation Dose Factor - AnrU (mrem/h per pCi/ml) Equation A-6 in Regulatory Guide 1.109 provides a methodolbgy for calculating the dose due to shoreline recreation along a water body: Dose = k K" u swF I c,, Ti DFGtj [t - r,t, ) ]

                                                   "reG Since the terms Ciyy                 part of the dose equation (Equation 6.6), the equation for the dose factor becomes:
                         "nJ, "r"

[{, o'r K" M swr u.) 1-06 DFG,I Anxj : - exp (- I,t. ) ] (6.21) 8760 . 36 00 - AT Ir, where: DFG;; = dose conversion factar for standing on contaminated ground for nuclide i and organ j (total body and skin), mrem/h per p0i/mz, {Table 6.6). Kc= transfer coefficient from water to shoreline sediment, L/kg-h, (Table 6.3), M= mass density CIf sediment, kg/ffi2, (Table 6.3). SWF = shoreline width factor, dimensionless, (Table 6.3). 103 = conversion factor, ml/L. 106 = conversion factor, pCi/pCi. 3600 = conversion factor, s/h. A; = decay constant for nuclide i, s-1, (Table 6.2). t-1b 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.

WBN TI'YO.UNIT OFFSITE DOSE CALCULATION Revision 1 0 MANUAL (ODCM) Page 84 of 205 Table 6.1 - RECEPTOR$ FCIR LIQUID DOSE CALCULATIONS Tennessee River Reaches Within 50 Mile Radius Downstream of WBN Beginning Ending Sizel Recreation2 Name TRM TRM {acres} visitsly Chickamauga Lake (from WBN to 528 51 03 4799 124,986 100% mixing point) Chickamauga Lake (from 100% mixing 51 03 484 22141 't,297,s80 point to Sequoyah Nuclear Plant) Chickamauga Lake (from $equoyah 484 471 9889 7,421 ,905 Nuclear Plant to Chickamauga Dam) Nickajack Lake (from Chickamauga 471 460 1 799 284,000 Dam to WBN S0-mile radius) TRM - Tennessee River Mile. 1 Reference 13. 2 Reference 14. g t OOX Mixing Point (Reference 1 1 ). Public Water $upplies lfiIithin 50 ltllile Radius Downstream of IIVBN Name TRM Estimated 2040 Population Dayton, TN 504 19,170 Soddy-DaisylFalling 487 11,452 Water Utility District East Side Utility, TN 473 49,744 Chattanooga, TN 465 237,048 NOTE: Tennessee river mile locations are rounded to the nearest mile for dose calculation purposes.

WBN TWCI-UNIT OFFSITE DO$E CALCULATION Revision I 0 MANUAL (OBCM) Page 85 of 205 Table 6.2 - RADIONUCLIDE DECAY AND STABLE ELEMENTTRANSFER DATA (Page 1 of 3) Half-Life A Bi, Fmi Fmi Fg Nuclide {minutes} {s-1} {cow} {goat} (beef} H-3 6.46E+06 1.79E-09 4.80E+00 1.00E-02 1.70E-01 1.208-02 c-14 3.01 E+09 3,84E-12 5.50E+00 1 .20E-AZ 1 .00E-01 3.108-02 Na-24 9.00E+02 1.28E-05 5.20E-02 4.00E-02 4.00E-02 3.00E-02 ?-32 2.06E+04 5.61E-07 1.10E+00 2.50E-02 2.50E-01 4.60E-02 Cr-S1 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 2.908-02 2.50E-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+0S 8.13E-09 6.60E-04 1.20E-03 1 .30E-04 1.20H.02 Fe-59 6.43E+04 1.80E-07 6.60E-04 1.20E-03 1.30E-04 1.24F-02 Co-57 3.90E+05 2.96E-08 9.40E-03 1.00E-03 1.00E-03 1.30E-02 Co-58 1.92f+05 1 .13E-07 9.408-03 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 Ni-63 5.27FtA7 2,19E-1 0 1.90E-02 6.70E-03 6.70E-03 5.30E-02 Ni-65 1.51 E+02 7.65E-05 1.90E-02 6.70E-03 6.70E-03 5.30E-02 Cu-64 7.62F+A2 1.52E-05 1.20E-01 1.408-A2 1 .30E-02 9.70E-04 Zn-65 3.52E+05 3.28E-08 4.00E-01 3.90F-02 3.90E-02 3.00E-02 Zn-69m 8.26E+02 1.408-05 4.008-01 3.90E-02 3.90E-02 3.00E-02 Zn-69 5.59f+01 2.488-04 4.008-01 3.908-A2 3.90E-02 3.00E-02 Br-82 2.1 2E+03 5.45E-06 7.608-01 5.00F-Az 5.00E-02 2.60E-02 Br-83 1.43E+02 8.088-05 7.608-01 5.00E-02 5.00E-02 2.60F-42 Br-84 3.18E+01 3.638-04 7"608-01 5.00E-02 s.00E-02 2.60E-02 Br-85 2.87E+00 4.A28-03 7.608-01 5.00E-02 5.00E-02 2.60E-02 Rb-86 2.69E+04 4.298-07 1 .30E-01 3.008-A2 3.00E-02 3.10E-02 Rb-88 1.78E+01 6.4SH-04 1 .308-01 3.00E-02 3.00E-02 3.10E-02 Rb-89 1.54E+01 7.508-04 1 .30r-01 3.00E-02 3.00E-02 3.10E-02 Sr-89 7.28t+44 1.598-07 1"70r-02 1.40E-03 1 .40E-02 6"00E-04 Sr-90 1.50E+07 7.708-10 1.708-02 1.40E-03 1 .40E-02 6.00E-04 Sr-91 5.70E+02 2.038-05 1.708-02 1,40E-03 1.4AE-*2 6"00E-04 Sr-92 1.638+02 7.098-05 1.708-02 1.40E-03 1 .40E-02 S.00E-04 Y-90 3.85E+03 3.008-06 2,60E-03 1.00E-05 1 .00E-05 4,60E-03 Y-91 m 4.97E+01 2.328-04 2.S08-03 1.00E-05 1.00E-05 4.60E-03 Y-91 8.43E+04 1.378-07 2.60E-03 1.00E-05 1.00E-05 4.60E-03 Y-92 2.128+A2 5.458-05 2.60E-03 1.00E-05 1 .00E-05 4.60E-03 Y-93 6.06E+02 1.91 E-05 2.608-03 1.00E-05 1.00E-05 4.608-03 Zr-95 9.22E+04 1.258-07 1.70E-04 5.00E-06 5.00E-06 3.40E-02 Zr-97 1.01 E+03 1.148-05 1.70E-04 5.00E-06 5.00E-06 3.40E-02 Nb-95 5.05E+04 2.298-47 9.40E-03 2.50E-03 2.50E-03 2.80E-01 Nb-97 7.21E+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+AZ 3.20E-05 2"50E-01 2.50E-02 2.50E-02 4.00E-01 Tc-1 01 1.428+A1 8.13E-04 2.50E-01 2.50E-02 2.50E'-42 4.00E-01 Ru-103 5.67E+04 2.04E-07 5.008-02 1.00E-06 1.00E-06 4.00E-01

WBN TWO-UNIT OFFSITE DOSE CALCULATION Revision I 0 MANUAL {0DCM} Page 86 of 205 Table 6.2 - RADIONUCLIDE DECAY AND STABLE ELEMENTTRANSFER DATA (Page 2 of 3) Half-Life i Bi, Fmi Fmi Fs Nuclide {minutes} {s'1} (cow) {goat} {beef} Ru-105 2.56E+02 4.34E-05 5.00E-02 1.00E-06 1.00E-06 4.00E-01 Ru-106 5.30E+05 2.18E-08 5.00E-02 1.00E-06 1.00E-06 4.00E-01 Ag-'l 10m 3.60E+05 3.21E-08 1,508-01 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 NIA Te-125m 8.35E+04 1.38E-07 1.30E+00 1.00E-03 1 .00E-03 7.7$F.CI2 Te-1 27m 1.57 E+05 7.3SE-08 1,30E+00 1.00E-03 1 .00E-03 7.7AF.A2 Te- 127 5.61 E+02 2.A68-05 1.30E+00 1.00E-03 1 .00E-03 7.70F-02 Te-129m 4.84E+04 2.39E-07 1.30E+00 1.00E-03 1 .00E-03 7.708-02 Te-129 6.96E+01 1.66E-04 1.30E+00 1.00E-03 1 .00E-03 7.70E.02 Te-131 m 1.80E+03 6.42E-06 1,30E+00 1.00E-03 1 .00E-03 7.7AE.Q? Te-131 2.50E+01 4.62E-04 1.30E+00 1.00E-03 1 .00E-03 7.708-A2 Te-132 4.69E+03 2,46E-06 1.30E+00 1,00E-03 1 .00E-03 7.70E-02 t-130 7.42s+42 1.56E-05 2.00E-02 1.2AF.02 4.30E-01 2.90E-03 f-131 1.168+04 9.96E-07 2.00E-02 1.2AF-A2 4.30H-01 2.90E-03 I-132 1.388+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 1.20H-02 4.30E-01 2.90E-03 t-134 5.26E+01 ?.248-44 2.00E-02 1.20E-02 4.30E-01 2.90E-03 t-135 3,97E+02 2.91E-05 2.00E-02 1.208-02 4.308-01 2.90E-03 Cs- 134 1.08E+06 1.06E-08 1.00E-02 8.00E-03 3.00E-01 1.50E-02 Cs-136 1.90E+04 6.08E-07 1 .008-02 8.00E-03 3.00E-01 1.50E-02 Cs- 137 1.59E+07 7 .26E-1 0 1.00E-02 8.00E-03 3.00E-01 1.50E-02 Cs-138 3,22F+M 3.59E-04 1.00E-02 8.00E-03 3.00E-01 1.50E-02 Ba-139 8.31 E+01 1,39E-04 5.00E-03 4,00E-04 4.00E-04 3.20E-03 Ba-140 1.ME+04 6.28E-07 5.00E-03 4.00E-04 4.00E-04 3.20E-03 Ba-141 1.83E+01 6.31 E-04 5,00E-03 4.00E-04 4.00E-04 3.208-03 B,a-l42 1.07E+01 1.08E-03 5.00E-03 4.00E-04 4.00E-04 3.20E-03 La-140 2.41 E+03 4.79E-00 2"50E-03 5.00E-06 5.00E-06 2.00E-04 La-142 9.54E+01 1.21E-04 2.508-03 5.00E-06 5.00E-06 2.00E-04 Ce-141 4.68E+04 2.478-AT 2.50r-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+05 2.82E-08 2.50E-03 1.00E-04 1 .00E-04 1.208-03 Pr-143 1.95E+04 5.92E-07 2.50E-03 5.00E-06 5.00E-06 4.708-03 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 7.31E-07 2.40E-03 5.00E-06 5.00E-06 3.30E-03 w-l87 1.438+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 2.00E-04 Ar-41 1.10E+02 1 .05E-04 N/A N/A N/A N/A Kr-83m 1.10E+02 1 .05E-04 N/A NTA NIA 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 NIA N/A N/A N/A Kr-87 7,638+01 1.51 E-04 N/A NIA NIA N/A

WBN TI'IIO-UNIT OFFSITE DOSE CALCULATION Revision I 0 MANUAL (0DCM) Page 87 of 205 Table 6.2 - RADIONUCLIDE DECAY AND STABLE ELEMENT TRANSFER DATA (Page 3 of 3) Half-Life A Bi, F rml L tr rml Fs Nuclide {minutes} {s{} {cow} {goat} (beef) Kr-88 1,748+42 6.79E-05 N/A NlA N1A N/A Kr-89 3.16E+00 3.66E-03 N/A N/A N/A N/A Kr-90 5.39E-01 ?.14E-02 N/A N/A N/A N/A Xe-131 m 1.70E+04 6.79E-07 N/A N/A N/A N/A Xe-133m 3.15f+03 3,S7H-06 NIA N/A N/A N/A Xe-133 7.55E+03 1.538-05 N/A N/A N/A NIA Xe-135m 1.54E+01 7.508-04 N/A NIA NIA N/A Xe-135 5,478+AZ 2.11E-05 N/A N/A N/A N/A Xe-137 3.83E+00 3.02E-03 NIA N/A N/A N/A Xe-138 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 15 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 transfer factors 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.

WBN TWO.UNIT OFFSITE DOSE CALCULATION Revision I 0 MANUAL {CIDCM} Page 88 of 205 Table 6.3 - DOSE CALCULATION FACTORS (Page 1 of 2) Factor Value Units Reference BR, (infant) 1400 m3/y Reference 20 8R* (child) 5500 m3/v Reference 20 BR" (teen) 8000 m3/y Reference 20 BR, (adult) 81 00 m3/y Reference 20 fs 1 Conservatively assumes all stored vegetables are grown locally. fg 1 Reference 4 (Table E-15) f0 1 See Note fs 0 See Note H o g s/m3 TVA Value Kc 4.472 L/kg-h Reference 4 ($ection 2.C.) M 40 ks/m2 Reference 4 (Section 2.C.) P 240 ks/m2 Reference 4 (Table E-15) Q (cow) 64 kglday Reference 21 (Sect. 3.4) Q1 (goat) 08 kg/day Reference 21 {Sect. 3,4) r 4.47 Reference 21 (Sect" 3.2\ t tb 4.73E+08 (15 y) S Reference 4 (Table E-15) tcu 7.78*.+06 (90 d) S Reference 10, Section 1 1 .3.10.1 L.t 1 .56E+07 (180 d) S Reference 10, Section 11.3.10.1 t" 5,18E+06 (60 d) S Reference 4 (Table E-15) Lp 2.5eE+06 (30 d) S Reference 4 (Table E-15) Lst 7.78E+06 (90 d) S Reference 4 (Table E-15) fu11 8.64E+04 (1 d) S Reference 10, Section 11.3.10.1 tr," 8.64E+04 {1 d} s Reference 21 , Table 3.40 ts 1.12t+0$t13 d) S Reference 21 , Table 3.40 t.u 2.38E+07(275 d) U Reference 10, Section 11.3.10.1 U.* (infant) 0 kgly Reference 4 (Tab e E-5) U"* (child) 41 kg/y Reference 4 (Tab e E-5) U"* (teen) 65 kg/y Reference 4 (Tab e E-5) Ur* (adult) 110 kg/v Reference 4 (Tab e 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.

WBN TWO.UNIT OFFSITE DO$E CALCULATION Revision I 0 MANUAL (0DCM) Page 89 of 205 Table 6.3 - DOSE CALCULATION FAGTORS (Page 2 at 2) Factor Value Units Reference U"p (infant) 330 Uy Reference 4 (Tab e E-5) U"p (child) 330 Uy Reference 4 (Tab e E-5) U"p (teen) 400 Uy Reference 4 (Tab e E-5) Uap (adult) 310 Uy Reference 4 (Tab e E-5) Uy"(infant) 0 kg/v Reference 4 (Table E-5) Uys(child) 6.9 ks/v Reference 4 (Table E-5) U1"(teen) 16 kg/y Reference 4 (Table E-5) U16(adult) 21 kglv Reference 4 (Table E-5) U1. (infant) 0 kg/v Reference 4 (Table E-5) U1, (child) 26 kg/y Reference 4 (Table E-5) U1" (teen) 42 kg/v Reference 4 (Table E-5) U1" (adult) 64 kg/v Reference 4 {Table E-5} us* ( nfant) 0 kg/v Referense 4 (Table E-5) Us* child) 520 kglv Reference 4 {Table E-5) Us* {teen} 630 kg/v Reference 4 {Table E-5} Us* adult) 524 kg/v Reference 4 (Table E-5) uw"( nfant) 330 Uy Reference 4 (Table E-5) Uw* child) 510 Uy Reference 4 (Table E-5) Uw, teen) 510 Uy Reference 4 {Table E-5) Uw* adult) 730 L/v Reference 4 (Table E-5) SWF 0.2 none Reference 4 (Table A-2) Yg 1.85 kg/m2 Reference 21 (Table 3.4) Ye 1.18 kg/m2 Reference 21 (Table 3.3) Ysr 0.64 kglm2 Reference 21 (Table 3.3) Yw 0.57 kg/m2 Reference 21 (Table 3.4) (value selected is for non-leafy vesetables) 46,,(iodines) 7.718-07 $-1 Reference 21 (Table 3.10) (15.4 d half-life) J\w (pafticulates) 5.21E-07 s-1 Reference 21 {Table 3.10} (10.4 d half-life)

WBN TWO.UNIT OFFSITE DOSE CALCULATION Revision 1 0 MANUAL (ODCM) Page 90 of 205 Table 6.4 - INGESTION DOSE FACTORS - DFarj (mrem/pGi ingested) (Page 1 of 8) ADULT Nuclide bone liver total body thyroid kidney lung GI.LLI H-3 1.05E-07 1.05E-07 1.058-07 1.05E-07 1.05E-07 1.05E-07 1.05E-07 c-l4 2.84E-06 5.68E-07 5.68E-07 5.68E-07 5"68E-07 5.68E-07 5.68E-07 Na-24 1.70E-06 1.70E-06 1.7AE-06 1.70E-06 1.70E-06 1.70E-06 1.70E-06 ?-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 9.72E-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 3.408-05 Co-57 0.008+00 1.75E-07 2.91E-07 g.ggf+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+00 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 3.91 E-08 0.00E+00 2.10E-07 0.00E+00 7.10E-06 Zn-65 4.84E-06 1.54E-05 6.96E-06 0.00E+00 1.03E-05 0.00E+00 9.70E-06 Zn-69 1.03E-08 1.978-08 1.37E-09 0.00E+00 1.28E-08 0.00E+00 2.96E-09 Zn-69m 1,708-A7 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 4.42E-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"118-05 9.838-06 0.00E+00 0.00E+00 0.00E+00 4.16E-06 Rb-88 0.00E+00 6.05E-08 3.2'l E-08 0.00E+00 0.00E+00 0.00E+00 9.36E-19 Rb-89 0,00E+00 4.01E-08 2.82E-08 0.00E+00 0.00E+00 0.00E+00 2.338-21 Sr-89 3.08E-04 g.ggf +00 8.84E-06 0.00E+00 0.00E+00 0.00E+00 4.94E-05 Sr-90 7.58E-03 0.00E+00 1.8SE-03 0.00E+00 0.00E+00 0.00E+00 2.19E-04 Sr-91 5.67E-06 0.008+00 2.29E-07 0,00E+00 0.00E+00 0.00E+00 2.70E-05 Sr-92 2.15E-06 0.008+00 9.30E-08 0.00E+00 0.00E+00 0.00E+00 4.2SE-05 Y-90 9.62E-09 0.008+00 2.58E-10 0.00E+00 0.00E+00 0.00E+00 1.02E-04 Y-91 m 9.09E-1 1 0.008+00 3.52E-12 0.00E+00 0.00E+00 0.00E+00 2.67E-10 Y-91 1.41E-07 0.00E+00 3.778-09 0.00E+00 0.00E+00 0.00E+00 7.76E-05 Y-92 8.45E-10 0.00E+00 2.478-11 0.00E+00 0.00E+00 0.00E+00 1.48E-05 Y-93 2.68E-09 0.00E+00 7.4AE-1 1 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 3.398-10 1 .55E-10 0.00E+00 5.12E-10 0.00E+00 1.05E-04 Nb-95 6.22E-09 3.46E-09 1.868-09 g.ggf+00 3.42E-09 0.00E+00 2.10E-05 Nb-97 5.228-11 1.32E-1 1 4.828-12 0.00E+00 1.54E-1 1 0.00E+00 4.87E-08 Mo-99 0.00E+00 4.31E-06 8.20E-07 0.00E+00 9.76E-06 0.00E+00 9.99E-06 Tc-99m 2.47F{4 6.98E-10 8.89E-09 0.00E+00 1.06E-08 3.42E-10 4.13E-07 Tc-101 2.54E-10 3.66E-10 3.59E-09 0.00E+00 6.59E-09 1.87E-10 1.14E-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.s4E-08 0.00E+00 6.08E-09 0.00E+00 1.99E-07 0.00E+OO 9.42E-06 Ru-106 2.75E-06 0.00E+00 3.48E-07 0.00E+00 5.31E-06 0.00E+00 1.78E-04

WBN TWO.UNIT OFF$ITE DOSE CALCULATION Revision I 0 MANUAL (oDCM) Page 91 of 205 Table 6.4 - INGESTION DOSE FACTORS - DFaij (mrem/pCi ingested) (Page 2 of 8) ADULT Nuclide bone liver total body thyroid kidney lung GI-LLI Ag-1'l0m 't.60E-07 1.48E-07 8.79E-08 g.gg5+00 231E-07 0.00E+00 6.04E-05 sb-124 2.80E-06 5.29E-08 1.11E-06 6.79E-09 0.00E-00 2.188-06 7.95E-05 sb-125 1.79E-06 2.00E-08 4.26q.-07 't.82E-09 0.00E-00 1.38E-06 1 .97E-05 Te-125m 2.68E-06 9.71E-CI7 3.59E-07 8.06E-07 1.09E-05 0.00E+00 1.07E-05 Te-127m 6.77E46 2.428-06 8.25E-07 1.73E-06 2.75E-05 0.00E+00 2.27E-05 Te-127 1.10E-07 3.95E-08 2.38E-08 8.15E-08 4.49E-OT 0.00E+00 8.68E-06 Te-129m 1.15E-05 4.29E-06 '1.82E-06 3.95E-06 4.808-05 0.00E+00 5.79E-05 Te-129 3.14E-08 1.18E-08 7.65E-09 2.41E-08 1.328-OT 0.00E+00 2.37E-08 Te-13'tm 1.73E-06 8.46E-07 7.05E-07 1.34E-06 8.57E-06 0.00E+00 8.40E-05 Te-131 1.97E-08 8.23E-09 6.22E-49 1.62E-08 8.63E-08 0.00E+00 2.79E-CI9 Te-132 2.52E4A 1.63E-06 1.53E-06 1.80E-06 1.57E-05 0.00E+00 7.71E-05 l-130 7.56E-07 2.23E-06 8.80E-07 1.89E-04 3.48E-06 0.00E+00 1.92E-06 l-131 4.16E-06 5.95E-06 3.41E-06 1.95E-03 1.02E-05 0.00E+00 1.57E-06 l-132 2.03E-07 5.43E-07 1.90E-07 1.90E-05 8.65E-07 0.00E+00'l.O2E-07 l-133 1.42E-06 2.47E-06 7.53E-07 3.63E-04 4.3'lE-06 0.00E+00 2.22E-06 l-1U 1.06E-07 2.88E-07 1.03E-07 4.99E-06 4.58E-07 0.00E+00 2.51E-14 l-135 4.438-07'1.16E-06 4.28E-Ol 7.65E-05 1.86E-06 0.00E+00 1.31E-06 Cs-134 6.22E-05 1.488-04 1.218-44 0.00E+00 4.79E-05 1.59E-05 2.59E-06 Cs-136 6.51E-06 2.57E-05 1.85E-05 0.00E+00 1.43E-05 1.96E-06 2.92E-Oo Cs-137 7.978-05 1.09E-04 7.14E-05 0.00E+00 3.70E-05 1.23E-05 2.11E-06 Cs-138 5.52E-08 1.09E-07 5.40E-08 0.00E+00 8.0'tE-08 7.91E-09 4.65E-13 Ba-139 9.70E-08 6.91E-11 2.84E-09 0.00E+00 6.46E-11 3.92E-11 1.72E-07 Ba-140 2.03E-05 2.55E-08 1.33E-06 0.00E+00 8.678-09 1.46E-08 4.18E-05 Ba-141 4.7',1E-O8 3.56E-11 1.59E-09 0.00E+00 3.31E-11 2.02E-1'.t 2.?28-17 Ba-142 2.13E-08 2.19E-11 1.34E-09 0.00E+00 1.85E-11 1.248-11 3.00E-26 La-140 2.50E-09 '1.26E-09 3.33E-10 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 4.258-07 Ce-141 9.36E-09 6.33E-09 7.18E-1A 0.00E+00 2.94E-09 0.00E+00 2.42E-45 Ce.143 1.65E-09 1.22E-06 1.35E-10 0.00E+00 5.37E-10 0.00E+00 4.56E-05 Ce-144 4.88E-07 2.04E-07 2.628-A8 O.OOE+OO 1.21E-07 0.00E+00 1.65E-04 Pr-143 9.20E-09 3.69E-09 4.56E-10 g.ggf+0O 2.13E-09 0.00E+00 4.03E-05 Pr-144 3.01E-11 1.25E-11 1.538-12 0.00E+00 7.05E-12 0.00E+00 4.33E-18 Nd-147 6.29E{9 7.278-Og 4.35E-10 0.00E+00 4.25E-09 0.00E+00 3.49E-05 W-187 1.03E-07 8.61E-08 3.01E-08 0.00E+00 0.00E+00 0.00E+00 2.82E-05 Np239 1.19E-09 1.17E-10 6.45E-1't 0.00E+00 3.65E-10 0.00E+00 2.40E-45

References:

Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sb-124, Sb-125 are from Reference 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).

WBN TWCI.UNIT OFFSITE DOSE CALCULATION Revision I 0 MANUAL (ODCM) Page 92 of 205 Table 6.4 - INGESTION DOSE FACTORS - DFaU (mrem/pCi ingested) (Page 3 of 8) rEEN 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 832F.A7 8.12E-07 8"12E-07 8.128-07 8.12E-07 8.128-07 Na-24 2.30E-06 2"30E-06 2"30E-06 2.30E-06 2,30E-06 2,30E-06 2.30E-06 ?-32 2.76E-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 5.148-09 6.05E-07 Mn-54 0.00E+00 5.90E-06 1 .17E-06 0.00E+00 1"76E-06 0.00E+00 1.218-05 Mn-56 0.00E+00 1.58E-07 2.81E-08 0.00E+00 2.00E-07 0,00E+00 1.048-05 Fe-55 3.78E-06 2,68E-06 0.25E-07 0"00E+00 0.00E+00 1.70E-0S 1 .1SE-06 Fe-59 5.87E-06 1.37E-05 5.29E-oS 0"00E+00 0,00E+00 4.32E-06 3.?4E-05 Co-57 0.008+00 2,38E-07 3.99E-07 0.00E+00 0.00E+00 0.00E+00 4.44E-06 Co-58 0.00E+00 9.728-47 2.24E-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 1.778-44 1.25E-05 6.00E-06 0.00E+00 0.00E+00 0.00E+00 1.99E-06 Ni-65 7.498-47 9"578-08 4.36E-08 0.00E+00 0.00E+00 0.00E+00 5.19E-06 Cu-64 0.00E+00 1 .15E-07 5.418-08 0.00E+00 2.91E-07 0.00E+00 8.92E-06 Zn-65 5.76E-06 2.00E-05 9.338-06 0.00E+00 1.28E-05 0.00E+00 8.47E-06 Zn-69 1.47E-08 2.80E-09 1.968-09 0.00E+00 1.83E-08 0.00E+00 5.16E-09 Zn-69m 2.40E-AT 5.66E-07 5.198-08 0.00E+00 3.448-07 0.00E+00 3.1 1E-05 Br-82 0.00E+00 0.00E+00 3.048-06 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-83 0.00E+00 0.00E+00 5.74E-09 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+00 Br-85 g.gQf +00 0.00E+00 3.058-09 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 4.418-06 Rb-88 0.00E+00 8.528-08 4.54E-08 0.00E+00 0.00E+00 0"00E+00 7.30E-15 Rb-89 0.00E+00 5.50E-08 3.89E-CI8 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 8.308-03 0.00E+00 2.05E-03 0.00E+00 0.00E+00 0.00E+00 2.33E-04 Sr-91 8.07=-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+00 1.30E-07 0.00E+00 0.00E+00 0.00E+00 7.778-05 Y-90 1.37E-08 0.00E+00 3.698-10 0.00E+00 0.00E+00 0.00E+00 1 .13E-04 Y-91m 1.29E-10 0.00E+00 4.93E-12 CI.00E+00 0.00E+00 0.00E+00 6.09E-09 Y-91 2.41E-07 0.00E+00 5.398-09 0.00E+00 0.00E+00 0.00E+00 8.24E-05 Y-92 1.21E-09 0.00E+00 3.50E-11 0.00E+00 0.00E+00 0.00E+00 3.32E-05 Y-93 3.83E-09 0.00E+00 1 .05E-10 0.00E+00 0.00E+00 0.00E+00 1 .178-04 Zr-95 4.12E-08 1.30E-08 8.948-09 0.00E+00 'l .g1E-09 0.00E+00 3.00E-05 Zr-97 2.37E-09 4.69E-10 2.16E-10 0.00E+00 7 .11E-10 0.00E+00 1.278-04 Nb-95 8.22E-09 4.56E-09 2.51E-09 0.00E+00 4.42E-09 0.00E+00 1.95E-05 Nb-97 7.378-11 1.83E-1 1 6.688-12 0.00E+00 2.148-11 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-10 9.26E-10 1.208-08 0.00E+00 1.38E-08 5.14E-10 6.08E-07 Tc-1 01 3.60E-10 5.128-10 5.03E-09 0.00E+00 9.26E-09 3.12E-10 8.75E-17 Ru-103 2.55E-07 0.00E+00 1.098-07 0.00E+00 8,99E-07 g.ggf+00 2.13E-05 Ru-1 05 2.18E-08 0.00E+00 8.46E-09 0.00E+00 2158-07 0.00E+00 1.76E-05 Ru-106 3.92E-06 0.00E+00 4.948-07 0.00E+00 7.56E-06 0.00E+00 1.88E-04

WBN TWO.UNIT OFFSITE DOSE CALCULATION Revision I 0 MANUAL TODCM) Page 93 of 205 Table 6.4 - INGESTION DOSE FACTORS - DFaij (mrem/pCi ingested) (Page 4 of 8) TEEN Nuclide bone liver total body thyroid kidney lung Gl-LLl Ag-1 10m 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 1.51 E-06 8.78E-09 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+00 2.18E-06 1.93E-05 Te-1 25m 3.838-06 1.38E-0S 5.12E-07 1.07E-06 0.00E+00 0.00E+00 1 .13E-05 Te-1 27m 9.67E-06 3.43f-06 1"'l5E-06 2,30E-06 3,92E-05 0.00E+00 2.41E-05 Te- 127 1.58E-07 5.60f-08 3.40E-08 1.09E-07 6.40E-07 0.00E+00 1.228-05 Te-1 29m 1.63E-05 S.05f-0S 2"58E-06 5.26E-06 6.82E-05 0,00E+00 6.128-05 Te-129 4.48E-08 1.578-08 1,0sE-08 3.20E-08 1.88E-07 0"00E+00 2.458-07 Te-1 31m 2.44E-06 .t 7E-06 1 g.7sE-07 1.76E-06 1.22F-05 0,00E+00 g.3gE-05 Te-131 2.798-08 .15E-08 1 9.728-09 2.15E-08 1.22F-07 0.00E+00 2.298-09 Te-132 3.498-06 2.21E-06 2.08E-06 2.33E-06 2,128-A5 0.00E+00 7.008-05 t-'t 30 1 .03E-05 2.988-06 1.19E-06 2.$E-44 4.59E-06 0.00E+00 2.29E-06 t-131 5.85E-06 8.19E-06 4.40E-06 2.39E-03 1.41E-05 0,00E+00 1 .628-00 l-132 2.79F-A7 7.308-07 2.62F-A7 2.46E-05 1.15E-06 0.00E+00 3.18E-07 r-133 2.01 E-06 3.41E-06 1.048-06 4.76E-04 5.98E-06 0.00E+00 2.58E-06 l-134 1.46E-07 3.87E-07 1.398-07 6.45E-06 6.10E-07 0.00E+00 5.10E-09 l-1 35 6.10E-07 .57E-06 1 5.82E-07 1.01 E-04 2.48E-06 0.00E+00 1.74E-06 Cs-134 8.37E-05 1.978-44 9.14E-05 0.00E+00 6.26E-05 2.39E-05 2.45E-06 Cs-136 8.59E-06 3.38E-05 2.27F-AS 0.00E+00 1.84E-05 2.90E-06 2.72E-06 Cs- 137 1 .128-A4 .49E-04 1 5.19E-05 0.00E+00 5.07E-05 1.97E-05 2.128-06 Cs-138 7.76E-08 .49E-07 1 7.45E-08 0,00E+00 1 .10E-07 1 .28E-08 6.76E-1 1 Ba-139 .39E-07 9.78E-1 1 1 4.05E-09 0.00E+00 9.22E-1 1 6.74E-1 1 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 8a-141 6.71E-08 5.018-1 1 2.24E-09 0.00E+00 4.65E-1 1 3.43E-11 1.43E-13 Ba-142 2.998-08 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 7.958-1 1 1.98E_1 1 g.gpf+0O 0.00E+00 0.00E+00 2.428-A6 Ce-141 1.33E-08 8.88E-09 1.02E-09 0"00E+00 4.18E-09 0.00E+00 2.54E-05 Ce- 143 2.35E-09 ,718-0S 1 1 .91 E_10 9.66f+00 7.67E-10 0.00E+00 5.14E-05 Ce-144 0.96E-07 2.888-07 3.74E-08 0,00E+00 1.72E-A7 0.00E+00 1 .758-04 Pr-143 1.31E-08 5.23f-09 S.S2E_10 g.ggf+0O 3.04E-09 0.00E+00 4.31E-05 ?r-144 4.30E-1 1 1.76E-1 1 2.18E-12 0.00E+00 1.01E-1 1 0.00E+00 4,748-14 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 1.468-07 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 *.ZZE_1 1 g.ggf+O0 5.21 E-10 0.00E+00 2.67E-05

References:

Dose Factors for Co-57, Zn-69m, Br-82, NF97, Sb-124, Sb-125 are from Reference 17, Table 3. All others are ftom 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 similady in allorgans (Reference 24).

WBN TWO.UNIT OFFSITE DOSE CALCULATION Revision I 0 MANUAL {0DCM) Page 94 of 205 Table 6.4 - INGESTION DOSE FACTORS - DFarj (mrem/pCi ingested) (Page 5 of 8) CHILD Nuclide bone Iiver 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 1.218-05 2.42r-06 2.428-06 2.42E-06 2.42E-06 2.428-A6 2.42E-06 Na-24 5.80E-06 5.80E-06 5.908-06 5.90E-06 5.80E-06 5.80E-06 5.80E-06 ?-32 8.25E-04 3.86E-05 3.188-05 0.00E+00 0.00E+00 0.00E+00 2.28E-05 Cr-S1 0.00E+00 0.00E+00 8.908-09 4,94E-09 1,35E-09 9.02E-0e 4.72F-A7 Mn-54 0.00E+00 1.07E-05 2.BSE-06 0.00E+00 3.00E-06 0.00E+00 8.98E-0S Mn-56 0.00E+00 3.34E-07 7.54E-08 0.00E+00 4.448-07 0.00E+00 4.848-05 Fe-55 1.15E-05 6.108-06 1.89E-06 0.00E+00 0.00E+00 3.45E-06 1 .13E-06 Fe-59 1.65E-05 2.678-05 1.33E-05 0.00E+00 0.00E+00 7.74E-06 2.78E-05 Co-57 0.00E+00 4.938-07 9.98E-07 0.00E+00 0.00E+00 0.00E+00 4.04E-0S Co-58 0.00E+00 1.80H-06 5.51 E-06 0.00E+00 0.00E+00 0.00E+00 1.05E-05 Co-60 0.00E+00 5.298-06 1.56E-05 0"00E+00 0.00E+00 0.00E+00 2.93E-05 Ni-63 5.38E-04 2.888-05 1.83E-05 0.00E+00 0,00E+00 0,00E+00 1.94E-06 Ni-65 2.228-46 2.098-07 1.228-07 0.00E+00 0.00E+00 0.00E+00 2.56E-05 Cu-64 0.008+00 2.458-AT 1.48E-07 0.00E+00 5,92E-07 0.00E+00 1 .15E-05 Zn-65 1.378-05 3.65E-05 2.278-05 0.00E+0S 2"308-05 0.00E+00 6.41E-06 Zn-69 4.388-08 6.33E-08 5.85E-09 0.00E+00 3,84E-08 0.00E+00 3.99E-06 Zn-69m 7 3AE-A7 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.'l2E-09 0.00E+00 0.00E+00 0.00E+00 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 9.328-09 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-0s Sr-90 1.708-02 0,00E+00 4.31E-03 0.00E+00 0.00E+00 0.00E+00 2.29F.A4 Sr-91 2.40E-05 0.00E+00 9.06E-07 0.00E+00 0,00E+00 0.00E+00 5.30E-05 Sr-92 9.03E-06 0.008+00 3.62E-07 0.00E+00 0.00E+00 0.00E+00 1.71E-04 Y-90 4.11E-08 0.00E+00 .10E-09 0.00E+00 1 0.00E+00 0.00E+00 1,178-04 Y-91m 3.82E-10 g.9Qf+00 1.39E-1 1 0.00E+00 0.00E+00 0.00E+00 7.48E.47 Y-91 6.02E-07 0.00E+00 1.618-08 0.00E+00 0,00E+00 0.00E+00 8.028-CI5 Y-92 3.60E-09 0.00E+00 1.03E-10 0.00E+00 0.00E+00 0.00E+00 1.048-04 Y-93 1.14E-08 0.008+00 3.13E-10 0.00E+00 0.00E+00 0.00E+00 1.70E-04 Zr-95 1 .168-07 2.558-08 2.27F-AA 0.00E+00 3.65E-08 0.00E+00 2.66E-05 Zr-97 6.99E-09 1.018-09 5.96E-10 0.00E+00 1.45E-09 0.00E+00 1.53E-04 Nb-95 2.258-08 8.76E-09 6.26E-09 0.00E+00 8.23E-09 0.00E+00 1.62E-05 Nb-97 2.17*,-14 3.92E-1 1 1.83E-11 0.00E+00 4.35E-1 1 0.00E+00 1.21E-05 Mo-99 0.008+00 1.33E-05 3.29E-06 0.00E+00 2.84E-05 0.00E+00 1 .10E-05 Tc-99m 9.238-10 1.81E-09 3.00E-08 0.00E+00 2.638-08 9.19E-10 1.03E-06 Tc-101 .07E-09 .12E-09 .42E-08 0.00E+00 1 1 1 1 .S1 E-OS 5.92E-10 3.56E-09 Ru-103 7.31E-07 0.00E+00 2.81 E-07 0.00E+00 1.848-0S 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 4.21E-05 Ru-106 1.17E-05 0.00E+00 1.46E-06 0.00E+00 1.58E-05 0.00E+00 1.82E-04

WBN TWO.UNIT OFFSITH DOSE CALCULATION Revision 1 0 MANUAL (ODCM) Page 95 of 205 Table 6.4 - INGESTION DOSE FACTORS - DFaij (mrem/pCi ingested) (Page 6 of 8) CHILD Nuclide bone liver total body thyroid kidney lung Gl-LLl Ag-110m 5.39E-07 3.64E-07 2.918-07 0.00E+00 6.78E-07 0.00E+00 4.33E-05 Sb-124 1.11E45 1.44E-oT 3.89E-06 2.45E-og 0.00E+00 6.16E-06 6.94E-05 Sb-'l25 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-05 1.52E-06 3.20E-06 0.00E+00 0.00E+00 1.10E-05 Te-'127m 2.89E-05 7.78E-06 3.43E-06 6.91E-06 8.24E-05 0.00E+00 2.34E-05 Te-127 4.71E-07 1.278-07 1.01E-07 3.26E-OT 1.34E-06 g.ggf+0O 1.ME-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 1.34E-07 3.74E-08 3.18E-08 9.56E-08 3.92E-07 0.008+00 8.34E-06 Te-131m 7.20E-06 2.49E-06 2.65E-06 5.12E-06 2.4'lE-05 0.00E+00 1.01E-M Te-131 8.30E-08 2.53E-08 2.478-08 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 4.15E_05 g.ggf+oo 4.50E-05 l-'t30 2.928-06 5.90E-06 3.04E-06 6.50E-04 8.82E-06 0.00E+00 2.76E-06 l-131 1.72E45 1.73E-05 9.83E-06 5.72E-03 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-Oo l-133 5.92E-06 7.32E-06 2.77E-06 1.36E-03 1.228-05 0.00E+00 2.95E-06 l-1U 4.198-07 7.78E47 3.58E-07 1.79E-05 '1.19E-06 0.00E+00 5.16E-07 l-'135 1.75E-06 3.15E-06 1.49E-06 2.79E-04 4.83E-06 0.00E+00 2^40E-06 Cs-'l34 2.3/,E-O4 3.84E-04 8.10E-05 0.008+00 1.19E-04 4.27E-05 2.07E-06 Cs-136 2.35E-05 6.46E-05 4.'t8E-05 0.00E+00 3.44E-05 5.13E-06 2.27F-06 Cs-137 3.278-04 3.13E-04 4.62E-05 0.00E+00 1.02E-A4 3.67E-05 1.96E-06 Cs-138 2.288-CI7 3.17E-07 2.018-07 0.00E+00 2.2?E-07 2.40E-08 1.46E-07 Ba-139 4.14E-O7 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 0.008+00 2.37E-08 4.34E-08 4.218-05 Ba-141 2.00E-07 1.12E-10 6.51E-09 0.00E+00 9.69E-1l 6.58E-10 1.14F-07 Ba-142 8.74E-08 6.29E-11 4.88E-09 0.00E+00 5.09E-11 3.70E-1 1 1.14E-09 La-140 1.01E_08 3.93E-09 1.19E_09 0.00E+00 0.00E+00 g.gQf+OO 9.84E-0S 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-Ag 0.00E+00 8.68E-09 0.00E+00 2.478-05 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-A7 0.00E+00 3.61E-07 0.00E+00 1.70E-04 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-'tl 6.49E-12 6.ggf+00 2.11E-11 0.00E+00 8.59E-08 Nd-147 2.79E-08 2.26l.48 1.75E-09 0.00E+00 1.24E-Og 0.00E+00 3.58E-05 W-l87 4.29E-07 254E-07 1.148-07 0.00E+00 0.00E+00 0.00E+00 3.57E-05 Np239 5.25E-09 3.77E-10 2.65E-10 0.00E+00 't.09E-09 0.00E+00 2.79E-05

References:

Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sb-124, Sb-125 are frorn Reference 17,Table 2. All others are from Reference 4, Table E-13. NOTE: The tritium dose factorfor bone is assumed to be equal to the total body dose factor. This assumes that tritium willact similarly in all organs (Reference 24).

WBN TWO.UNIT OFFSITE DOST CALCULATION Revision 1 0 MANUAL (0DCM) Page 96 of 205 Table 6.4 - INGESTION DOSE FACTORS - DFaij (mrem/pCi ingested) (Page 7 of 8) INFANT Nuclide bone liver total body thyroid kidney lung GI-LLI H-3 3.08E-07 3.088-07 3.08E-07 3,08E-07 3.08E-07 3.08E-07 3.08E-07 c-14 2.378-05 5.068-06 5,06E-06 5.06E-06 5.06E-06 5.06E-06 5.06E-06 Na-24 1.01E-05 1.018-05 1"01 E-05 1.01 E-05 'l ,01E-05 1.01E-05 1 .01E-05 P-32 1.70E-03 1.008-04 6,59E-05 0.00E+00 0.00E+00 0.00E+00 2.30E-05 Cr-51 0.00E+00 0.00E+00 1"418-08 9.20E-09 2.o1E-09 1.79E-08 4.11E-07 Mn-54 0.00E+00 1.99E-05 4,51 E-06 0.00E+00 4.41 E-06 0.00E+00 7.31E-06 Mn-56 0.00E+00 8.18E-07 1.41E-07 0.00E+00 7.03E-07 0.00E+00 7.43E-05 Fe-55 1.39E-05 8.988-06 2.40E-06 0.00E+00 0.00E+00 4.39E-06 1.14E-06 Fe-59 3.08E-05 5.38E-05 2.128-05 0.00E+00 0.00E+00 1,59E-05 2.57E-05 Co-57 0.008+00 1.15E-06 1.878-06 0.00E+00 0.00E+00 0.00E+00 3.92E-06 Co-58 0.00E+00 3.60E-06 g.g8E-06 0.00E+00 0.00E+00 0.00E+00 8.97E-06 Co-60 0.00E+00 1.08E-05 2.558-05 0.00E+00 0.00E+00 0.00E+00 2.57E-05 NL63 6.34E-04 3.92E-05 2.24F-45 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 0.00H+00 0.00E+00 4.05E-05 Cu-64 0.00E+00 6.09E-07 2.82F-47 0.00E+00 1,03E-06 0.00E+00 1.25E-05 Zn-SS 1.84E-05 6.31E-05 2.91E-05 0.00E+00 3.06E-05 0.00E+00 5.33E-05 Zn-69 9.33=-08 1.68E-07 1.25E-08 0.00E+00 6.98E-09 0.00E+00 1.37E-05 Zn-69m 1,508-06 3.06E-06 2.798-07 0.00E+00 1.24E-06 0.00E+00 4.248-05 Br-82 0.00E+00 0.00E+00 1.278-05 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-83 0.008+00 0.00E+00 3.63E-07 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-84 0.008+00 0.008+00 3.82E-07 0,00E+00 0,008+00 0,00E+00 0.00E+00 Br-85 0.008+00 0.00E+00 1.94E-08 0,00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-86 0.008+00 1.708-04 8.40E-05 0.00E+00 0,00E+00 0.00E+00 4.35E-06 Rb-88 0.00E+00 4.98r-07 2.rc8-47 0.00E+00 0.00E+00 0.00E+00 4.85E-07 Rb-89 0.008+00 2.868-07 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-0s 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 2.07F-04 Y-90 8.69E-08 0.00E+00 2.338-09 0.00E+00 0.00E+00 0.00E+00 1.20E-04 Y-91 m 8.10E-10 0.00E+00 2.76F-11 0.00E+00 0.00E+00 0.00E+00 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 7.658-09 0.00E+00 2.15E-10 0.00E+00 0.00E+00 0.00E+00 1.46E-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-11 0.00E+00 7.658-1 1 0.00E+00 3.09E-05 Mo-99 0.00E+00 3.40E-05 6.63E-06 0.00E+00 5.088-05 S.00E+00 1 .12E-05 Tc-99m 1.928-09 3.96E-09 5.10E-08 0.00E+00 4.268-08 2.07E-09 1 .15E-06 Tc-101 2.27*.-Ag 2,86E-09 2.83E-08 0.00E+00 3.408-0S 1.56E-09 4.86E-07 Ru-103 .48E-06 1 0.00E+00 4.95E-07 0.00E+00 3"088-0S 0.00E+00 1.80E-05 Ru-105 1.368-07 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 3.01 E-06 0.00E+00 2,85E-05 0.00E+00 1.83E-04

I'YBN TWO.UNIT OFFSITE DOSE CALCULATION Revision 1 0 MANUAL TODGM) Page 97 of 205 Table 6.4 - INGESTION DOSE FACTORS - DFaU (mrem/pCi ingested) (Page I of 8) INFANT Nuclide bone liver total body thyroid kidney lung Gl-LLl Ag-1 10m 9.96E-07 7 .278-A7 4.81 E-07 0,00E+00 1.04E-06 0.00E+00 3.77E-05 sb-124 2.14r-A5 3"158-07 6.638-06 5.68E-08 0.00E+00 1.34E-05 6.608-05 sb-125 1.23E-05 1.19E-07 2.53E-06 1.54E-08 0.00E+00 7.72F.86 1"64E-05 Te- 125m 2.33E-05 7.79E-05 3.15E-06 7.84E-06 0.00E+00 0.00E+00 1"11H-05 Te-1 27m 5.85E-05 1.94E-05 7.088-0S .69E-05 1 1.44E-04 0,00E+00 2,36f-05 Te- 127 'l .00E-06 3.35E-07 2.158-07 8.14E-07 2.44E-06 0"00E+00 2.'tr0H-05 Te-1 29m 1.00E-04 3.438-05 1.548-05 3.84E-05 2,50E-04 0.00E+00 5.97f-05 Te- 129 2.848-A7 9.798-08 6.638-08 2.38E-07 7.ATE-AT 0.00E+00 2^27F.45 Te-131 m 1 .52E-05 6.128-06 5.05E-06 .24E-05 1 4.21 E-05 0.00E+00 1,038-04 Te- 131 1.76F.47 6.508-08 4.94E-08 .57E-07 1 4.50E-07 g.ggf+00 7 ^118-06 Te-132 2.08E-05 1.03E-05 9.61 E-06 .52E-05 1 6.44E-05 0.00E+00 3.818-05 t-130 6.00E-06 .32E-05 5.30E-00 .48E-03 1 1 1.45E-05 0"00E+00 2.838-06 t-131 3.59E-05 4.23E-05 1.86E-05 .39E-02 1 4.94E-05 0.00E+00 1.51E-06 t-132 1,66E-06 3.37E-06 1.20E-06 .58E-04 1 3.76E-OS 0.00E+00 2.738-06 f-133 1.25E-05 .82E-05 5.33E-06 3.31 E-03 1 2,148-05 0,00E+00 3.08E-06 t-1M 8.SgE-07 1.78E-06 6.33E-07 4.15E-05 1.998-06 0^00E+00 1 .84E-06 f-135 3.64E-06 7 .248-46 2.64E-06 6.49E-04 8,07E-06 0,00E+00 2.62E-06 Cs-134 3.77F-44 7.03E-04 7.14E-05 0.00E+00 1.918-04 7 .42r.A5 1.91 E-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"648-04 6.648-05 1.91E-06 Cs-138 4.81=-AT 7 .828-A7 3.79E-07 0.00E+00 3,908-07 6,09E-08 1.25E-06 Ba-139 8.81E-07 5.84E-10 2.55E-08 0.008+00 3.51 E-10 3.54E-10 5,58E-05 Ba-140 1.71E-04 1.71E-07 8.81 E-06 0.00E+00 4,06E-08 1,05E-07 4.20E-05 Ba-141 4.25F-A7 2.918-10 1.34E-08 0.00E+00 1"75E-10 1.77*.-10 5.19E-06 Ba-142 ,848-07 .538-10 9.06E-09 0.00E+00 1 1 g.g1E-11 9.268-1 1 7.59E-07 La-140 2.11E-08 8.32E-09 2.14E-09 0.00E+00 0.00E+00 0.00E+00 9,77E-05 La-142 1.108-09 4,04E-10 9.67E-1 1 0.00E+00 0.00E+00 g.ggf +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 9.828-06 1.12E-09 0.00E+00 2.86E-09 0.00E+00 5.738-05 Ce-144 2.98E-06 1.228-06 1.S7E-07 0.00E+00 4.93E-07 0.00E+00 1"718-04 Pr-143 8.13E-08 3.048-08 4.038-09 0.00E+00 1 .13E-08 0.00E+00 4.298-05 ?r-144 2.748-14 1.06E-10 1.38E-1 1 0.00E+00 3.84E-1 1 0.00E+00 4.938-06 Nd-147 5.53E-08 5.688-08 3.48E-09 0.00E+00 2.19E-08 0.00E+00 3.608-05 W-187 9.03E-07 6.28E-07 2.17F-AT 0,00E+00 0.00E+00 0.00E+00 3.698-05 Np-239 .11E-08 9.93E-10 5.61 E-10 0.00E+00 1 1.98E-09 0.008+00 2.87E-05 Referenses: Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sb-124, Sb-125 are from Reference 17, Table 1. Allothers are ftom 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).

I/VBN TWO.UNIT OFFSITE DOSE CALCULATION Revision 1 0 MANUAL {oDclul} Page 98 of 205 Table 6.5 - BIOACCUMULATION FACTORS {Bi} FOR FRESHI,YATER FISH Nuclide Bi Nuclide Bi H-3 9.0E-01 Tc-99m 1"5E+01 c-14 4,6E+03 Tc-101 1,5E+01 Na-24 1.0E+02 Ru-103 1.0E+01 P-32 1.0E+05 Ru-105 1"0E+01 Cr-51 2.0E+02 Ru-106 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"08+01 Te-'l25m 4.0E+02 Co-58 5.0H+01 Te-127m 4.0E+02 Co-60 5.08+01 Te- 127 4.0E+02 Ni-63 1.0E+02 Te-129m 4.0E+02 NL65 1.0E+02 Te-129 4.0E+02 Cu-64 5.0E+01 Te-131m 4.0E+02 Zn-65 2.0E+03 Te-131 4,08+02 Zn-69 2.0E+03 Te-132 4"0f;+02 Zn-69m 2,0E+03 t-130 4.0H+01 Br-82 4.28+42 t-131 4.0H+01 Br-83 4.2E+42 t-132 4.08+01 Br-84 4.28+42 t-133 4"0E+01 Br-85 4.ZF+OZ t-134 4,0E+01 Rb-86 2.0E+03 t-135 4.0E+01 Rb-88 2.0E+03 Cs-134 1.9E+03 Rb-89 2,0E+03 Cs-136 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-139 4.0E+00 Sr-92 5.6E+01 Ba-140 4.0E+00 Y-90 2.5E+01 B,a-141 4.0E+00 Y-91m 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+01 Y-93 2.5E+01 Ce-141 1.0E+00 Zr-95 3.3E+00 Ce-143 1.0E+00 Zr-97 3.38+00 Ce-144 1.0E+00 Nb-95 3.08+04 Pr-143 2.5E+01 Nb-97 3.0E+04 Pr-144 2.5E+01 Mo-99 1.0E+01 Nd-147 2.58+01 w-187 1.28+03 Np-239 1.08+01

References:

Bioaccumulation factors 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' bioaccumulalion factors are from Reference 4, Table A-1.

WBN TWO-UNIT OFFSITE DO$E CALCULATION Revision 1 0 MANUAL (oDCM) Page 99 of 205 Table 6.6 - EXTERNAL DOSE FACTORS FOR STANDING oN CONTAMINATED GROUND - DFij (mremlh per pCi1m2) {Page 1 of 2) Nuclide Total Body $kin 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-S1 2,20E-10 2.60E-10 Mn-54 5.80E-09 6.80E-09 Mn-Sfi 1 .1 0E-08 1 .30E-08 Fe-55 0.0 0.0 Fe-59 8.008-09 9.40E-09 Co-57 1.77E-09 2,21 E-09 Co-58 7.008-09 8.208-09 Co-60 1.708-08 2.00E-08 Ni-63 0.0 0.0 Ni-65 3.70E-09 4.308-09 Cu-64 1.50E-09 1.70E-09 Zn-65 4.00E-09 4.60E-09 Zn-69 0.0 0.0 Zn-69m 5.50E-09 6.59E-09 Br-82 3.18E-08 3.908-08 Br-83 6.40E-1 1 9.308-11 Br-84 1.20E-08 1.40E-08 Br-85 0^0 0.0 Rb-86 6.30E-10 7 .2A*14 Rb-88 3.50E-09 4.00E-09 Rb-89 1.50E-08 1,80E-08 Sr-89 5.S0E-13 6.50E-13

                      $r-91       7.10E-09 8.30E-09 Sr-92       9.00E-09 1.00E-08 Y-9S        2,2AF-12 2.608-12 Y-91m        3.808-09 4.40E-09 Y-S1        2,40F-11 2.7AE-11 Y-92         1.60E-09 1.90E-09 Y-93        5.708-10 7.80E-10 Zr-95       5.00E-09 5.808-09 Zr-97       5.50E-09 6.408-09 Nb-95        5.10E-09 6.008-09 Nb-97        8.1   1E-09    1.008-08 Mo-99         1.90E-09 2.208-09 Tc-99m        9.60E-10 1.10E-0S Tc-101       2.70E-09 3.00E-09 Ru-103       3.60E-09 4.208-09 Ru-105       4.50E-09 5.10E-09

WBilI TWO.UNIT OFFSITE DOSE CALCULATION Revision I 0 MANUAL (oDCM) Page 100 of 205 Table 6.6 - EXTERNAL DOSE FACTORS FOR STANDING ON CONTAMINATED GROUND - DFii (mremlh per pCi/m2) (Page 2 of 2) Nuclide Total Body Skin Ru-106 1.50E-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-125m 3.50E-1 1 4,80E-1 1 Te-1 27m 1.10E-12 1.30E-12 Te-127 1 .008-1 1 1 .10E-1 1 Te-129m 7.70E-10 9.00E-10 Te-'129 7 3AE-10 8,40E-10 Te-131m 8.40E-09 9.90E-09 Te-131 2.24E-09 2.60E-06 Te-132 1.74E-09 2.00E-09 l-130 1.4AE-08 1 .70E-08 l-131 2.808-09 3.40E-09 r-132 1.7AE-08 2.00E-08 t-133 3.70E-09 4.50E-09 l-134 1.60E-08 1,90E-08 t-135 1.20E-08 1.40E-08 Cs-134 1.20E-08 1.408-08 Cs-136 1,50E-08 1.70E-08 Cs-1 37 4.20E-09 4.90E-09 Cs-1 38 2.10E-08 2"40E-08 Ba-139 2.40E-09 2.70E-09 Ba- 140 2.10E-09 2,40E-09 Ba-141 4.30E-09 4.90E-09 Ba-142 7.908-09 9.00E-09 La-140 1.50E-08 1.70E-08 La-142 1,50E-08 1.80E-08 Ce-141 5.50E-10 6.20E-10 Ce-143 2.208-09 2^50E-09 Ce-144 3.?08-10 3.70E-10 Pr-143 0.0 0.0 Pr-144 2.00E-10 2.308-10 Nd-147 1.00E-09 1.20E-09 w-187 3.10E-09 3.608-09 Np-239 9.50E-10 1 .10E-09

References:

Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sb-124 and Sb-125 are from Reference '18. All others are from Referenc,e 4, Table E-6.

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WBN TWO.UNIT OFFSITE DOSE CALCULATION Revision I 0 MANUAL {ODCM} Page 104 of 205 7.0 . GASEOUS EFFLUENTS INTRODUCTION There are six discharge points for gaseous radioactive effluents from WBN. 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 below, 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 for elevated releases; therefore, all releases are considered to be ground-level. Various plant syetems 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 identiff any unexpected radioactivity releases, and to ensure that the dose rate limits of ODCM Control 1.2.2.1are met. Each monitor has an alarm/trip setpoint which causes the monitor to alarm if the monitor's setpoint is exceeded. The monitors do not have separate 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 flow rate to ensure 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, to determine compliance with ODCM Controls 1.2.2.2and 1.2.2.3. For continuous releases, the pathways are sampled for radioactivity periodically, as required by Table 2.2-2. 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 and 7.2. The sampling results are also used to determine a setpoint for the associated noble gas radiation monitorfor 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 projected dose is calculated, as outlined in ODCM Section 7.5, to determine compliance with ODCM Control 1.2.2.4.

WBN TWO.UNIT OFFSITE DOSE CALCULATION Revision 1 0 MANUAL (oDCM) Page 105 of 205 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-0'l33 (Reference 3) and Regulatory Guide 1.109 (Reference 4). Because all releases 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 (Reference 4). RELEASE'DISGHARGE POINTS DESCRIPTION There are six discharge points at WBN that are monitored for airbome radioactive effluents. These are: a CVE for each unit, a common Service Building Exhaust, a common 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 buildings. 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 BuildiFo 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 cfrn and is monitored by radiation monitor 0-RE-90-132B. Auxiliarv Buildino Exhaust The Auxiliary Building exhausts at a maximum total design flow of 228,000 cfm (2of 4 ventilation fans and 1 fuel handling fan). This discharge point exhaust is monitored by radiation monitor 0-RE-90-1018. 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-90-400A. There are nine Waste Gas Decay Tanks (WGDTs) that discharge into the waste gas header which is released into a Shield Building Vent (see Figure 7.3). The Train A Auxiliary Building Gas Treatment System (ABGTS) is operated during a WGDT release. Each WGDT has a design capacity of 600 fF and a maximum design release rate of 100 cfm [SOURCE NOTE 17]. The WGDT release point is monitored by radiation monitor 0-RE-90-118.

WBN TWO.UNIT OFFSITE DOSE CALCULATION Revision I 0 MANUAL (oDCM) Page 106 of 205 The Auxiliary Building Gas Treatment System (ABGTS) draws from the Auxiliary Building Secondary Containment Enclosure and exhausts to the Shield Building Exhaust. Any activity 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 Coniainment 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 byradiation monitors 1,2-RE-90-'130 and 1,2-RE-90-131. lf the lncore Instrument Room Purge is operating exclusively, it exhausts at 800 cfm, and is monitored by the Containment Purge Monitors given above. The common header exhausts io the Shield Building Exhaust. 7.1 GASEOUS EFFLUENT MONITOR INSTRUMENT SETPOINTS Airbome effluent noble gas monitor setpoints are determined to ensure that the dose rate al the UNRESTRICTED AREA BOUNDARY does not exceed the dose rate limits given in ODCM Control 1.2.2.1and 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 he 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: Setpoint Release Pathway Monitor Default Setpoint Limit Setpoint 1-RE-90-1 30 Containrnent 2-RE-90-1 30

                                            $ection  7 .1 .1 .3          {1}        $ection  7 .1 .2 Purge          1-RE-90-131 2-RE-90-1 31 WGDT           0-RE-90-1 18          Section 7.1.1 ,2            S*",        Sectiofi 7 .1 .2 Shield 1-RE-90-4004                                      S*"*

Building SectionT.l .1.3 Section 7 .1 .2 2-RE-90-4004 Exhaust Auxiliary Building 0-RE-90-101 B Section 7^1.'l .3 S*r* Section 7.1 .2 Exhaust Seruice Building 0-RE-90-1328 Section 7 .1 .1 .3 S*"* Section 7 ,1 .2 Exhaust 1-RE-90-1 19 S*"* CVE $ection 7.1.1 ,4 Section 7 .1 ,2 2-RE-90-1 19 ('t) Sr", or Tech Spec value from setpoint and scaling document, whichever is smaller.

WBN TI'IIO-UNIT OFFSITE DOSE CALGULATION Revision I 0 MANUAL (ODCM) Page fiT of 205 7.1.1 Default Monitor Setpoints 7.1.1.1 Reserved for future use. 7.1.1.2llYaste Gas Decay Tank Effluent Monitor (0-RE-90-118) During periods of release, the methodology in Section 7.1.2will be used to determine the monitor setpoint and may be set at a default value. Site procedures will document and control this value. 7.1.1.9 Shield Building Exhaust (1,2-RE-90400A), Auxiliary Building Exhaust (0-RE-90-1018), Containment Purge Effluent Monitors (1,2-RE-90-130,-'131), and Service Building Exhaust (0-RE-90-1328) 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 DRprlDR equal to 1.0. The default setpoints for the shield building monitors are calculated in units of pCi/s. The default setpoints willbe defined in plant procedures. 7 .1.1.4 Condenser Vacuum Exhaust Vent (1,2-RE-90-l I 9) This discharge point effluent monitor is set to ensure compliance with ODCM Control 1.2.2.1and to identify 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 identify any further increases in the leak rate. 7.'t.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 .'l .2.1 and 7.1 .2.2) trhich 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 after 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 .'l .1) to determine which is used for the release.

WBN TWO.UNIT OFFSITE DOSE CALCULATION Revision 1 0 MANUAL (ODCM) Page 108 of 205 7 .1.2.1 Expected Monitor Response The expected monitor response, ER, is determined using the following equation: ER = BKG +lt, c, (7.1) i where: BKG = monitor background, cpm. E; = efficiency factor for the monitor for nuclide i, cpm per pCilcc. This term may also be refered to as a response or calibralion factor. Q = measured concentration of nuclide i, pCi/cc. 7 .1.2.2 Expected Response Setpoint An expected response setpoint SEq is calculated for the monitor for each release: Sr* -xIg,c,+x BKG (7,21 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 < 2.0. lsouRcE NoTE 151 7.1.2.3 Calculated Maximum Setpoint The calculated maximum setpoint, Sr"* in cpm, coresponding to the dose rate limit is determined using the following equation: E\={o. s** r.. on @n-nxQfl+axc sF[q}ul ' (7.3)

l. L '))

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 2l SF = safety factor for the monitor, dimensionless. Safety factors will be < 1. Safety factors for each monitor are defined in approved plant procedures. DRL1,',,= the dose rate limit, mrem/y.

      = 500 mremly 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.
      = DRra for total body (as described in Section 7.2.1),
      = 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.

WBN TWO.UNIT OFFSITE DOSE CALCULATION Revision 1 0 MANUAL {ODCM} Page 109 of 205 7.r.2.4@ 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 (afrer the release, the monitor is normally retumed to the default setpoint).

1. lF Sen < So*"rtt ( S*", RepOfted = Sdefautt 2' lF SER ( Sr* ( So"raun Reported = Sr*

3. lF Sa"r"ra < SeR

                             " Sr",,      RepOfted = SeR
                                                     = Sd"r"un (for Containment Purge monitors) 4.lF  Srn  ) S*"*                 Reported = $*u,

WBN TWO.UNIT OFFSITE DOSE CALCULATION Revision 1 0 MANUAL {ODCM} Page 110 of 205 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 bodydose rate must meet the condition (from NUREG-0133 Section 5.2.1): I luqk

DFBi k)" e* ]J. soo mre*:/y Since there are no elevated release points at WBN, the elevated release terms in the equation (Vi and Q;s) are not used. Substituting the flow (f) multiplied by the concentration (G) 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:

DR* = trl i ci DFq (7.41 where: dQ = tenain adjusted relative conceniration, 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 1986-2005 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. C; = concentration of noble gas nuclide i in effluent stream, pGi/cc. DFBI = total body dose factor due to gamma radiation for noble gas nuclide i, mrem/y per pCi1m3 (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.

WBN TWO.UNIT OFFSITE DOSE CALCULATION Revision 1 0 MANUAL (ODCM) Page 111 of 205 7.2.2skin Dose Rate The calculated skin dose rate must meet the condition (from NUREG-0133 Section 5.2.1): I {lhtE(tl + r.IR,h,-]* [rtsi + I I Dqt]l.k]e*1]. 3000 mrem/y Sin"" tn"r" are no elevated release poinis at WBN, the stack terms in the equation, DFS;, (X/Q)", 81, and Qis, ?re not used. Substituting the flow (f) multiplied by ihe 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: DR. = tf +l.llDqt) r.s) Tc,(rE, where: X/Q = tenain adjusted relative concentration, s/m3. Relative air concenkations 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 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. Q = 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). 1.11 = the average ratio of tissue to air energy absorption coefficients, mrem/mrad. (1.1 I is used from Regulatory Guide 1.109 Equation B-7 in lieu of '1.1 from NUREG-O133) DFy, = dose conversion factor for external gamma for noble gas nuclide i, mrad/y per pCi/m3 (Table 7.4). 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.

WBN TWO.UNIT OFFSITE DOSE CALCULATION Revision I 0 MANUAL (ODCM) Page 112 of 205 7.2.3 4-131,1-133, Tritium and All Radionuclides in Particulate Form with Half-Lives of Greater Than I 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, DR; 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-O133 Section 5.2.11: Ii q(w.q, + w'Q* ) s I 5oo nror/v Since there are no elevated release points at WBN, the elevated release terms (W" and Qs) are not used. Substituting the flow (f) multiplied by the concentration (G) for the release rate (Q) in the above equation, and inserting the appropriate dispersion factor (rJQ or D/Q) for each pathway considered, the organ dose rate, DRi in mrem/y, is calculated using the following equation: DR, = r{c, t (n * + R.* ) + h, *, + ft (R.,, + Rr"rpr + Rwi * *", r]} (7,6) Ta, where: f = flowrate of effluent stream, cc/s. Cr = concentration of tritium in effluent stream, gCi/cc. I/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 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).

      = (/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-Rcpr = Grass-cow-milk dose factor for tritium, mrem/y per pCi/m3. Dose factor is calculated as described in Section 7.8.7..

C1 = concentration of nuclide i in efffuent stream, pCi/ce. 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. DIQ = tenain 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 't986-2005 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). 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. RMpi = Grass-beef dose factor for each identified nuclide i, m2-mrem/y per pCi/s. Dose factors are calculated as described in Section 7.8.3. RvFi = Fresh leafy vegetable dose factor for each identified nuclide i, m2-mrem/y per pCi/s. Dose factors are calculated as described in Section 7.8.5. Rci = 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 fom among the dose rates calculated for all the organs and all age groups. lt is compared to the limit of 1500 mrem/y.

WBN TWO.UNIT OFFSITE DOSE CALCULATION Revision 1 0 MANUAL {oDCM} Page 113 of 205 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 terrain adjusted annual-average 1/Q based on 1986-2005 meteorological data (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.{ 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 I l.*r, k), qi,

k),,q*.l* F,e* + 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 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 gamma air dose, Dn in mrad, is calculated for each release using the following equation: DT - l,eE-o6tI Q, D{,,r (7.7') i where: 1 .9E-06 = conversion factor, y/min.

g/Q = highest tenain adjusted unrestricted area boundary annual-average relative concentration, s/m3 (from Table 7.3).

Q; = release rate for nuclide i, pCi/s. DFv, = dose conversion factor for external gamma for nuclide i (Table 7 .4), mradty 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.

WBN TWO.UNIT OFFSITE DOSE CALCULATION Revision 1 0 MAf{UAL {0DCM} Page 114 of 205 7.3.2 Beta Dose to Air NUREG-0133 Section 5.3.1 provides the following equation for the calculation of the beta air dose from noble gases: D=k I t*, k), q,,

po),o,,

J* [po[0,,

ft). o- J]

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 calculafing 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, D6 in mrad, is calculated for each release using the following equation: Dp : 1.eE-o6t T Q, DS, r (7.8) where: 1.9E-06= conversion factor, y/min. X/Q = highest tenain adjusted unrestricted area boundary annual-average relative concentration, s/m3 (from Table 7.3). Qi = release rate for nuclide i, pCi/s. DFBi = dose conversion factor for extemal beta for nuclide i, mradly 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 Dose - 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 current 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 accordan ce with Surveil lance Req u ire ment 2.2.2.2. to determ ine com pliance.

WBN TI'IIO.UNIT OFFSITE DOSE CALCULATION Revision I 0 MANUAL (ODCM) Page 115 of 205 7.4 DOSE DUE TO t-13t, t-133, C-14, TRITIUM AND ALL RAIIlONUCLlDES tN PARTTCULATE FORM WTH HALF.LIVES OF GREATER THAN 8 DAYS 7.4.1 Organ Dose Calculation Organ doses due to l-1 31 , l-1 33, C-14, tritium and all radionuclides in particulate form with halilives of greater than I days are calculated for each release for the mitical receptor. The critical receptor is defined as the UNRESTRICTED AREA BOUNDARY in the sector with the highest annual average tenain adjusted 1/Q. The annual average 1/Q and DIQ are calculated using the methodology in Sections 7.9.2 and 7.9.3 using the historical 1986-2005 meteorologicaldata (Table 7.21. Aconservative assumption is used to select the dispersion factors for the critical receptor. The highest calculated 7-lQ and DIQ values are chosen from Table 7.'t values after being multiplied by the applicable terrain adjustment factors (see 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 leafy 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 intemal organ doses for all age groups. NUREG-0133 Section 5.3.1 provides the following equation for the calculation of the organ dose ftom radioiodines, radioactlve materials in particulate form with halflives greater than 8 days: D : kI n,(W.q.

w,ei. +'W,Q* + w,qi,)

i 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) times the length of the release (T). The general equation for the calculation of organ dose is: Di - 3.r7E-o8TI In*t{W*Q,) {7.e) i P where: 3.17E-08 = convercion factor, yls 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-beef, and vegetation pathways, and mrem/y per pCilm3 for inhalation, C-14 and tritium ingestion pathways. Equations for calculating these dose factors are given in Section 7.8. Wp = dispersion factor for the location and pathway P (from Table 7.3),

           = tenain adjusted 1/Q for the inhalation, C-14 and tritium ingestion pathways,
           = tenain adjusted D/Q for the food and ground plane pathways, Qi          = release rate for radionuclide i, pCi/s.

WBN TWO.UNIT OFFSITE DOSE CALCULATION Revision I 0 MANUAL {ODCM} Page 116 of 205 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 Cumulative Organ 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 Requirement2.2.2.3 to determine compliance. 7.5 DOSE PROJECTIONS ln accordance with ODCM Surveillance Requirement2.2.2,4.1, dose projections willbe performed. This will be done for the gamma dose, the beta dose and the maximum organ dose.

,={("10),:r}+c ld            )

r.1o) where: D = the 31-day dose projection, mrem. a = the cumulative dose for the quarter, mrern. b = the projected dose for this release (as calculated in Sections 7.4.1,7.4.2 and 7.4.3), mrem. c = any anticipated additional dose in the next month from other sources, 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 Su rvei lance Requ re ment 2.2.2.4. 1 to d eterm ine compliance. I i 7.6 GASEOUS RADWASTE TREATMENT SYSTEM DESCRIPTION The GASEOUS RADWASTE TREATMENT SYSTEM (GRTS) described in the WBN FSAR shall be maintained and operated to keep releases ALARA. A simplified flow diagram for the GRTS is given in Figure 7.3.

WBN TYI'O.UNIT OFFSITE DOSE CALCULATION Revision I 0 MANUAL (0DClttU Page 117 of 205 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. Allreal pathways 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 corresponding calendar quarter will be used. For iodine releases, it is assumed that half the iodine released is in organic form. Organic 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: D=I X,* {D1* or DFpr ) {7.1 1 ) where: Xim = concentration of nuclide i at location m, pCi/m3. Air concentrations are calculated as described by Equation 7.39. DFyi

dose conversion factor for extemal gamma for nuclide i, mradly per pCi/m3 (Table 7.4).

DFg = dose cpnversion factor for external beta for nuclide i, mrad/y per pGilm3 (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-SFI DFq (7.12) i where: SF= shielding factor. This factor is conservatively set equal to 1.0. Xirn = concentration of nuclide i at location m, pCilm3. Air concentrations are calculated as described by Equation 7.39. DFB; = total body dose conversion factor due to submersion in a semi-infinite cloud of noble gases for nuclide i, mrem/y per pCi/ms (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: rl D= {l.llsFI x,* D+ f *I x- DFq (7.1s) Ir)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. Xim = concentration of nuclide i at location m, pCilm3. Air concentrations are calculated as described by Equation 7.39. DFyi = dose conversion factor for extemal gamma for nuclide i, mrad/y per prCi/m3 (Table 7.4). DFS; = skin dose conversion factor due to submersion in a semi-infinite cloud of noble gases for nuclide i, mremly per pCiim3 (Table 7.4).

WBN TWO.UNIT OFFSITE DOSE CALCULATION Revision I 0 MANUAL {ODCM} Page 118 of 205 7.7.3 Radioiodine, Particulate, C-14, and Tritium - Maximum Organ Dose Regulatory Guide 1.109 Equations C-2, -4, and -13 provide the following equations for the calculation of doses ftom the release of iodine and particulate radionuclides: D = Sr IC*fio, (forground contamination) i D = BR,L z, Ro, (for inhalation) i o =lno(ts,,frc* +u,*c* +urocr, +u.frc,o) (for ingestion) i 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 (DlQ or /Q) multiplied by the total release (Q) for the concentration terms (C) as follows: D: BRo\5e,a**s.I# e,Ro,*IRo Be,(u*-fr *u * +() r, +(l r, f ,\ iii 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: o:ZLse, R, *I#e, R, *U,#Q, R, iii Since the calculation of C-14 and tritium concentrations in vegetation are based on air concentration rather than ground deposition (Equations C-8 and C-9 in Regulatory Guide 1.109), separate terms are added to the equation to account for the C-14 and tritium ingestion dose pathways. ln addition, a tenain adjustment factor (TAF) is added. Therefore the equation for calculating the organ dose, Q in mrem, is: D; :3.rzE-08{k)IR*a,*e)ERo,.,Q.,o-;[elT"**(3)n.-(t)",]o,] Q'14) where: 3.17E-08 = convercion factor, y/s. D/Q = Tenain Adjusted Relative deposition for location under consideration, m-2. Relative deposition is calculated as described in Equation 7.41. Rpr = ingestion dose factor for pathway P for tritium, mamrem/y per pCi/s. lngestion pathrarays available for consideration are the same as those listed above for Rp;. Equations for calculating ingestion dose factors for tritium are given in Sections 7.8.7 through 7.8.12. Qr = adjusted release rate for tritium for location under consideration, prCi/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 equal to the actual release rate decayed for an average travel time during the period. Qr:Q,Zfrery (U*) (7.1 5) k=l where: Qn = 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. It = radiological decay constant for tritium, s-l. x = downwind distance, m. u1 = midpoint value of wind speed class interval k, m/s.

WBN TWO.UNIT OFFSITE DOSE CALCULATION Revision 1 0 MANUAL (ODGM) Page 119 of 205 Rpcra = ingestion dose factor for pathway P for C-14, mlmrem/y per pCi/s. lngestion pathways available for consideration are the same as those listed above for Rs. Equations for calculating ingestion dose factors for C-14 are given in Sections 7.8.'l 5 through 7 .8.20. Qcra = adjusted release rate for C-14 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 equal to the actual release rate decayed for an average travel time during the period. 9 Qcr+ = Q",u,L-fu",p [ +,- k=l f) where: C",0,= initial average release rate for C-14 overthe period, pCils. fk = joint relative frequency of occurrence of winds in windspeed class k blowing toward this exposure point, expressed as a fraction. 1614= radiological decay constant for C-14, s-1. x = downwind distance, m. uk = midpoint value of wind speed class interval k, m/s. Rpi = ingestion dose factor for pathway P for each identified nuclide i (except C-14 and tritium), m2-mrem/y per pCi/s. lngestion pathways available for consideration include: pasture grass-milk animal-milk ingestion - R6p (see Section 7.8.1\. stored feed-milk animal-milk ingestion - Rss (see Section 7.8.2). pasture grass-beef ingestion - Ryp (see Section 7.8.3). stored feed-beef ingestion - Rys (see Section 7.8.4). fresh leafy vegetable ingestion - Ryp (see Section 7.8.5). stored vegetable ingestion - Rys (see Section 7.8.6). Roi = Dose factor for standing on contaminated ground, mLmremly per pCi/s. The equation for calculating the ground plane dose factor is given in Section 7.8.14. '{"lQ = Relative concentration for location under consideration, s/m3. Relative concentrations are calculated as described by Equation 7.40. Rri = lnhalation dose factor, mrem/y per pCi/m3. The equation for calculating the inhalation dose factor is given in Section 7.8.13. Q; = adjusted release rate for nuclide i for location under consideralion, 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 identffied pathways for each receptor including ground contamination, inhalation, vegetable ingestion (for identified garden locations), cow andlor 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). 7.7.4 Population Doses The population dose is detennined using Equation D-1 from Regulatory Guide 1.'109: D:kf eor,, lD", FP,- mi For determining population doses to the S0-mile population around the plant, each compass sector is broken down 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

WBN TWO.UNIT OFFSITE DOSE CALCULATION Revision I 0 MANUAL {0DCM) Fage 120 of 205 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: Dosepop =ffifnerlq PoP- FP" DosEp where: 0.001 = conversion from mrem to rem. TAF Tenain Adjustment Factor. Given the population centers are far from the site, the straight line dispersion factors provide conservative dose results when compared to a variable trajectory model. RATIOp = ratio of average to rnaximum dose for pathway P. Maximum ingestion rates are given in Table 6.3. (Average ingestion rates are obtained from Reference 4, Table E4.)

         = 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 vegetable ingestion ratio also applies to leafy vegetables.)

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

         = 0.015, 0.167, 0.153, 0.665 for infant, child, teen and adult, respectively (fractions taken ftom 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 correction 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= exp(-[,to) (r.17) For beef: ADC'- ery {- Ato) Al,u (7.1 8) l-eryp?lr,,o) where: I1 = decaY constant for nuclide i, s-1. 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 beel 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 beef, 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 50-mile population.

WBN TYI'O.UNIT OFFSITE DO$E CALCULATION Revision 1 0 MANUAL (ODcrvl) Page 121 of 205 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.

WBN TWO.UNIT OFFSITE DOSE CALCULATION Revision I 0 MANUAL (ODCM) Page 122 of 205 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 atmqspheric 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 RESTRICTED AREA BOUNDARY (WBN UFSAR Table 12.4-2\. The total dose rate is the sum of the adult whole body inhalation dose rate, lhe 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 RESTRICTED AREA BOUNDARY is 105 mrem/y, based on a continuous 2000 hlyoccupancy. 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 near the UNRESTRICTED AREA BOUNDARY and from estimates of the dose from gaseous effluents) willbe reviewed on an annual basis to ensure that the actual exposure to any individuals is less than 100 mremly for these locations. The results of this review will be included in the Annual Radiological Effluent Report pursuant to ODCM Administrative Control 5.2.

WBN TWO.UNIT OFFSITE DOSE CALCULATION Revision 1 0 MANUAL {ODCM} Page 193 of 205 7.8 GASEOUS RELEASES. DOSE FACTORS 7.8.1 Pasture Grass4owlGoat-Milk lngestion Dose Factors - R6pi (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:

                                                                                      -elp (--i Ti.I              Bil,*L:.: e)ry{-ito) 1l D,--D}FLU-aptp F*m[       mia f\ ery    ,ryt,Itufin )rdi       pl'rtn :*

slq) ,ery [l"rn) { Y';iur"E P;

                                                                                                                                    ,7, I

lce tlthe dor Sirno oseie eq quatiiornnin

                        )qu                                    andt7.7 .J (rEq in Se3ct:tiornsi 7., 4at                    luatiolns'

qtru i7.

7.9 aand 7.1 .14 4)cco

4) corln'rtaiintthe vafliatble edid (equal the to th' produ(

p .tcttoftl 'elt the r,re le t tht eas 'att iase ri te( ])(0l)a nd'l I thtede ,pOr on fac;tor ti(or S'itir tcl ,r (Dr (l le Q)),

                                                                                                         )),  the fl te]I, factr fac  )r tcto   isl ren mTlaitningI  n ir   the the   above uatic equal eq IUe   ion are  edt defin ine ned as i r{   the dcOS,ieffa<
                                    )li tht             cto r.FFot rct       -otrr parstu l"te!

I )(gr grass, he S,, th,eviarrriat abk tt,6isd ile)tx his sdrle rfinled clas i zer'o in 1 Regu Re ryulaatory Gui G uidee1) 1.1109),)., th reefcore thr there hat: ext po)nen,tiall1ter xpo ETrm dr(ro3ps,outtt lofl rf th ihe equal r uatiti(oni. TI IThe! re$iu1Itino ng(dose

tor eeQuatir factot tion

                    )n is:

5. B--[-"'p(-4'r))) r.rrl Rcp = lou DFL,, u* &,er

                                                 ",p(-4t*lr,            {#-n*

I yrl, P4 I where: 106 = conversion factor, pAi/pCi. DFLH = ingestion dose conversion factor for nuclide i, age group a, organ j, mremlpCi (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). Qr = animal's consumption rate, kg1d. \ = decay constant for nuclide i, s-1 fable 6.2). $n = transport time from milking to receptor, s. fp = fraction of time animal spends on pasture, dimensionless. r = fraction of activity retained on pasture gtrass, dimensionless. Ag = the effective decay c,onstant, due to radioactive decay and weathering, s-1.

           = r\i + AW.

trra = weathering decay constant for leaf and plant surfaces, s-1. Lp = time pasture is exposed to deposition, s. Yp = agricultural productivity by unit area of pasture grass, kg/m2. Bi, = transfer factor for nuclide i from soil to vegetation, pCilkg (wet weight of vegetation) per pCi/kg (dry soil). (Table 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.

WBN TWO.UNIT OFFSITE DOSE CALCULATION Revision 1 0 MANUAL TODCM) Page 124 of 205 7.8.2 Stored Feed-CowlGoat-Milk lngestion Dose Factors - Rcsi (m2-mrem/y per pci/s) The generaldose equation stated in Regulatory Guide 1.109 for calculating the annualdose 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-5 and C-10 are inserted into the above equation to yield the following:

s' [ - e]q(- rt, )l]

D DFL u F* Q. e,p (- a.t * )., * .-n m, I {qtf"d 1-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 fte 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, lherefore 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:

&si = 106 DFLi"j ury    r q, opt4,-)r,                                                                   ro, where:

{#}{ry.*r#},r 'tOo = conversion factor, p0i/pOi. DF!3; = 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). Q1 = animal's consumption rate, kg/d. f" = fraction of time animalspends on stored feed, dimensionless. Ai = decay constant for nuclide 1, s-1 (fable 6.2). t161 = transport time from milking to receptor, s. Lsr = time between harvest of stored feed and consumption by animal, s. r = fraction of activity reiained on pasture grass, dimensionless. lg = the effective decay constant, due to radioactive decay and weathering, s-l

         =Ai  +lw.

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

WBN TWO.UNIT OFFSITE DOSE CALCULATION Revision 1 0 MANUAL {0DCM) Page 125 of 205 7.8.3 Pasture Grass-Beef lngestion Dose Factors - Rrrp; (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: D = DFLU* F, e. e,p(-l"t, )., {eT*-J -#} "+1-m, ; Since the dose equation in Sections 7 .4 and 7.7.3 (Equations 7.9 and 7 .'l,4) contain the variable d1 (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 individualslaughters and eats the animal over a period of time (t"6) fieference 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: &,pi:r0dDFL'u**o,{ry}",,Fa,,)rte1l4J.4[#] rz.zrl where: 106 = conversion factor, pCi/pCi. DFL6; = 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, kg/y. F6 = transferfactorfor nuclide ifrom cow's feed to beel d/kg (Table 6.2). Q1 = cou/s consumption rate, kg/d. A1 = decay constant for nuclide i, s-l (Table 6.2). t"u = time for receptor to consume a whole beef, s. t = transport time from slaughter to consumer, s. ip = fraction of time cow spends on pasture, dimensionless. r = fraction of activity retained on pasture grass, dimensionless. ,\s = the effective decay constant, due to radioactive decay and weathering, s-1, equal to li + lw. i\\, = weathering decay constant for leaf and plant surfaces, s-1. tp = time pasture is exposed to deposition, s. Yp = 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) tb = time over which accumulation on the ground is evaluated, s. P = effective surface density of soil, kgt71f' NOTE: Factors defined above which do not reference a table for their numerical values are given in Table 6.3.

WBN TWCI.UNIT OFFSITE DOSE CALCULATION Revision I 0 MANUAL TODCM) Page 126 of 205 7.8.4 Stored Feed-Beef lngestion Dose Factors - RMs; (m2-mrem/y per pCi/s) The general dose equation stated in Regulatory Guide 1.109 for calculating the annualdose 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 beef pathway, Regulatory Guide 1.109 Equations C-5 and C-12 are inserted into the above equation to yield the following:

                                               -                   r"'[r -

D: r\ sIo,'L DFL u.o r- eu exp(-2t-1 {'[' "]{-"'")] Y,,1,

                                                                *          "]!(-'u')l] *4-rrrl P2         j    -' -n 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, faclors are added to account for the decay during the time the animals are consuming the stored feed {t"s) and during the time period of over which the beef is being consumed (t"6) (Reference 10). The resulting dose factor is:

R r*, = Io"$Fli*jtl-*&Q, ery) tc.uI 4,[r -elp(- l,tu xl (7.22) {! Ai t.u Pi, where: 106 = conversion factor, pCi/pCi. DFLi6; = 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. F11 = transfer factor for nuclide i from cods feed to beef, d/kg (Table 5.2). Q1 = cot/l/s consumption rate, kgfd. A1 = decay constant for nuclide i, s-1 ffable 6.2). t"u = 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. tsr = time between harvest of stored feed and consumption by cow, s. r = fraction of activity retained on pasfure grass, dimensionless. t = time stored feed is exposed to deposition, s. Ys1 = agricultural productivity by unit area of stored feed, kg/m2. A6 = the effective decay constant, due to radioactive decay and weathering, s-I,

          =  li+Aw.

lry = weathering decay constant for leaf and plant surfaces, s-1. Bi, = lransfer 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 girren in Table 6.3.

WBN TWO.UNIT OFFSITE DOST CALCULATION Revision I 0 MANUAL (0DCM) Page 127 of 205 7.8.5 Frcsh Leafy Vegetable lngestion Dose Factors - Rypl (m2-mrem/y per pGils) 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(UfRadionuclide 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:

DFLUFL" 4 e-[1_e;l(:It'n] r",,"y D

{.[#. "-n1-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. Thus, the dose factor is: (: rttuJ]

       -r 06DFL,.jexp(- l,irr,. )urr. F,- {t [t-:.,:-ry

B,,n11 -ery(-r,toI (7.23)

I Y,L, PT, where: 106 = conversion factor, pCi/pCi. DF!e; = ingestion dose conversion factor for nuclide i, age group a, organ j, mrem/pCi (Table 6.4). A; = decay constant for nuclide i, s-1 lTable 6.21. trt" = average time between harvest of vegetables and their consumption and/or storage, s. uFLa = consumption rate of fresh leafy 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 vegetables, dimensionless. AE = the effective decay constant, due to radioactive decay and weathering, s-1.

         =Ai+Aw 41ry      = decay constant for removal of activity on leaf and plant surfaces by weathering, s-'1.

t = exposure time in garden for ftesh leafy andlor stored vegetables, s. Y; = agricultural yield for fresh leafy vegetables, kg/rnz. Biu = transfer factor for nuclide i from soil to vegetables, pOi/kg (wet weight of vegetation) per pCi/kg (dry soil). (Table 6.2) t5 = time period over wtrich accumulation on the ground is evaluated, s. P = effective surface density of soil, kdm2. NOTE: Factors defined above which do not reference a table for their numerical values are given in Table 6.3.

WBN TWO.UNIT OFFSITE DOSE CALCULATION Revision 1 0 MANUAL (ODCM) Page 128 of 205 7.8.6 Stored Vegetable lngestion Dose Factors - Rvst 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: r [t - ep (- z' t" )] B' [' - t:l (- *' ))) D = DFL uFL"

                 L d i{

YnA,

H.
G r,," )

)'

Since the dose equation in Sections 7.4 and 7.7.3 (Equations 7.9 and7.14) contain the variable d1 (equal to the product of the release rate {Q) and the deposition factor (DlQ)), 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 (tsv); this term assumes that the stored vegetables are eaten throughout the storage period (Referenee 10). Thus, lhe dose factor is: R,s=106 DFL", ery(-)"itr.)u.n t i&qp}{#-Wj v.rot where: 106 = conversion factor, pCi/pCi. DFL6i = ingeslion dose conversion factor for nuclide i, age group a, organ j, mremlpCi (Table 6.4). J\; = decay constant for nuclide i, s-1 fiable 6.2). tr," = average time between harvest of vegetables and their consumption andlor storage, s. Us" = consumption rate of stored vegetables by the receptor in age group a, kg/y. fs = fraction of stored vegetables grown locally, dimensionless. ts, = time between storage of vegetables and their consumption, s. r = fraction of deposited activity retained on vegetables, dimensionless. Ag = the effective decay constant, due to radioactive decay and weathering, s-1.

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

t" = exposure time in garden for fresh leafy andlor stored vegetables, s. Y., = agriculturalyield for stored vegetables, kg/m2. Biu = transfer factor for nuclide i from soil to vegetables, pCi/kg (wet weight of vegetation) per pCi/kg (dry soil). (Table 6.2) b = 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.

WBN TWO.UNIT OFFSITE DOSE CALCULATION Revision I 0 MANUAL {0DCluI} Page 129 of 205 7.8.7 Tritium-Paslure Grass-CodGoat-Itlilk Dose Factor - Rcpr (mrem/yper prCi/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 - DFLUup 4, Q, erytft*)e, frlrrr[f)] Since the dose equation in Sections 7 .4 and 7.7.3 (Equations 7.9 and 7 .141 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: ft.* =103 106 Drr*,, F* Q, u* rr[f)] t e)pl,r,,*) (7,25) [o where: 103 = conversion factor, g/kg. 106 = conversion'factor, pCi/pCi. DFL13; = 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 ftaction 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. fp = fraction of time animal spends on pasture, dimensionless. A1 = decay constant for tritium, s-t Gable 6.2). tr, = transport time from milking to receptor, s.

I,VBN TWO.UNIT OFFSITE DOSE CALCULATION Revision I 0 MANUAL (ODCM) Page 130 of 205 7.8.8 Tritium-Stored Feed4odGoat-Milk Dose Factor - Rcsr (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 Fac.tor(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: n -DFL u"n L Q, ery I t,* ) e,

                                          #lrr, [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: rl0.rr[#ll te{P{-}'r* (&"u)

^Rara where:
      - r03 r06   DFIr. F* e,     uoo L [f)] tH)J,E       r\ ru"/lh-ery '*)ll e{p(-;rt*'f 4,,,, -I            (7.26) 103      = conversion factor, g/kg.

106 = conversion factor, pCi/p0i. DFL16; = ingestion dose conversion factor for H-3 for age group a, organ j, mrem/p m/pCi (Table 6.4). F;1 = transfer factor for H-3 from cow's feed to beef, d/kg (Table 6.2). Q1 = cow's consumption rate, kg/d. Uap = milk ingestion rate for age group a,Lly. 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 ater. H = absolute humidity of the atmosphere, glm3. fs = fraction of time cow spends on stored feed, dimensionless. A1 = decay constant for tritiurTl, s-1 fiable 6.2). k* = transport time from milking to receptor, s. Lsr = 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.

WBN TWO.UNIT OFFSITE DOSE CALCULATION Revision 1 0 MANUAL {0DCM) Page 131 of 205 7.8.9 Tritium-Pasture Grass-Beef Oose Factor - Rupr (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 1.109 Equations C-9 and C-10 are inserted into the above equation to yield the following: f) -DFLU@ 4 Q, $s{-ir.}Q, {[o?srgJ]l -tH al- )l 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 (;6/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** = loi 106 DFLr*j where: ri e, LI*u F.r, l#l] to *,p f r.,t,, {ry} {ry} t7.27) 103 = conversion factor, g/kg. 't06 = conversion factor, pCi/pCi. DFL161 = ingestion dose conversion factor for H-3 for age group a, organ j, mrem/pOi (Table 6.4). Frr = transfer factor for H-3 from co#s feed to beef, dlkg (Table 6.2). Q1 = covr/s consumption rate, kg/d. U"* = beef ingestion rate for age group a,kgly. 0.75 = the fraction of totralfeed that is water. 0.5 = the ratio of the specific activity of the feed grass water to the atmospheric water. H = absolute humid'rty of the atmosphere, g/m3. fp = fraction of time cow spends on pasture, dimensionless. A1 = decay constant for tritium, s-1 Gable 6.2). t" = transport time from slaughter to consumer, s. Lp = time pasture is exposed to deposition, s. Lu = time for receptor to consume a whole beef, s.

WBN TI'YO.UNIT OFFSITE DOSE CALCULATION Revision 1 0 MANUAL {ODCM} Page 132 of 205 7.8.10 Tritiumtored Feed-Beef Dose Factor - Rmsr (mrem/y per pCi/m3) The general dose equation stated in Regulatory Guide '1.109 for calculating the annual dose ftom consuming foods containing atmospherically released radionuclides (Equation C-13) is: Dose(D) = Dose Conversion Factor(DFL)nUsage Rate(U).Radionuclide Concentration in Media(C) For the beef pathway, Regulatory Guide 1.109 Equations C-9 and C-10 are inserted into the above equation to yield the following: fi -DFL u*, E e, ery (-,1*" ) e, s 610, [Y)] Since the dose equation in Sections 7 .4 and 7.7.3 (Equations 7.9 and 7 .14) contain the variables for the release rate (Q) and the dispersion factor (1/Q), lhe 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: x,*sr=r03106DFr{d&,Q,u*[r"[H)]r*t u,,l{ffd}{qttPi r.mr where: 103 = conversion factor, g/kg. 106 = conversion factor, pCilrrCi. DFL16; = ingestion dose conversion iactor for H-3 for age group a, organ j, mrem/pCi (Table 6.4). Fs = transfer factor for H-3 from cou/s feed to beef, d/kg (Table 6.2). Qr = cou/s consumption rate, kg/d. U"* = beef ingestion rate for age group a,kgly. 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 = absolufe humidity of the atmosphere, g/m3. G = fraction of time cow spends on stored feed, dimensionless. 11 = decay constant for tritium, s-1 (Table 6.2). tr = transport time from slaughter to consumer, s. Lst = time to consume stored feed, s. tn = 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.

WBN TWO.UNIT OFFSITE DOSE CALCULATION Revision 1 0 MANUAL (oDCM) Page 133 of 205 7.8,11Tritium-Fresh Leafy Vegetable Dose Factor - Rvrr (mrem/yper pCi/m3) The general dose equation slated 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-9 is inserted into the above equation to yield the following: D- DFLUno exp (tr ,") Qtr nl,0.7. ;{ 0,5 hc el" L, t H ')l

                                                 ,.4 Sirnce rce metdo)se) equratic th                              )Ito nss7. $alnd 7.-'

tilon iniSe:ctions uati onls 7.9 and 7 .14) contain the variables for the

                                                              .7 .3 (E:qu
   )ase rate (a)) antdth rellease                I the dirspe)rsion sio n faccto 1   [or'(xll0)r), th effac ors$r'emaining in the above equation are defined ctor as thee d   lse oos facI ctor. The relsultting Th              1g dcdooseefe fatctor 'is q'

(or.J

                                     -(a.s Rn - 103 106 DrI.o              0\.7:5)t            {J,Fl,l f; ery)(- 1,   tn" )

Ltn (7.2e L, IH Ir ')l where: 103 = conversion factor, g/kg. 106 = conversion factor, pCi/pCi. DFL16; = 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 ihe vegetabhs water to the atmospheric water. H = absolute humidity of the atmosphere, g/m3. UFu = consumption rate of fresh leafy vegetables by the receptor in age group a, kg/y. fL = fraction of fresh leafy vegetables grown locally, dimensionless. 11 = decay constant for tritium, s-t (fable 5.2). tn" = time between harvest of vegetables and their consumption andlor storage, s. NOTE: Factors defined above v'rhich do not reference a table for their numerical values are given in Table 6.3.

WBN TWO.UNIT OFFSITE DOSE CALCULATION Revision I 0 MANUAL (ODCM) Page 134 of 205 7.8.12 Tritium-Stored 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 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 uun ery (- rto") e, s frla, [H)] 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. An additional decay term is added to account for the decay during the time the vegetables are stored (this tenn assumes that the vegetables are being ealen during the storage period) (Reference 10). The resulting dose factor is: DFk* t- exp (- 4 /rr, xl R,*, =ro3106 u-. * {r eryc4to.) (7.30) [orr[f)] ,\t, v where: 103 = conversion factor, g/kg. 106 = conversion factor, pCi/pCi. DFL16; = ingestion dose conversion factor for tritium for age group a, organ j, mrem/pOi (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. A1 = decay constant for tritium, s-t Fable 6.2). ts, = time between harvest of stored vegetables and their consumption andlor storage, s. hc = time between harvest of vegetables and their storage, s.

WBN TWO.UNIT OFFSITE DOSE CALCULATION Revision 1 0 MANUAL (ODCM) Page 135 of 205 7.8.13lnhalation Dose Factors - R11 (mrem/y per pCi/m3) The inhalation dose factors are calculated using the equation provided in NUREG-0133, Section 5.3.1.1. Rr - 106 DFA_: BRu (7.31 ) where: 106 = conversion factor, pCi/pCi. DFAiaj = 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, maly gable 6.31. 7.8.14 Ground Plane Dose Factors - R6; (m2-mrem/y per pCi/s) The ground plane dose factorc 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. Ro, =lo6 B76oDFG,j U)1 g32t i[r-"ry(- where: 106 = conversion factor, p0i/pOi. 8760 = conversion factor, h/y. DFGij = dose conversion factor for standing on contaminated ground for nuclide i and organ j (total body and skin), mrem/h per pCi/m2 (Table 6.6). \ = decay constant of nuclide i, s{ gable 6.2;. tb = time period over rvlrich the ground accumulation is evaluated, s (Table 6.3).

WBN TWO.UNIT OFFSITE DOSE CALCULATION Revision I 0 MANUAL {0DCM) Page 136 of 205 7.8.15 G-14-Pasture Grass-CodGoat-Milk Dose Factor - Rcpqr (mrem/y per pCi/m3) The general dose equation stated in Regulatory Guide 't .1 09 for calculating the annual dose from consuming foods containing atmospherically released radionuclides (Equation G-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-8 and C-10 are inserted into the above equation to yield the following: D=DFLU* L Q, elrp (rti")O",r6[*i:) Since the dose equation in Sections 7 .4 and 7.7.3 (Equations 7.9 and 7 .14) conlain the variables for the release rate (Q) and the dispersion factor (/Q), the factors remaining in the above equation are defined as the dose factor. The resulting dose factor equation is: Rr*,4 :103 106 DFl-crgaj qcr+ Qr U.o + e4) {- ir,+t,n*) (7.33) []i*l where: 103 = conversion factor, g/kg. 106 = conversion factor, pCi/pCi. DFL",o"j = ingestion dose conversion factor for carbon 14 for age group a, organ j, mremlpOi (Table 6.4). Fr"ro = transfer factor for carbon 14 from animal's feed to milk, d/L (Table 6.2). Q1 = animal's consumption rate, kgld. Uap = milk ingestion rate for age group a, Uy. 0.'11 = the fraction of total plant mass that is natural carbon, dimensionless. 0.16 = is equal to the concentration of natural carbon in the atmosphere, in $m3. fp = fraction of time animal spends on pasture, dimensionless. l",o = decay constant for carbon 14, s-1 ffable 6.2). tfm = transport time from milking to receptor, s. NOTE: Factors defined above which do not reference a table for their numerical values, are listed in Table 6.3.

WBN TWO.UNIT OFFSITE DOSE CALCULATION Revision I 0 MANUAL (ODGM) Page 137 of 205 7.8.16 C-14-Stored Feed-CodGoat-Milk Dose Factor - Rcscrr (mremly 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-8 and C-10 are inserted into the above equation to yield the following: D:DFLU* 4, Q, exp [2tu,)Qcr+ 6(#) 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 (i6lQ), 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 equation is: [, -r*(-;.r+/"qr )] ft.r, -103 106 DFLcr+ai Fncr4 Qr Un* (r#)- ery (- /,.,rr., ){ (7.34) Arr+lcs/' where: 103 = conversion factor, g/kg. 106 = conversion factor, pCi/pCi. DFL"ro"j = ingestion dose conversion factor for carbon 14 for age group a, organ j, mrem/pCi (Table 6.4). F*".,, = transfer factor for carbon 14 from cora/s feed to milk, d/L (Table 6.2). Q = animal's consumption rate, kg/d. Uap = milk ingestion rate for age group a, L/y. 0.11 = the fraction of total plant mass that is natural carbon, dimensionless. 0.16 = is equal to the concentration of natural carbon in the atmosphere, in g/m3. fs = fraction of time animal spends on stored feed, dimensionless. L.ro = decaY constant for carbon 14, s-1 (Table 6'2). tcsf = time between harvest of stored feed and consumption by animal, s. tfm = transport time from milking to receptor, s. NOTE: Factors defined above which do not reference a table for their numerical values, are listed in Table 6^3.

WBN TWO.UNIT OFFSITE DOSE CALCULATION Revision 1 0 MANUAL TODCM) Page 138 of 205 7.8.17 C-l4-Pasture Grass-Beef Dose Factor - Rspcra (mremly 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 . 109 Equations C-8 and C-1 0 are inserted into the above equation to yield the following: D=DFLU* 4, e, ery Gztu")e",-6(*i*) Since the dose equation in Sections 7.4 and 7.7.3 (Equations 7.9 and 7.14) contain the variables for the release rate (Q) and the dispersion factor (i1lQ), 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:

                                                                     ! l" C1 +t+ )lt  ery I

I {L elq3 Ro,*.,u =103 10" DFL.,roi Fo,u e, Lr*,{*i*)fo exp(-r.,*t, L C1 .rt cu nl (7.35)

F lu 1t cp l, CT 4t cb where: 103 = conversion factor, g/kg. 106 = conversion factor, pCilpCi. DFL",o"i = ingestion dose conversion factor for carbon 14 for age group a, organ j, mrem/pCi (Table 6.4). Ff",o = transfer factor for carbon 14 from cow's feed to meat, dlkg (Table 6.2). Q1 = cow's consumption rate, kg/d. Uam = meat ingestion rate for age group a, kg/y. 0.11 = the fraction of total plant mass that is naturalcarbon, dimensionless. 0.16 = is equal to the concentration of natural carbon in the atmosphere, in g/m3. fp = fraction of time cow spends on pasture, dimensionless. I"ro = decay constant for carbon 14, s-1 (Table 6.2). ts = transport time from slaughter to consumer, s. tep = time pasture is exposed to deposition, s. bO = time for receptor to consume a whole beef, s. NOTE: Factors defined above which do not reference a table for lheir numerical values, are listed in Table 6.3^

IJYBN TVI'O.UNIT OFFSITE DOSE CALCULATION Revision 1 0 MANUAL (ODCM) Page 139 of 205 7.8.18 G-{4-Stored Feed-Beef Dose Factor - Rxscr* (mrem/y per pCi/m3) The general dose equation stated in Regulatory Guide 1.'t09 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 beef pathway, Regulatory Guide 1.109 Equations C-8 and C-10 are inserted into the above equation to yield the following: D:DFLU* 4, Q, elp (-zti")Q" ,rfr(#) Since the dose equation in Sections 7 .4 and 7.7.3 (Equations 7.9 and 7 .14) contain the variables for the release rate (Q) and the dispersion factor (2glQ), 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: (7.36) where: 103 = conversion factor, g/kg. 106 = conversion factor, pCi/pCi. DFL"ro"i = ingestion dose conversion factor for carbon 141or age group a, organ j, mrem/pCi (Table 6.4). Ff"ro = transfer factor for carbon 14 from cow's feed to meat, dlkg (Table 6.2). Q1 = cow's consumption rate, kg/d. Uam = meat ingestion rate for age group a, kg/y. 0.11 = the fraction of total plant mass that is natural carbon, dimensionless. 0.16 = is equal to lhe concentration of natural carbon in the atmosphere, in g/m3. fs = fraction of time cow spends on stored feed, dimensionless. L",,0 = decaY constant for carbon 14, s-1 (Table 6.2)' ts = transport time from slaughter to consumer, s. tcsf = time between harvest of stored feed and consumption by animal, 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 listed in Table 6.3.

WBN TWO.UNIT OFFSITE DOSE CALCULATION Revision I 0 MANUAL (ODCM) Page 140 of 205 7.8.19 G-l4-Fresh Leafy Vegetable Dose Factor - Rvrcu (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-l3) is: Dose(D) = Dose Conversion Facto(DFL)*Usage Rate(U).Radionuclide Concentration in Media(C) Forthe vegetable pathway, Regulatory Guide 1.109 Equation C-8 is inserted into the above equation to yield the following: D = DFLU* ery (- zto")e.,* 6 (*i*) Since the dose equation in Sections 7.4 and 7.7.3 (Equations 7.9 and 7.'14) contrain 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 is: fi,,., 4:r03 106 DFL.,-,, u,* fr e4p(- i.,+rr,.) (7.371 [*i*) where: tO3 = conversion factor, g/kg. 106 = conversion factor, pCi/pOi. DFLel4d = ingestion dose conversion factor for carbon 14 for age group a, organ j, mrem/pci (Table 6.4). 0.11 = the fraction of total plant mass that is natural carbon, dimensionless. O.'tO = is equal to the concentration of natural carbon in the atmosphere, in g/m3. Ur,_. = consumption rate of fresh leafy vegetables by the receptor in age group a, kg/y. f1 = fraction of tesh leafy vegetables grown locally, dimensionless. l"lu = decaY constant for carbon 14, s-1 ffable 6.2). hc = time between harvest of vegetables and their consumption and/or storage, s. NOTE: Factors defined above which do not reference a table fortheir numerical values, are listed in Table 6.3.

WBN TWO.UNIT OFFSITE DOSE CALCULATION Revision I 0 MANUAL {ODCM} Page 141 of 205 7.8.20 C-l4-Stored Vegetables Dose Factor - Rvscr (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) Forthe vegetable pathway, Regulatory Guide 1.109 Equation C-9 is inserted into the above equation to yield the following: D=DFLU* os (-ztn")e.,u 6(#) Since the dose equation in Sections 7 .4 and 7.7.3 (Equations 7.9 and 7 .'14) contain the variables for the release rate (Q) and the dispersion factor (;6/Q), the factorc 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: n,".,u -ro3 106 DFLc,l,j ,,.. rs [t

                                                    - *rp (- 1.14r," I ery ( irrutr,.)               (7.38)

[*+*) { lrr4lr,, where: 103 = conversion factor, g/kg. 106 = conversion factor, pCilpCi. DFLslsl = ingestion dose conversion factor for carbon 14 for age group a, organ j, mrem/pCi (Table 6.4). 0.1 'l = the fraclion of total plant mass that is natural carbon, dimensionless. 0.16 = is equal io the concentration of natural carbon in the atmosphere, in g/m3. Usa = consumption rate of stored vegetables by the receptor in age group a, kgly. fg = fraction of stored vegetables grown locally, dimensionless. ?,c14 = decay constant for carbon 14, s-1 fi'able 6.2). tsv = time between harvest of stored vegetables and their consumption andlor storage, s. thc = time between harvest of vegetables and their storage, s. NOTE: Factors defined above which do not reference a table for their numerical values, are listed in Table 6.3.

WBN TWO.UNIT OFFSITE DOSE CALCULATION Revision 1 0 MANUAL TODCM) Page 142 of 205 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 't0m and temperature measurements at 10m and 46m. A sector-average dispersion equation consistent with Regulatory Guide 1.111 is used. The dispersion model considerc plume depletion (using information from Figure 7.4), 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 Ranse {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 8.3-10.9 9.59 o J >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 correspond to A=1, B=2, ..., G=7. 7.9.1 Air Concentration - I Air concentrations of nuclides at downwind locations are calculated using the following equation: 917 _\r I xi:*rAr# LII*I tl"ffi

            -T A T]     i/. f*, Qt     P
                                       -?sL n
                                                       *)                                                  (7,39) where:

ftr = joint relative frequency of occurrence of winds in windspeed class k, stability class I, blowing toward this exposure point, expressed as a fraction. Q1 = average annual release rate of radionuclide i, prCi/s. p = fraction of radionuclide remaining in plume (Figure 7.4). TAF = site specific terrain adjustment factor (see Table 7.3). Calculated as described in Section 7.9.4. Lzt = vertical dispersion coefficient for stability class I which includes a building wake adjustment,

G

            .lo]+-         ,

T7E t-or = rl3 clr, whichever is smaller. where: o7l 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-$ectional area t1630 m2) {Reference 23). Uj = midpoint value of wind speed class interval k, m/s.

WBN TWO.UNIT OFFSITE DOSE CALGULATION Revision I 0 MANUAL {ODCM} Page 143 of 205 x = downwind distance, m. n = number of sectors, 16. tri = radioactive decay coefficient of radionuclide i, s-l 2tJn = sector width at point of interest, m. 7.9.2 Adjusted Relative Concentration - /Q Relative concentrations of nuclides at downwind locations are calculated using the following equation: x -TArTI T F i fo, a where:

           ;:i   I:1  t;ffi                                                                               t7.40) fn      = joint relative frequency of occurrence of winds in windspeed class k, stability class l, blowing toward this exposure point, expressed as a fraction.

TAF = site specific terrain adjustment factor (see Table 7.3). Calculated as described in Section 7.9.4. Zd = vertical dispersion coefficient for stability class I which includes a building wake adjustment,

l"

          .loi   +-"*   ,

Y7r or = r/3 o,r , whichever is smaller. wfiere: s1 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-sectionalarea (1630 m1(Reference 23). u1 = midpoint value of wind speed class interval k, m/s. x = downwind distance, m. n = numberof sectors, 16. 2nxln = sector width at point of interest, m. 7.9.3 Adjusted Relative Deposition - DIQ Relative deposition of nuclides at downwind locations is calculated using the following equation: 9=rori a-^'"# i# +(+) s.41) where: frr = joint relative frequency of occurrence of winds in windspeed class k and stability class l, blowing toward this exposure point, expressed as a fraction. dr = relative deposition rate, m-I (from Figure 7.6). TAF = site specific terrain adjustment factor (see Table 7.3). Calculated as described in Section 7.9.4. x = downwind distance, m. n = numberof sectors, 16. 2raln = sector width at point of interest, m.

WBN TWO.UNIT OFF$ITE DOSE CALCULATION Revision I 0 MANUAL (ODCM) Page lM of 205 7.9.4 Terrain Adjustment Factor -TAF As discussed in Reference 5, the straighlline 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 terrain 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 factors to lhe straight-line modeldispersion factors is defined as the TAF. The dispersion factors used in the dose rate and dose calculations described in Sections 7.2.?,7.2.3,7.3.1, 7.3.2, and7.4.1 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 7.4O and 7.41 for the UNRESTRICTED AREA BOUNDARY locations identified in Table 7.1,for 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 modfy the /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.

WBN TI'I'O.UNIT OFFSITE DOSE CALCULATION Revision I 0 MANUAL {0DCM) Page 145 of 205 Table 7.1 - WBN - OFFSITE RECEPTOR LOCATION DATA Receptor Sector DI$TANCE

D/Q*

                                                                       ?(,rQ from plant (m)             (s/m3)                 {1Imz}

Unrestricted Area Boundary N 1 550 3.01E-06 4.78E-09 Unrestricted Area Boundary NI{E 1 980 3,53E-06 6.83E-09 Unrestricted Area Boundary NE 1 580 5.00E-06 5.24E-09 Unrestricted Area Boundary ENE 1 370 7.24e.-46 5.1Sr-0S Unrestricted Area Boundary E 1 280 8.56E-06 6.048-09 Unrestricted Area Boundary ESE 1 250 7.948-06 6^44H-09 Unrestricted Area Boundary SE 1254 7,40E-06 6.338-09 Unrestricted Area Boundary SSE 1250 4.03E-06 5.478-09 Unrestricted Area Boundary s 1340 2.81 E-06 6.168-09 Unrestricted Area Boundary SSW 1 550 2.07E-06 5.25E-09 Unrestricted Area Boundary SW 1 670 2,12F.46 3.508-09 Unrestricted Area Boundary WSW 1 430 3.04E-06 3.54E-09 Unrestricted Area Boundary W 1 460 1.76E-06 1.73E-09 Unrestricted Area Boundary WNW 1 400 9.96E-08 9.528-10 Unrestricted Area Boundary NW 1400 1^21E-06 1,25E-09 U nrestricted Area Boundary NNW 1460 1.68E-06 1.938-09 Liquid Discharoe NIA NIA NOTE:For quarterly airbome dose calculations, doses will also be calculated for all locations identified in the most recent land use Gensus, and for any additional points deemed necessary. "These 1/Q and D/Q values must be multiplied by the sector specific Tenain Adjustment Factor (see Table 7.3) priorto selecting the criticalUNRESTRICTED AREA BOUNDARY location to be used in dose calculations.

WBN TWO.UNIT OFFSITE DOSE CALCULATION Revision'l 0 MANUAL (oDCM) Page 146 of 205 TabIe 7.2 . JOINT PERCENTAGE FREQUENCIES OF WIND DIRECTION AND WIND SPEED FOR DIFFERENT STABILITY CLASSES (Page 1 of7) STABIIITY CI,AsS A Watt.s Ba:' Nr.rclear Pl"ant,

                                                                        ,IA)tr 1,    1.98rr    -    DEC  31, 30t}5 WI}iD                                                                w:l.lD sPEEi, (ItpHl T}iBEC?ICI{                              0.fr*l.4       i.5-3.4          3.ir*5.4         5.5..7.4          ?.5*12.4 13.:i-18.{                   l-9.5*:4.4       l>=14.5     ?OTAI li                 0. Cti0           ,J. tiall     0.011            0,05:            r) it']    (r     n na.q                 {i . 0,:) 5      0 -,:100     0  .01i0    (i . t4 4 Iii.iE             0 . Cl]O          ir. Ct'tl       c. i)31          {.i nq3          r)    -i
                                                                                                    ^d       0.1rii                 L..U.J'          0 - i!00     O.Ofiil     ,i.413 t{E                0 - r.lC'r        0.0011          *-034            0-   L0rj        0.08t)            ir.u94                 0.00'i           ti,0itc      i-].'i00    0.3fi8 EliE               0 - iic0          0.001'l         *.039            0. L't ?6        0.045             .'r   ._l 1 1

c. ()0,j ri.0ti0 0.,:0ri 0..1?5 E 0-CCtj 0,0Oi.r 0.03? 0.04rj S,0r.0 !-r. {-il.J+ 0.00i1 ri .Ots i.r.t00 0.0'43 ESE 0.0{i0 al , {jilo n i\t? {i.Q23 t).*0! 0.001 {l .000 0. *0ti 0.0{lt} ;}.t)4:

5E 0.0{i0 *. c0t 0.0:6 {-r,Q27 ':). *C5 U. UU.i ri - 000 0. ir0* 0.0CI1] *.064 ssE r'!. siiO i.,. ri00 4.049 r.). ()63 ir.0i5 U.TJI. I rl.00i 0 . i.;Stl 0 . 0ri0 (l . 140 s 0. riOrj U.UUI ,i 0?c

                                                            "             u.l-oL'          ft    l rn        'J . l-: l-            0.0?'"j          0. crii      Ll-*0fi     0.535
     .iSif             0. ilOc           0 ,000          *.0r,3           0.37i            0.594             :.1 . ,'!JU            0,049            ri.0*1       {-.r.ti0t-} i.?7S
     .!w               0 - 0011          0.000           i) .0:9          0.1"46           u. i{i)           i-.;. r.'i*5           0.003            rl .0t0      0.00r)      0.3'tii Fisw               0.0c0             dl. {i00        0.007            {i.$2a           ,-) . {ii  I      C.04,J                 c. rit-) 6     0. ir0{l     0.$fjt)     ,; .09t w                  [].0110           i'.;. ri00      0.00t]           {1.007           0 . 0:'t          0.059                  C. tl0l        0  "

i.rO{l 0 .0rifi 0.108 t{};i,J il . iJC! 0. c0L) * - 0r'14 0. L)llj 0.0i1 ir.064 0.005 0.0,i0 L'}.,i00 c.093 liw 0 - i0rl 0.000 * .0rr4 o.041 0.0i9 i.,. {j52 0.005 rl .0i)0 0. ii00 0.08? t'&\EW 0 - ilO(l 0 .00{-r ii .00? 0.0?i" \,r . u.: a) qi.r.iSl C. C,1: ri.0ii0 ft. C0tl 0. 161" si.iBTOT3,t t't.0rl1 ii.005 a .42f, L .23ii 1".35? 1 ,589 {}.1L9 0 " ii01 0.0'.i0 4. ?:5

    ?OTAL Iii:iI]B.S {iE I.'AIID STAtsIi,I?Y OBSEP.]jATI{]I{,3                                                             LifI63!I rOTA.t I{QT.IRS OT s?ABILTTY C:,ASS E                                                                                     BT'I3'J TI.ITAL IiCURS CF' VS.tITi hII}Iil DIB.$C?ICT{-WI}IN .5PEED-ST&BIIITY i::tAss A                                           ?94i TOTAL I{CLIF.S CF' VALTD WII{D D1RfiCT1,}}T-W1NN SPESD-STABTLTTY OBSERVATIQNS 1('L]I4,1 TOTAL IiCLIF.S   r-'ALM                                                                                                         1 t{[TXOS.iJtCi;ii:AL FACITITY: ]iatt.s Bar l{r.rcl-ear P.Lant STABITITY EASED ON DEI,TA.? BETWEEI{ 9,5J- zu.iD 45.'J3 I,IETEF.S I{II.I-N SPEED AIID DIFiEC?.ICN I.IIIASTJRED A?              9. 7T MT]TER :,EVEI, ttEAlI WIIID SFEED        =   6. ?!

l.iO?E: TL-}TAiS Ai.:D STjBTCTALS AF.{ OBTAINED fH.Cl"{ UI.IROU}IDED NiJI"IEERS

WBN TWO-UNIT OFFSITE DOSE CALCULATION Revision I 0 MANUAL (oDCM) Page 147 of 205 Table7.2 -JOINT PERCENTAGE FREQUENCIES OF WIND DIRECTION AND WIND SPEED FOR DIFFERENT STABILITY CLASSES lPage 2 of 7) S::ABII*ITY CLA;3.1 B I,{etti, Bar $uciear Piant JAli '1, L9*6 - DEC ?1, 2C{i5 ir-I [iD wlND SPEEii (I"IPH) DiFTC?I+N c. ti-l.4 i.5-3.4 3.5-5.4 5"5-7.4 i.5-L?^4 12.5-1s.4 t'i 0.00rj 0 .0oil i-r r1.: -) 0.084 0.005 t.l .0il0 ir . ili0rl 0.318

,)

u. ij..l{?,

tilfE 0.0$r-] 0,s01 s.03? s. iiO9 0.0i10 it.ll0t') 0 .5e3 liE 8.0*0 ,J . *00 c. 3i t'f r-) . ri90 tj . rj'-'! L 0. {tOtl c. ri*i) 'i.39d iliE 0.0rlS i; - rl01 0.058 l-r i-: rl ) rl.0i-.r0 l; - {t0r.,1 0,c00 s.209

      .E                  0.               0. s01           tJ  -ti4b                                0.0ri1                         S.00'J        rJ  ,0,ic     L).:jOrj    0. lfi6 ESE                     'i00

0. ri0'j U.UU/ tJ .{i2{ 0.00t) 0. a)0'-l (J ,0 j;0 L'). r.-100 . t}51

      .SE                 0.0$t.i          0  .00#          * .03?                                   0,    Ci:i5                    0.00i         ti  .0*0      i"l . ii00      .078 sSE                 0.0ii0           ir . tjr,'tC     0. t]5?                                  t). r._10!j                  ti. rir-)0   0. ir0tj      0 . Crji)       . tt)4 5                   r1.0il0          *. ri01        0.{t7i                                                                  tl . r)14     0. i.i0:      0.0riO          .354 SSW                 t]. rj0'j        0  .001          ,i.08:                                   $.:$6                          0. t]:'j      {"i ,0LtO     0. x0$          . t3u sw                  0.,i00           0.00i-l          ,i .03r,                                 ar    a,E.t

0. t')0i 0 ,0iiO 0 .,i00 n .)'? (

I{$if 0. S0rl 0 .Otif; i].0[.t7 0,0.:"5 0. t0i ri . 0r;0 i.r. il*r-] 0.0r]1 w 0.0c0 ir.000 0.006 L). *t5 (l.ri09 0. al0i 0 .O{ii'} ri.

                                                                                                                                                                                  'i9_1" Wiil*i              t'1.0C0          il. r101         0.0rr5                                   ar    l\.r   l
                                                                                                                                    *. L")07    g i.igii
                                                                                                                                                      "         0 .0tj0     \^t.LJl l.iw                0. iic0          0 . c0t')        0 " 0L)7                                 0 .03:1                        c.00u         {,i , c,ic    ,,1 . t;$tj c.135 l.ilii,,            0. ri0'J         C.0{iL)          0   . ritl                               U.U<IU                         0.008         (.i ,0{i0     ,-1.  *00   lJ. L /J SUBTCTiTL 0,0f 0                     ,i. {i07         0.606                   t.383            t) rr^ ?          0^958        *.a83         0.irOi        0 ^ 00r)

TOTAL HCTTF"S CF" VALTD S?AETLITY OBSERVATIO}Is :.?T)C39 TOTAL Hi:iUB.S ,if iiTABILITf i:LA.59 B ir7?l

      ?OTAL iiOrJRS OF 'v?tID WIND DTH.ECTTOI'I-}JI}.iD 5PtrEn-ST.B,tsILI?Y CUa^SS E                                            (;659 T{iTAL HCUP.S OF VALIII }JI}trTi DIB.ECTIOI.{.HI}Til ,$}iEED-ST&BTT,T?Y OB.SEFVA?ICI{3 J"i'a144 T{:ITAL iiCURS CAIM                                                                                                           I ttSTECp,CLCG.iCAt FACIL:?Y: Watts Bar' Nr.rclsar PlanE S?ABIIITY BESEIi OT.I iiflLTA-T EE?WSE}I                    I " 51 At'Iii 45 . 5:l I,IETERS WIND SFEEli At{D DrRE{::?IC}I MSAS{.iR.nti AT                    9 -'l:. r"Ifi?ER. LtrVEL FTEAN    I{i}I[! SPEED    :   5.-98 Ni-lTE:     TC?ALS AED S{-ISTCTALS Ap.E OBT.qINEI)I fR0l"t l}t1F.{:!Ui'I[ifitj              I'JI:,]dBfiB.S

WBN TWO.UNIT OFFSITE DOSE CALCULATION Revision I 0 MANUAL TODCM) Page 148 of 205 Table7.2 - JOINT PERCENTAGE FREQUENCIES OF WIND DIRECTION AND WIND SPEED FOR DIFFERENT STABILITY CLASSES (Page 3 of 7) SSABIL]TY CLASS i:

                                                                                           ?{*tts    Bar" llrrclear Plant.

iAN '1, 19s6

DEC 3'1, 2C{15 wlNO w:I.rD spEEii {t"lP}t)

DIFIECE:ON 0. r'-1.4 i.5*3..1 3.5-5.4 8.5-7.4 "t.5*1?.4 12.5-ld.4 tt 0. S$rj 0 .001- s.060 0.125 ij . 151 0.007 r1.0il0 0. ilOrl 0. 485 NI{E 0.00{.1 0,00i, 0.1t1 0. ?ti9 (j"260 0. frl.3 0.0i10 rt.{jQrl C.Sl? liE ri, CtJ0 0, {i03 c.139 Lt.iL7 0.0?t"'l 0.0rll 0. il0{l 0.00t) ri.55: EIiE 0.000 (, . ti0l 1-.r. fi30 0 .005 tj.0i., I 0. r-J0.j 0 .0ri0 *.2i1 ri 0.00rj 0.005 *"0*0 0.Ori!, '*;. tjt)1 c.000 0.OiiC rl. il06 0. 14it ri{tr 0. 00{j U.UUJ 'i .654 0 .Ori! '.i . rit) i c.00CI 0.ori0 Ll. {i0CI 0.098

0. ilO{.'i /1 A 11r 0.0?1 0.0r:i: 0. {i01 0.000 ri .0i10 0.000 0. 109 3SE 0.000 r't l'ii)a $. i)3d rl.ri09 0.004 ti.oit: 0.0c$ 0.0{it} t. 16i J 0.0{10 fi. ti01 0. 128 t-! r-'lOq 0,04.q {i. L10B 0.i,01 0.0110 0.503 ss9l 0.00{:i 0.001 ri - 15: n ^86 *- 177 0.019' 0 .0r10 rl. rJ00 j.. t):U sw i).000 0.001 0 " fiu0 0.0?!) il . {r1l 0. ilO1 0 ,000 Ll.*00 0.3tj?

T{3Iil 0 " 00tl 0 .00i. S"r")f3 11 l't? i i.,. {jl5 0.00i- rl .000 ii " iti00 0. 1"1? w 0.000 (r.li0l 0. t')t6 L) - j;39 0.042 tl.oLr4 0.,:10{'j 0.0'jt) *.1-:10

    ?fliH                             rl.Oti0          f,. ri00              0.013                            fi  -*4?        n     111           ii.111"0  0"  i,otj  0.0ri0     0.214 l.iw                              0 " ti0rj        0.001)                (i,020                           tJ . uq.]      {.699               0.0ti     ti,o{.lC    t'r.*00   c.!06 tglli,J                           0 . rJ0rj        0.0011                ,J .03:                          0.0{i4          it - t393           C. Llti  ri.0*0      L). {}00  0.:ii4 SLiETOTAI 0.0*0                                    tr.0?3                i.r?1                            f.i30                               *,0'a9    0.  ,t01    0  .0'i0  5.4 7d i(J1JaIr        HCUF.$ CF'          VAIT}    STAE.TLITY QBSSRVATIC}iS                                                                1?0i;-i9 l- (, t- f1.Lr   I{i:itiB.,,-( ,}f' ,$TA-Bii,iTr {l],A.ss c                                                                              9 3*9 TC?AL }iOIJRG                   Qf riAtl i"S: ND Df F.ECT f Ol.i -9If ND S PEED- S?AB 1 I, I ?Y CLjr*cS C                                 92A7 T{]TAt            iiCtlRS CF. III' rilliir DIB.ECTIC}i-?{I}I$ SPE[D*ST&8ItI?Y                             ()BS[F.V"\?rCI{3             i"b8i44 T*TAt iiCURS CAIM                                                                                                                             n I'{ETEOF.OLOGICAI                     rACILI?Y:               I{atts, Ba.r Nucl^ear PlanL S?ABII,ITY ts&SE[i if,N ITEITA-.T BE?WEE]I 9.5i A]Iii 45.ii? ].If,THRS WIND 3PEE[1 EHD DIRE{.:?:C}T MEA5[.:SE[: AT                                     9.i: I.,IETEB. I,EVEL t'1fl41{        I{INti      SPEED       :    5.5?
    !f{.iTE:             TCTALS AND 5I.!3?OTAL.5 AaE OB?AINEII fROFt t}NB.{iUNtiEi) }ltit4iifiF$;

WBN TWO.UNIT OFFSITE DOST CALCULATICIN Revision I 0 MANUAL (oDCM) Page 149 of 205 Table7.2 - JOINT PERCENTAGE FREQUENCIES OF WIND DIRECTION AND WIND SPEED FOR DIFFERENT STABILITY CLASSES (Page 4 of 7) S?ABILITY CLAS.S D {- i .5< DELTA T.'1:..0 .?t ti lil0 S{} Watt; Bar $r-lciear PianL

                                                                               .TAN '1, i985 - DEC 3'L, 2C{-:5
 !{IND                                                                      w:t{D sPEEri {!{?i{)

DiH-EC?ION 0. .-1.4 i.5-3.4 3.5-5.4 5.5-V.4 1.1-t?.4 12.5-18.4 1{i.5-2.{..4 )='i4. 5 TOfAt l-: It 0.006 0.050 ii.656 L , uE.) l -2tt3 0 - il0tl TiNE 0. c06 n nq4 il,697 1. ?tif' l-.18? il . ii0{.) tiE {i . ct}7 it r't AA u . ,,:ir) t)..t?? 0.:ri3 0.0*tl EiiE 0.0t8 ii. rl95 0.$4ij 0.i15 0.03$ 0 .0i0 f,' l'r.0c5 c. i:6 *.4?E tJ.v,ji (t. tjttS

                                                                                                                                                                  ']. ilOrj ESE                 r). tiC3            0.081            al ';;?c                                 0.0'i6            il.0t)4                                  L]. rj0{j

0. i04 fl f).)l"r 0.3h? i-i . ri 14 0. i.l0Ll 5SE 0.01i6 Lt . i'i3 0.5s6 r1.035 U. UJ.I 0. c*0 s t') . Cl1 i.i. i?4 i.l'u+ 0.?9{} n ^q1 0.0riO ssrJ tl. iiiS 0. i45 i . i.i.0 0 .9t7 ir.815 0.,.i00 slI 0 - iJltj u.!ti, 'i 0.:rl! il. fi97 ,:).ij0{j

                                                                 -{i6a I{si{               rr.*06              0, 109           il.5ii3                                  0.123             ii. tSgg                                 0 - il0t) w                   0. cc5              ;r U -:iI 3,!!

u. -lui-\ 0.2513 U..:3t) 0 ^ 0{it) wliri rl.0rl4 i, . il95 n 1<'1 lt .4lt'1 0.520 tl .0ti0 t{}i 0.,i0.I n n-?l ar ?<? 0. 53t (r.603 L).,i00 l.lliw 0 -,.1c4 0.042 ,i.445 0. r,.31" i).?95 r-'t. t;00 SLIBT0TAL 0 . Ltil i_ - 615 i0.5ri6 9r.4f,6 6. r!C5 L.l"tJ 0. ui-*

TOTAL IiCL'IF.S CF' \,TAI,TD STAE.TLITY OBSERVATIO}IS ].TOt;*19 TOTAL I((:X]B.S {iT STABILITT i:L&.Ss D 5$?4ii TOTAL EOT;XS QF l.,?I,ID }JT}.IO DTF,ECTTOI{*'fJTND STEED_STEEILI?Y CIG.SS D 5I325J T{ITAL iiCUP.S CT' V},}]Ti 9TI}Iii DIB.SC?ICTi-WI}Iil SPEf,D*STEBILI?Y '3BSEF.VA9ICT{3 ].b8i44 Ti:'?At HCURS C&tM ll5 I,IETECF.OLCIGI.CAI TACILITY: WaItg Bar Nr-rcLsar Planl STABITITY SASETI {]N TigLTA-T BETWEE}I 9-5i Allir 45,{t3 l,fETEP,s WIND SPtrBiI AJ{D D:RE{::TIO}I MEASt.}REii AT 9.7: !"!ETEB. :'E-\{EL l"!EAl{ I{I}I[} .SPEED = 4.96 ISi:jTE: TOTALS AI'ID :3{.I8f9"1'115 AAE OB?AII{E!i FRC!,! tll'{B.i-rU}Ji.iEI} }rt,},{3ER*c

WBN TITI'O.UNIT OFFSITE DOSE CALCULATION Revision I 0 MANUAL (0DCM) Page 150 of 205 Table 7.2 - JOINT PERCENTAGE FREQUENCIES OF WINO DIRECTION AND WIND SPEED FOR DIFFERENT STABILITY CLASSES (Page 5 of 7) STABIL"ITY CI,ASs E {-T}.5<. DETTA T.i= i.5 Ci 10,il 14}

                                                                               !{atts Bar i.iuclea.r Fiant JAI{ i, l-9t6 -                     DEC  31, :ri05
  ,SI}iD                                                                     l"JilJ[i .sPEg] (F{Fili DlRT]C?ILlN                                t).6-1 ,4          i.5-3.4           r" 5-5.4                    5.5--?.4       ?.5-1:.4 N                                      ij.156              .44{             t',     .ql?               CI.30tj                       0. rr0?        0. iiotl    0.0'.10    1".653
                                            ,'-t : /t')
                                                                .13L             0.331                      l"r ': -i I ii.003         0. i,00      0 .0n0     :..144 NIiE                                  '-, . LaL l.iE                                   0.169               . i;L]          0.3d6                      u. utld                       c.00.,.:       ri ,0!i0     0 - ttoCI  i   ^ :t/q SNE                                   0.140               .813             0.l        -c.i, 11 l\!r.                      0. CIo1"     rl .000      0 . tl0r)   i ,32i U                                     it  -Zi1            .']Iir           ri.040                     0  .,ji.l                     tl .0t"'10     0. Lr0rj     0.0ril)    ri.  {i71" ESE                                   r-i. l-t ,          .118             r1.034                     fi.006                        0.r10i         0 . i,0tl    0.0riCI sI                                    i-i.2{)3            .L49             r.i.04g                    0. {i:5                       ii . rr0?      0 - i.iO{l   0,0tl0     i-i.4!i s5E                                                         ?)l            0.      L)83               0  .051                       c. tl07        {J ,0,J0     0 -..100   u. e;3L 5                                     n     <tQ           .012             t.-tl-.^r                  0.197                         0.04i          r.i.00i        - c00    ?.45,1
      .$st{                                 0, iio4             .464             1.l-78                     0.645                         0.05i          rl .OCS        . tOtl   4 . SrBl" 5W                                    ar.;31                1(11           ti.3*1                     i)   I1t                      0. riL):       0.']Ct_]       . 0!it)  2 . $',Lii w.$li                                 i-, -736            . ?11            {.1  . 147                 0. i)87                       t.r.r0i        0. i,0tl      .0ri0    :,. ivi BI                                    0 .6!ia             .5:rl            0.194                      0.083                         c.00,i         {i ,oric       -,J0rj   i.tri4 I$rt{                                 0.545               .537             u.      .- t).:r           0.099                         0.001-         ri .00C      0. ti0t')   i .641 tiw                                   0.461               .507             0.:79                      0.lr:ig                       u . llu.:      rl.0ci       0.000       i.453 l.Il,i!{                              r-t.255                              $.375                      L) .24?                       *.01't5        0.,:.tC*     0 ^ 0'lt)  "L
                                                                                                                                                                                     .455 SUBTOTAT O.*:]                        n.326                                ,1.8t2                     ?. i3.1                      0.11i          I  .Oi-l:    0-  'i00  23   .1'l'i TCTA.I   I{QTJRS   Of r.te1,l}   S?.FBIT,fTY       {f,BSEF.v'ATIOtl:i                                                         L7{:639 T{:I?AL  HCURS     CE S?ABTLJTY CLAS.$ E                                                                                       44]"30 TOTAL    IiCtrFlS O!' lrAtfD WIND nIRECTILII;-rdII.ID SPEED-STABILiry CTASS E                                                  43343 TOTAT    IiCtrF.S Cr VAlrIr rrirND DIRECTICD;-WIND SPEBD-STABILI?I OBSERYATI*IJS 168144 tcTAL    lii:iuB.s ilA1,l'l                                                                                                     1.390 I.1E?EOROL$GfCA"L fACfLiTY:                   Wartts Bar    l,Juclear Flant
      .TTABIIITY EA,5ED OI'I DilLTA-? BETWtrEI{                   '? . 5:. AttD      4I: .      63  l"ril?EB..S Hi}I[i .TPEED      A}TT) t}IP.fiC?IIiI{ ISASUP.SD A?            ,.12  MTTER IEYEL HEAII WII{D 9PEEli        =   3.1i3 I{OTE:      TOT&-LS   AliD  SUBTI:)TALS AB.il        OBT&IIIED fF.CiH UItrROI!I{D$D 3{UI'!BERI

WBN TWO.UNIT OFFSITE DOSE CALCULATION Revision 1 0 MANUAL {oDCM} Page 151 of 205 Table 7.2 - JOINT PERCENTAGE FREQUENCIES OF WIND DIRECTION AND WIND SPEED FOR DIFFERENT STABILITY CLASSES (Page 6 of 7) sfAaILIlY CLASS r ( 1.5.i DELIA T<= 4.rl C/10n Ui tdatts Bnr Nucle;;ir PlErrt JAN i, l$i:ii .- nBC 31, :ri05 WII'ID wrliD EFEED il"lilH) DI$TE{::T1O}I fi-6-'t.4 i.5-3.4 3.5-5.4 5.5*7.4 f.it*ti.4 1?.5*i3.4 i8.5-14.4 ):24 .I:r Ti-ITAL N r).046 r-t -264 0. tai ri.0ig 0,Ot-ll" i} . t-100 0..i0{l il " 515 l.illE 0.,i38 0. i9i a! I ?4 0. L'tl6 U . l.ir) I 0. t'10,; {J ,0 j;0 0.,139

                                                ,!tQ tiE               0.05ti             n 0-26S              4.029                               ii. r.i1ig             0.00i:,          r]  .0i.;0             0.565 Si.ln             0.064              i
                                                ^';

a, f.343 {}.(t32 i.i. rl0l 0.00ij {l .0{}0 0. ?21-ri.033 ,J.i9? n 'I 1':r {).t)ti5 0^000 0.0,r)0 0.,i0C ,i, 353 ESE tl.0i5 n.l":1 0.0.?? {.1.0iiO 0,0r-10 i. rr00 0. i.ic+ L' " 1r)J s? 0. rii6 0. i1', {l " 03r, 0. r]04 i-t.001 0.00'i {-i .0i;0 0.1?5

     .$SE              ar J1^E ii " 0tl$          0.0iil                              ij. rl{)2               0.00L            ri.0t]0                U.
                                                                                                                                                                                             -fiJ
     .i                0. c5             n     trt                 . z)l)          A.r)32                              ii. {i02                0.00i.i          {j . 0t:i0             0.643 ssw               0.1r13             0.4 59                      \n7           n. 156                              U^UU{                   tl.00C           0.,J$(j                i. tv0 st{               0.13b              0.694                       i,2'l         r.t. u9u                            0.0t--ll-               f1. 0ii0         0. ir0rj               l-.5{i7 t{Sir]            0. 16?             0. r94                    . tiJy          0.,:'l:3                            {}.  {j0l               0. tlO/"j        0 .000                 j-. c. j J tq                t).i83             l.,rtlr                   .52:            t).il:i                             al.0i)l                 0. L'l0il        ri.0{.r0               i. 999 I{isw             lt.L17              I 4?O                    .447            A.it?9                              qi . r.)01              0.00i)           rl .0i10               i   .9:13 liw               0. t?1             1.193                     . 412           0.0ti4                              0   .001                {i.0i}0          0. tr00                i.ri?s Iii,ffi           0.0rr0             r't (1{                   .:)+            0.0:16                              0.001                   ti.000           0. tl0(j               {: - ts'11 SUBTOI'AI         1.;{6'j                                   4.953              U.{olj                              al . {i1$               c. L'l0i       0,0,i0      0.*Ori    i5.I3i Tr'.iTAL IiCIJRS CF V&t]il      .$T;EBILITY qIBSSRVATIO}IS                                                                     l-?1r63 9 TO?AL IiC.UF,S CT S?ABII,:TT CLASS T                                                                                             ?6048 TO?AL I{CLiF.S CT TJALTD !{IND NIREC?IC}I*fl1TqD SPSED-STABTLITY CLASS r                                                         2i',52t tCTAt Hi.XlF.$ *F I;?LIO I{II{D DIRE{:TI$N-WIliD gFEEIi-STABILIT): cBgEp.liaTrclls                                             i68i44 fl'\^r' TOTAI }iOTJRf; CA.LI"I                                                                                                            il,olJ I"1STEOR.OIL'!GfCAI, FACftfTl' :                I{atls Bai t'{uciear Flant
     .iTABTtiTY BA.5ED O}i DELTF.-?                 BETT.IEET{        :?.5i AND 4i:,. .3 t'lflTEB..li WrIID SFEED irll} DIREC?loli I.IEASUFID A?                              9. ?: HgTEFi LEVE],

l,ISAlI WIND 9PEEI = l" - 41 I'.ICTE: TOT&I'5 AND S{,3T.}?.ELS AR,A OETEI}T8D TROM U}TRO{.INDilD T{TI&!BERI"}

l/VBN TWO.UNIT OFFSITE DO$E CALCULATION Revision I 0 MANUAL (oDCM) Page 152 of 205 Table 7.2 - JOINT PERCENTAGE FREQUENCIES oF WIND DIRECTION AND WIND SPEED FOR DIFFERENT STABILITY CLASSES (Page 7 of 7) STABILITY CIA.SS I; ([iEtTA T > 4"ti rj,ii*s H)

                                                                               !{atts Bar }Iuclear Piant iAN "L, i986 -              DEC 3.L, 20{i5 tiitrD                                                                      wI?{D SFEEIi (t"IP}i}

D:FEC?ION 0.i'-1.4 1.5-3..1 3.5-5.4 3.5-1 .4 -i.5-L2.4 12.5-t8-4 ti $.00i 0.Oi:r0 i. ti1i6 0.000 ri .0S0 fr. tOt] 0.323 tii'iE 0. i-r0i 0.0r:i0 ii. rl00 0. 00i) ri.000 0.s00 0.31i.i

     };E                                                                          {3 .0,;:          0. 'i00            0   .00t)           ri.000     !).000      O.CSL)      U..1,11 EIiE                                                                         0.0s4             0.001              0.0trf.r            {i. Lrr.,0 0. ii0tj    0.000       s.55 i r                                                                            0.,:)0U           0.0{itl            ir.0i)0             0 .00rj    {l ,0ri0    L).it0{r    0.it}4 E5E                                                                          0.110*            0 .0*r')           '-t
                                                                                                                           . 0i)0          0.00ii     rl  .0ii0   L).ii0fi    0.15i SE                                                                           0.00tj            0.0ri0             (i. ri00            0.00i)     {l  .0ii0   0.*00       0.1t39 ssE                                                                          tJ . 0,J::"       t) . iicrj        0.00t)              n.000      0. ir00     0 .0{ji'}   ,i. 731" J                                                                            r.i.0il?          0. S0r.'i       0. 0rr0             {1. rli)0  0 . iio*    0.0ri0      0.:135 SS'ttJ                                                                       0. r)$5           0 . c(lL           ir. sil6            c. t'lori  {i . Crio   ,:).ii00    0.556 sw                                                                           0. Ll0?           0.0ti0             it.000              0. t)0{j   tl ,0ri0    ,-).ii00    0.&$9

[!isr{ 0.047 0.0ri0 (i.000 0.00* rl ,0il0 0.*00 i .495 w 0 .0*: L). 'J0{j 0.000 r. c*$ 0.'i0* 0.0*t) i .559 wlili 0.004 0. {l0rl O. gr.r{"1 0.0ir0 0. ii0il 0.0ri0 L.2tt0 l.iw 0. ir02 0.0{iil it. tlttO c. L)Oi.j 0,0,i0 ,:'l.tj00 i.173 I'iliW 0. L)ct 0.0*il tt . tii)6 0. r)0t {.} .O.iC 'J. ti00 0. 536 SUBTCTEL i..'.lirf

                                                               -.Jr*'i

{i . 0-1? r-) . tJOI 0 .00t-) ri,0'ir0 0. *0* 0 .000 l-'i.136 TOTAL IiCLIF.S OT VA-LTD STAETLITY OBSARVATIC}TS i?0839 TOTAI Iii:)t]B.S {:ir STABiLi?y {:LASS G 1?4$4

     ?C?AL }iOTJRS GF      -.-Ii.LID   WI}.i3 BTF*ECTIOI'I_I,,TND SPEED*STAEILI?Y CLASS G                                              1?2ii T[iTAt iiCUR$ CF' V&TITi HI}Jii DIB,EC?ICT{*'II}I[] 5PEED*STISItI?Y OB.SER.VA?IOITS ].bB]"44 T*?At iict,Frs cAtM                                                                                                                1S64 I.{ETEOECLCGICAL      FACILI?Y: 'tfatts Bar Nt:i:}ear Planl 5?ABII,ITY B&SNii i]N IiELTA*T BETWilEI'I 9.5i A}iIi 45.53                                T4ETERS wll{}   SFEEI1 Ar{D }rRE{.:TfO}tr MSASt.iRAii            &?       f .i: l,ltrTER LEVEi, t'tEAl{ I{I}iii  SPEED  :     1.14 N{-ITE: TCTALS AND          :3i.Its1i'C'fAi.5     AF.[ OBtAINEit     FRC&I I-ll-IF.iiU]l[!En ]J$].{BEB.S

Ul'BN TI'UO.UNIT OFFSITE DOSE CALCULATION Revision 1 0 MANUAL {ODCrur} Page 153 of 205 Table 7.3 - ADJUSTED DISPERSION FACTORS $ector xlQtTerrain Adjusted) D/Q(Terrain Adjusted) 1slm3) {ilm2} N 5.12E-06 8.1 3E-09 NNE 6.35E-06 1.23E-08 NE 1.05E-05 1 .10E-08 ENE 1.23E-05 8.77E-09 E 1.37E-05 9.66E-09 ESE 1 .43E-05 1 .16E-08 SE 1.118-05 9.49E-09 ssE 6.048-06 8,21E-09 s 5.338-06 1 .17E-08 ssw 4.148-06 1 .05E-08 SW 4.46E-06 7.34E-09 WSW 5.47E-06 S.37E-09 w 2.11E-06 2.07E-09 WNW 2.49E-06 2.38E-09 NW 2.05E-06 2.138-09 NNW 2.69E-06 3.08E-09 'The Site Specific Tenain Adjustment Factor (TAF) is equal to the ratio of the variable trajectory /Q to the straight-line ;6/Q. See ODCM Section 7.9.41or a full explanation.

WBN TWO.UNIT OFFSITE DOSE CALCULATION Revision 1 0 MANUAL (ODCM) Page 154 of 205 Table 7.4 - DOSE FACTORS FOR SUBMERSION IN NOBLE GASES Submersion dose Air dose mremly per pCilms mradly per r0i/m3 DFsi DFsi DFn, DFoi Kr-83m 7.56E-02 1.93E+01 2.88E+0e Kr-85m 1 .178+03 'l .46E+03 1.23E+03 1.97E+03 Kr-85 1.61E+01 1.34E+03 1.72E+01 1.95E+03 Kr-87 5.928+03 9.73E+03 6.1 7E+03 1.03E+04 Kr-88 1.478+A4 2.378+03 1.52t+44 2.93E+03 Kr-89 1.66E+04 1.01E+04 1.73E+04 1.06E+04 Kr-90 1.5SE+04 7.29E+03 1,63E+04 7^83E+03 Xe-131m 9.15E+01 4.768+42 1.S6E+02 1.11E+03 Xe-133m 2.51E+02 9.94E+02 3.27E+02 1,48E+03 Xe-133 2.94E+A2 3.06E+02 3.53E+02 1.05E+03 Xe-135m 3.12E+03 7.11E+02 3.368+S3 7.39E+02 Xe-135 1 .81E+03 1.86E+03 1.92E+03 2"46E+03 Xe- 137 1.42E+03 1.228+04 1.51 E+03 1,27E+04 Xe-138 8.83E+03 4.11f+03 9.21E+03 4.75E+03 Ar-41 g.94f +03 2,69E+03 9.30E+03 3.288+03

Reference:

Regulatory Guide 1.109, Table B-1 {Reference 4}.

WBN TWO-UNIT OFFSITE DOSE CALCULATION Revision I 0 MANUAL {OBCM} Page 155 of 205 Table 7.5 - SECTOR ELEMENTS CONSIDEREO 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

WBN TWO.UNIT OFFSITE DOSE CALCULATION Revision I 0 MANUAL (ODCM) Page 156 of 205 Table 7.6 - POpULATION WITHIN EACH SECTOR ELEMENT Distance from $ite {miles) RadiilDistances {mi} Sectors 0-1 1-2 2-3 3-4 4-5 5-10 10-20 20-30 3040 40-50 N 0 18 00 135 24A5 1885 2778 4798 6172 NNE 00 18 411 185 1 536 11762 187S6 14502 2547 NE 00 18 308 287 827 3783 16734 29838 78334 ENT 00 18 308 287 497 3553 29539 $37s8 253831 H 08 431 308 616 552 11352 18647 300s3 44013 ESE 00 027 41 68 6230 2A120 5068 3280 SE 80 029 ?o vv 135 19852 15185 3950 7822 SSE 21 0 0 246 413 103 8951 129A7 2918 48593 S 16 0 00 1 983 3824 4586 42883 56430 17985 SSW 00 21 0 0 546 5725 42517 46281 106392 SW 00 00 0 1 051 12978 14499 623A7 111795 WSW 06 36 59 126 711 12791 2837 2840 3372 W 014 22 101 90 714 3406 5555 2944 M74 WNW 00 22 126 79 490 2091 4372 5654 24il1 NW 0 108 332 376 526 2655 2889 18634 10462 15956 NNW 00 0 'l 73 123 31 16 1536 33843 1 1609 5890 Total 45 155 919 2471 4930 19287 1 13368 299818 353432 728968

WBN TVI'O.UNIT OFFSITE DO$E CALCULATION Revision I 0 MANUAL (ODCM) Page 167 of 205 Table 7.7 - INHALATION DOSE FACTORS - DFiro (mrem/pCi inhaled) (Page 1 of 8) ADULT Nuclide bone liver total body thyroid kidney lung GI.LLI H-3 1 .58E-07 1.588-07 1.58E-07 1 .58E-07 1.58E-07 1.58E-07 1.588-07 c-14 2.27E-06 4.26F.A7 4"26F.07 4.26E-07 4.26E-07 4.26E-07 4.268-07 Na-24 1.28E-06 1.288-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 1.28E-06 P-32 1.658-04 9.64E-0S 6^26E-06 0,00E+00 0,00E+00 0,00E+00 1.08H-05 Cr-51 0.00E+00 0.00E+00 1,25E-08 7.44=-09 2.85E-09 1.80E-06 4.15H-07 Mn-54 0.00E+00 4.95E-06 7 "87F.07 0.00E+00 1,23E-06 1,75E-04 9.S7H-06 Mn-56 0.00E+00 ,558-10 1 ?,2SE-11 0.00E+00 1.63E-10 1.18E-S6 2.538-SS Fe-55 3.07E-06 2.12E-0S 4.93H-07 0.00E+00 0,00E+00 9.01E-06 7.548-07 Fe-59 1.47E-06 3.47E-06 1,32E-06 0.00E+00 0.00E+00 1.278-04 2.35H-05 Co-57 0.00E+00 8.65E-08 8.39E-08 0.00E+00 0.00E+00 4.62E-05 3.938-00 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 1.448-0S 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 NL65 1 .92E-10 2.62E-1 1 1.148-1 1 0.00E+00 0.00E+00 7.00E-07 1.54E-06 Cu-64 0.00E+00 1.83E-10 7.698-1 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 4.238-12 8.148-12 5.65E-13 g.ggf+00 5.27E-12 1 .'l5E-07 2.04E-09 Zn-69m 1.02E-09 2.458-09 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 3.01E-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-13 Br-85 0.00E+00 0.00E+00 1.608-09 0.00E+00 0,00E+00 0.00E+00 0.008+00 Rb-86 0.00E+00 1.698-05 7.378-06 0.00E+00 0.00E+00 0.00E+00 2.088-06 Rb-88 0.00E+00 4.848-08 2"418-08 0.00E+00 0.00E+00 0.00E+00 4.18E-19 Rb-89 0.00E+00 3.208-08 2.128-08 0.00E+00 0.00E+00 0.00E+00 1 .1SE-21 Sr-89 3.80E-05 0.00E+00 1^098-06 0.00E+00 0,00E+00 1.75E-04 4.37H-05 Sr-90 1.24F.A2 0.00E+00 7.62F-A4 0.00E+00 0.00E+00 1.20E-03 9.028-05 Sr-91 7.74i.-Ag 0.00E+00 3.13E-1 0 0.00E+00 0.00E+00 4.56E-06 2.39E-05 Sr-92 8.438-10 0.00E+00 3.S4E-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 2.128-05 s.32E-05 Y-91m 3.268-1 1 0.00E+00 1.278-12 0.00E+00 0.00E+00 2.448-07 1 .6SE-10 Y-91 5.788-05 0.00E+00 1.55E-06 0.00E+00 0.00E+00 2.13E-04 4.818-05 Y-92 1.29E-09 0.00E+00 3.778-11 0.00E+00 0.00E+00 1.96E-06 9.19E-06 Y-93 1 .18E-08 0.008+00 3.268-10 0.00E+00 0.00E+00 6.06E-06 5.278-05 Zr-95 1.34E-05 4.30E-06 2.91E-06 0.00E+00 6.77E-06 2.21E-04 1.888-05 Zr-97 1.218-08 2.45E-09 1 .138-09 0.00E+00 3.71E-09 9.84E-06 6.54E-05 Nb-95 1.76E-06 9.778-A7 5.268-07 0.00E+00 9.67E-07 6.31 E-05 1.30E-05 Nb-97 2.788-11 7.03E-12 2.568-12 0.00E+00 8.18E-12 3.00E-07 3.028-08 Mo-99 0.00E+00 .51E-08 1 2.87E-09 0.00E+00 3.64E-08 1.14E-05 3.108-05 Tc-99m .29E-13 3.648-13 1 4.63E-12 0.00E+00 5.528-12 9.55E-08 5.208-07 Tc-101 5.228-15 7.528-15 7.38E-14 0.00E+00 1.35E-13 4.99E-08 1.36E-21 Ru-103 1.91E-07 0.00E+00 8.238-08 0.00E+00 7.29F-07 6.31E-05 1.388-05 Ru-105 9.88E-1 1 0.00E+00 3.89E-11 0.00E+00 1.278-1A 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

WBN TWO.UNIT OFFSITE DOSE CALCULATION Revision I 0 MANUAL (ODCM) Page 158 of 205 Table 7.7 - INHALATION DOSE FACTORS - DFi"o (mrem/pCi inhaled) (Page 2 of 8) ADULT Nuclide bone liver total body 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-12s 6.67E-06 7.44E.Og 1.58E-06 6.75E-09 0.00E+00 2.18E-04 1.26E-05 Sn-125 1.'t6E-06 3.12E-08 7.03E-08 2.59E-08 0.00E+00 7.37E-05 6.81E-05 Te-125m 4.27E-07 't.98E-07 5.84E-08 1.31E-07 1.55E-06 3.92E-05 8.83E-06 Te-127m 1.58E-06 7.21847 1.96E-07 4.'l1E-07 5.72E-06 1.zOE-04. 1.87E-05 Te-127 1.75E-10 8.03E-11 3.87E-11 1.32E-10 6.37E-10 8j4E-07 7.178-06 Te-129m 1.22E{,6 5.84E-07 't.98E-07 4.30E-07 4.57E-06 1.45E-04 4.79E-05 Te-129 6.228-12 2.998-12 1.55E-12 4.87E-12 2.34E-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.ME:13 4.49E-13 1.178-12 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 5.72E-07 1.68E-06 6.60E-07 1.42E-04 2.61E-06 0.00E+00 9.61E-07 l-131 3.15E-06 4.47E46 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 l-134 8.05E-08 2.16E-07 7.69E-08 3.73E-06 3.44E-07 0.00E+00 1.26E-10 l-135 3.35E-07 8.73E-07 3.2'lE-OT 5.60E-05 1.39E-06 0.00E+00 6.56E-07 Cs-134 4.66E-05't.06E-04 9.10E-05 0.00E+00 3.59E-05 1.228-05 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.'l4E-08 7.76E-08 4.05E-08 0.00E+00 6.00E-08 6.07E-09 2.33E-13 Ba-139 1.17E-10 A32E-14 3.42E-12 0.00E+00 7.788-14 4.70E-OT 1.12E-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 1.258-11 9.41E-15 4.208-13 0.00E+00 8.75E-15 2.42E-07 1.458-17 Ba-142 3.29E-'12 3.38E-15 2.078-'13 0.00E+00 2.86E-15 1.49E-07 1.96E-26 La-140 4.30E-08 2.17E-OA 5.73E-09 0.00E+00 0.00E+00 1.70E-05 5.73E-05 La-142 f.ilE-11 3.88E-11 9.65E-12 0.00E+00 0.00E+00 7.91E-O7 2.6/rE-OT 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 1.72EqA't.91E-09 0.00E+00 7.60E-09 9.97E-06 2.83E-05 Ce-144 4.29E-M 1.79E44 2.30E-05 0.00E+00 1.06E-M 9.72E-M 1.O?E-CA 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 1.278-07 2.69E-18 Nd-147 6.59E-07 7.628-07 4.56E-08 0.00E+00 4.458-07 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 Np239 2.87E-OB 2.82E-09 1.55E-09 0.00E+00 8.75E-09 4.70E-06 1.49E-05

Reference:

Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sb-124, Sb-125, Sn-125 are ftom Reference '17, Table 8. All others 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).

Ul'BN TWO.UNIT OFFSITE DOSE CALCULATION Revision I 0 MANUAL (ODCM) Page 159 of 205 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-CI6 1.728-46 1.728-46 1.72E-06 1.72E-06 P-32 2.36E-04 1.37E-05 8.95E-06 0.00E+00 0.00E+00 0.00E+00 1 .16E-05 Cr-51 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 2.48r.A4 8.35E-0S Mn-56 0.00E+00 2.12C.-1A 3.15E-11 0.00E+00 2.248-10 1.90E-06 7.18E-0S Fe-55 4.'l8E-06 2.988-06 6.938-07 0.00E+00 0.00E+00 1.s5E-05 7.99E-07 Fe-59 1.99E-06 4.62E-06 1.79E-06 0.00E+00 0.00E+00 1.91E-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 3.47F-07 0.00E+00 0.00E+00 1.68E-04 1 .19E-05 Co-60 0.00E+00 1.89E-06 2.488_06 0.00E+00 g.ggf+00 1.09E-03 3.24E-05 Ni-63 7.25E.45 5.43E-06 2.47F-06 0.00E+00 0.00E+00 3.84E-05 1.77E-06 Ni-65 2.73r-10 3.66E-1 1 1.598-11 0.00E+00 0.00E+00 1.17E-06 4.59E-06 Cu-64 0.00E+00 2.548-10 1 .068-10 0.00E+00 8.01 E-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 5.83E-06 Zn-69 6.04E-12 .15E-11 1 8.07E-13 0.00E+00 7.538-12 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+00 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 0.008+00 0.00E+00 5.41E-08 0.00E+00 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+00 0.00E+00 0.00H+00 Rb-86 0.00E+00 2.38E-05 1.05E-05 0.00E+00 0.00E+00 0.00E+00 2.21E-06 Rb-88 0.00E+00 6.82f-08 3,40E-08 0.00E+00 0.00E+00 0.00E+00 3.658-15 Rb-89 0.00E+00 4.40E-08 2,91E-08 0.00E+00 0.00E+00 0.00E+00 4.22F-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-9'l 'l .108-08 0.008+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 0.008+00 1.00E-08 0.00E+00 0.00E+00 3.66E-05 6.99E-S5 Y-91m 4.63E-1 1 0.00E+00 1.778-12 0.00E+00 0.00E+00 4.00E-07 3.778-S9 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-11 0.00E+00 0.00E+00 3.35E-06 2.06H-05 Y-93 1,69E-08 0.008+00 4.65E-10 0.00E+00 0.00E+00 1.04E-05 7.24F-45 Zr-95 1.82E-05 5.738-06 3.94E-06 0.00E+00 8.42E-06 3.36E-04 1.868-05 Zr-97 1.72E-08 3.408-09 1 .57E-09 0.00E+00 5.15E-09 1.62E-05 7,88E-05 Nb-95 2.32E-06 1.298-06 7.AAE-07 0.00E+00 1.25E-06 9.39E-05 1.21E-05 Nb-97 3.92E-1 1 9.728-12 3.55E-12 0.008+00 1 .148-11 4.91 E-07 2,71E-07 Mo-99 0.00E+00 2.11E-08 4.038-09 0.00E+00 5.14E-08 1.92E-05 3.36E-05 Tc-99m .73E-13 4.83E-13 1 6.24F-12 0.00E+00 7.208-12 1.448-07 7.66E-07 Tc-1 01 7.40E-15 .05E-14 1 1 .038-13 0.00E+00 1 .90E-13 8.34E-08 1 .09E-16 Ru-103 2.638-07 0.00E+00 1.12E-A7 0.00E+00 9.29E-07 9.79E-05 1.36E-05 Ru-105 .40E-10 0.00E+00 1 5.42F-11 0.00E+00 1.76E-10 2.27F-46 1 .13E-05 Ru-106 .23E-05 0.00E+00 1 1.558-06 0.00E+00 2.38E-05 2.41 E-03 1.20E-04

WBN TWO.UNIT OFFSITE DOSE CALCULATION Revision I 0 MANUAL (ODCM) Page 160 of 205 Table 7.7 - INHALATION DOSE FACTORS - DFt* (mrem/pCi inhaled) (Page 4 of 8) TEEN Nuclide bone liver total body thyroid kidney lung Gl-LLl Ag-110m 1.73E-06 1.64E-06 9.99E-07 0.00E+00 3.13E-06 8.44E-04 3.41E-05 Sb-124 s.38E-06 9.92E-08 2.10E-06 1.22E-08 0.00E+00 4.81E-04 4.98E-05 Sb-125 9.23E-06 1.01=-OT 2.15E-06 8.80E-09 0.00E+00 3.42E-04 1.24E-05 Sn-125 1.66E-06 4.42E-Og 9.99E-08 3.45E-08 0.00E+00 1.26E-M 7.29E-05 Te-125m 6.10E-07 2.808-07 8.34E-08 1.75847 0.00E+00 6.70E-05 9.38E-06 fe-127m 2.25E-06 '1.02E-06 2.738-07 5.48E-07 8.17E-06 2.078-0/ '1.99E-05 Te-127 2.51E-1A 1 14E-1O 5.52E-1 I 1 .77E-10 9.1OE-l0 1 .40E-06 1 .01 E-05 Te-129m 1.74E-06 8.23E-07 2.81E-07 5.72E-o7 6.49E-06 2.478-A4 5.06E-05 Te-129 8.87E-12 4.22E-12 2.20E:12 6.48E-12 3.32E-11 4.12E-OT 2.02E-07 Te-131m 1.23E-08 7.51E-09 5.03E-09 9.05E-09 5.49E-08 2.97E-05 7.76E-05 Te-131 1.97E-12 1.04E-12 6.30E-13 1.55E-12 7.72F.12 2.92E-OT 1.89E-09 Te-132 4.50E-08 3.63E-08 2.74E-Og 3.07E-08 2.448-07 5.61E-05 5.79E-05 l-'130 7.80E-07 2.24E-O6 8.96E-07 1.86E-04 3.44E-06 0.00E+00 1.14E-06 l-131 4.43E-06 6.14E-06 3.30E-06 1.83E-03 1.05E-05 0.00E+00 8.11E-07 l-132 1.99E-07 5.47E-07 1.97E-O7 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-1U 1.1'lE-OT 2.90E-O7 1,05E-07 4.94E-06 4.58E-07 0.00E+00 2.55E-09 l-135 4.62E-07 1.'t8E-06 4.36E-07 7.76E-05 1.86E-06 0.00E+00 8.69E-07 Cs-134 6.28E-05 1.41E-04 6.86E-05 0.00E+00 4.69E-05 1.83E-05 1.22E-A6 Cs-136 6.44E-06 2.42E-AS 1.71E-05 0.00E+00 1.38E-05 2.22E-OO 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-08'1.07F.07 5.58E-08 0.00E+00 8.28E-08 9.84E-09 3.38E-1'l Ba-139 1.67E-10'1.18E-13 4.478-12 0.00E+00 1.11E-l3 8.08E-07 8.06E-07 Ba-140 6.84E-06 8.38E-09 4.40E-07 0.00E+00 2.85E-09 2.548-04 2.86E-05 Ba-14'l 1.78E-11 1.328-14 5.93E-13 0.00E+00 1.23E-14 4.11E-O7 9.33E-14 Ba-142 4.628-12 4.63E-15 2.8/E-13 0.00E+00 3.92E-15 2.398-07 5.99E-20 La-140 5.99E-08 2.95E-08 7.82E-09 0.00E+00 0.00E+00 2.6SE-05 6.09E-05 La-142 1.20E-10 5.31E-11 1.32E-11 0.00E+00 0.00E+00 1.27E-06 1.50E-06 Ce-141 3.55E-06 2.378-05 2.718-07 0.00E+00 1.11E-06 7.67E-05 1.58E-05 Ce"l43 3.32E-08 2-42E48 2.70E-09 0.00E+00 1.08E-08 1.63E-05 3.19E-05 Ce-144 6.11E-04 2.53E-U 3.28E-05 0.00E+00 1.51E-04 1.67E-03 1.08E-04 Pr-143 1.67E-06 6.ME-07 8.28E-08 0.00E+00 3.86E-07 6.04E-05 2.67E-05 Pr-144 5.37E-12 2.2OE-12 2.72E-13 0.00E+00 1.26F-12 2198-07 2.94E-14 Nd-147 9.83E-07 1.07E-06 6.41E-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, Zn-69m, Br-82, Nb-97, Sb-124, Sb-125, Sn-125 are from Reference 17, Table 7. All others 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).

WBN TWO.UNIT OFFSITE DOSE CALCULATION Revision I 0 MANUAL TODCM) Page 161 of 205 Table 7.7 - INHALATION DOSE FACTORS - DFi"o (mrem/pCi inhaled) (Page 5 of 8) CHILD Nuclide bone liver tolal body thyroid kidney Iung GI-LLI H-3 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.04E-07 3.048-07 3.048-07 c-14 9.70E-06 1.82E-06 1.828-06 1.82E-06 1.82E-06 1.82E-06 1.828-06 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-S1 0.00E+00 0.00E+00 4.178-08 2.31 E-08 6.57E-09 4.59E-0S 2.93E-07 Mn-54 0.00E+00 1.16E-05 2.578-CIS 0.00E+00 2.71E-06 4.26E-04 s.198-06 Mn-56 0.00E+00 4.48E-10 8.43E-11 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 4.51 E-0S g.6gf+00 0.00E+00 3.43E-04 1 .91 E-05 Co-57 0.00E+00 2.44F.07 2.88E-07 0.00E+00 0.00E+00 1.37E-04 3.58E-06 Co-58 0.00E+00 4.79F.AT 8.558-07 0.00E+00 0.00E+00 2.99E-04 9.29E-0S Co-60 0.00E+00 3.558-06 6.128-06 0.00E+00 0.00E+00 1.91E-03 2.60E-05 Ni-63 2.228-44 1.25E-05 7.56E-06 0.00E+00 0.00E+00 7.43E-05 1.71E-06 Ni-65 8.08E-10 7.998-1 1 4.448-11 0.00E+00 0.00E+00 2.21 E-06 2,278-A5 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 3.068-05 1.908-05 0.00E+00 1.93E-05 2.69E-04 4.418-06 Zn-69 1.81E-1 1 2,618-1 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 8.598-10 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 0.008+00 1.28E-AT 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Br-84 0.00E+00 0.00E+00 1.488-07 0.00E+00 0.00E+00 0.00E+00 0.008+00 Br-85 0.00E+00 0.00E+00 6.848-09 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Rb-86 0.00E+00 5.36E-05 3.098-05 0.00E+00 0"00E+00 0.00E+00 2.16E-06 Rb-88 0.00E+00 1.52F-47 S.908-08 0.00E+00 0"00E+00 0.00E+00 4,66E-09 Rb-89 0.00E+00 9.338-08 7.838-0S 0"00E+00 0"00E+00 0.00E+00 5.11E-10 Sr-89 1.628-A4 0.00E+00 4.668-0S 0.00E+00 0.00E+00 5.83E-04 4,52E-05 Sr-90 2.73e,-AZ g,ggf+00 1.74E-03 0.00E+00 0.00E+00 3.99E-03 9.28E-05 Sr-91 3,28E-08 0.008+00 1.24E-09 0.00E+00 0.00E+00 1.44E-05 4.70E-05 Sr-92 3,54E-09 0.00E+00 1.42F-1A 0.00E+00 0.00E+00 6.49E-06 6.558-05 Y-90 1,11E-06 0.00E+00 2,99E-08 0^00E+00 0.00E+00 7.07E-05 7.24E-S5 Y-91m 1 .37E-10 0.00E+00 4.988-12 0.00E+00 0.00E+00 7.60E-07 4.64E-07 Y-91 2.41'.44 g.ggf+00 6.59E-06 0.00E+00 0.00E+00 7.10E-04 4.978-05 Y-92 5.50E-09 0.00E+00 1.578-10 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 2.41 E-05 1.05E-04 Zr-95 5.13E-05 1.13E-05 1.00E-05 0.00E+00 1.61E-05 6.03E-04 1.658-05 Zr-97 5.07E-09 7.34E-09 4.32E-09 0.00E+00 1.05E-08 3.06E-05 9.498-05 Nb-95 6.35E-06 2.49E-06 1.77E-06 0.00E+00 2.33E-06 1.66E-04 1.00H-05 Nb-97 1 .16E-10 2.08E-1 1 9.74E-12 0.00E+00 2.31E-1 1 9.23E-07 7.52E-06 Mo-99 0.00E+00 4.66E-08 1.158-08 0.00E+00 1.06E-07 3.66E-05 3.42E-05 Tc-99m 4.81 E-13 9.41 E-13 1.568-11 0.00E+00 1.37E-11 2.57F.47 1.30E-06 Tc-1 01 2.198-14 2.30E-14 2.91 E-13 0.00E+00 3.92E-13 1.58E-07 4.41E-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-10 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

WBN TI'IIO.UNIT OFFSITE DOSE CALCULATION Revision I 0 MANUAL (ODCM) Page 162 of 205 Table 7.7 - INHALATION DOSE FACTORS - DFto (mrem/pCi inhaled) (Page 6 of 8) CHILD Nuclide hone liver total body thyroid kidney lung Gl-LLl Ag-110m 4.56E-06 3.08E-06 2.478-AO 0.00E+00 5.74E-06 1.48E-03 2.71E-O5 Sb-124 1.55E-05 2.00E-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-O7 1.03E-07 0.00E+00 2.43E-U 7.17E-05 Te-125m 1.82E-06 6.29E-07 2.47E-AT 5.20E-OT 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 2.718-06 1.52E-05 Te-129m 5.19E-06 1.85E-06 8.22E-O7 1.71E-06 1.36E-05 4.768-C4 4.91E-05 Te-129 2.64E-'11 9.458-12 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 1.788-12 4.59E-12 1.59E-1'l 5.55E-07 3.60E-07 Te-132 1.30E-07 7.36E-08 7.12E-OA 8.58E-08 4.798-07 1.02E-04 3.72E-05 f-130 2.21E-06 4.43E-06 2.28E-06 4.99E-04 6.61E-06 0.00E+00 1.38E-06 l-131 1.30E-05 1.30E-05 7.37E-oO 4.39E-03 2.13E-05 0.00E+00 7.68E-07 l-132 5.72E-07 1.'l0E-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 3.178-07 5.84E-07 2.69E-07 1.37E-05 8.92E-A7 0.00E+00 2.588-07 l-'135 1.33E-06 2.36E-06 1j2E-ao 2.14E44 3.62E-06 0.00E+00 1.20E-06 Cs-134 116E-C4 2.748-0l. 6.07E-05 0.00E+00 8.93E-05 3.27E-05 1.ME-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-U 3.47E-05 0.00E+00 7.63E-05 2.81E-05 9.78E-07 Cs-138 1.71E-07 2.278-07 1.50E-07 0.00E+00 1.68E-07 1.84E-08 7.29E-08 Ba-139 4.98E-10 2.668-13 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 4.71E-U 2.75E-05 Ba-141 5.29E-11 2.95E-14 1.728-12 0.00E+00 2.56E-14 7.89E-07 7.448-08 Ba-142 1.35E-11 9.73E-15 7.il8-13 0.00E+00 7.87E-15 4.44E-07 7.41E-10 La-140 1.748-07 6.08E-08 2.04E-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 7.778-Og 0.00E+00 2.26E-OO 3.12E-05 3.44E-05 Ce-144 1.83E-03 5.72E-04 9.77E-oS 0.00E+00 3.'t7E-04 3.23E-03 1.05E-04 Pr-143 4.99E-06 1.50E-06 2.478-07 0.00E+00 8.1'tE-07 1.17E-04 2.63E-05 Pr-'144 1.61E-'t1 4.99E-12 8.10E-13 0.00E+00 2.64E-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_.t87 4.41E_09 2.61E_09 1.17E-09 0.00E+00 g.gQf+0o 1.11E-05 2.46E-0S Np-239 1.26E-07 9.04E-09 6.35E-09 0.00E+00 2.63E-08 1.s7E-05 1.73E-05

Reference:

Dose Factors for Ce.57, Zn-69m, Br-82, Nb-97, Sb-124, Sb-125, Sn-125 are from Reference 17, Table 6. All others from: Regulatory Guide 1.'t09, Table E-9. NOTE: The tdtium dose factor for bone is assumed to be equal to ihe total body dose factor. This assumes that tritium will act similarly in all organs (Reference 24).

WBN TWO.UNIT OFFSITE DOSE CALCULATION Revision I 0 MANUAL {0DCM) Page 163 of 205 Table 7.7 - INHALATION DO$H FACTORS - D4"o (mrem/pCi inhaled) (Page 7 of B) INFANT Nuclide bone liver total body thyroid kidney Iung GI.LLI H-3 4.62C,-A7 4.628-47 4.62E-07 4.62E-07 4.62E-A7 4.628-07 4.62E-47 c-14 1.89=-05 3.79=-06 3,79E-06 3.79E-06 3.79E-06 3.79E-06 3.79E-06 Na-24 7.54E-05 7.54E-05 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+00 0.00E+00 0.00E+00 1 .15E-05 Cr-51 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-00 0.00E+00 3.56E-06 7.148-04 5.04E-06 Mn-56 0.00E+00 1 .108-09 1 .58E-10 0.00E+00 7.86E-10 8.95E-06 5.128-05 Fe-55 1.41E-05 8.39E-06 2.38E-06 0.00E+00 0.00E+00 6.21 E-05 7.828-47 Fe-59 9.69E-06 1,688-05 6.77E-06 0.00E+00 0.00E+00 7.25E-44 1.77F.05 Co-57 0.00E+00 4.65E-07 4.58E-07 g.ggf+00 0.00E+00 2.718-04 3.47E-0S Co-58 0.00E+00 8.71 E-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 3.228-03 2.28E-05 Ni-63 2.42r-A4 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 Cu-M 0.008+00 1 .34E-09 5.53E-10 0.00E+00 2.84E-09 6.64E-06 1.07E-05 Zn-65 1.388-05 4,47E-05 2.22E-05 0.00E+00 2.32E-05 4.S2E-04 3.67E-05 Zn-69 3.858-1 1 6.918-1 1 5.13E-12 0.00E+00 2.87F-11 1.058-06 9.44E-06 Zn-69m 8,98E-09 1.84E-08 1.67 E-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+00 0.00E+00 0.00E+00 Br-83 0.00E+00 0,00E+00 2.728-a7 0.00E+00 0.008+00 0.00E+00 0,00E+00 Br-84 0.00E+00 0.00E+00 2.86E-07 0.008+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 g.ggf +00 Rb-86 0.00E+00 1.36E-04 6.30E-05 0.008+00 0.00E+00 0.00E+00 2.17E-06 Rb-88 0.00E+00 3"988-07 2.05E-07 0.00E+00 0.00E+00 0^00E+00 2.428-47 Rb-89 0.00E+00 2,298-47 1.47F-Q7 0.00E+00 0.00E+00 0.00E+00 4,87E-08 Sr-89 2.848-A4 0.00E+00 8,158-06 0.00E+00 0.00E+00 1.45E-03 4.57E-05 $r-90 2.928-A2 0.00E+00 1.85E-03 0.00E+00 0.00E+00 8.03E-03 9.36H-05 Sr-91 6.83E-08 0.00E+00 2.478-09 0.00E+00 0.00E+00 3.76E-05 5.248-05 Sr-92 7.50E-09 0.00E+00 2.79E-10 0.00E+00 0"00E+00 1.70E-05 1.00H-04 Y-90 2.35E-06 0.00f;+00 6.308-08 0.00E+00 0.00E+00 1.928-04 7.43E-05 Y-91m 2.918-10 0.008+00 9.90E-12 0.00E+00 0.00E+00 1.99E-06 1.68E-06 Y-91 4.2AF-A4 0.008+00 1.12E-05 0.00E+00 0.00E+00 1.75E-03 5.02E-05 Y-92 1.17E-09 0.008+00 3.29E-10 0.00E+00 0^00E+00 1.75E-05 9.04E-05 Y-93 1.078-07 0.008+00 2,91E-09 0.00E+00 0.00E+00 5.468-05 1 .19E-04 Zr-95 8"248-05 1.99E-05 1.45E-05 0.00E+00 2^228-05 1.25E-03 1.55E-05 Zr-97 1.07f-07 1 .83E-08 8.36E-09 0.00E+00 1.858-08 7.888-05 1.00E-04 Nb-95 t .128-05 4.59E-06 2.70E-06 0.00E+00 3.378-06 3.42E-04 9.05E-06 Nb-97 2.448-1A 5.21E-1 1 1.88E-11 0.00E+00 4.078-1 1 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-13 2.06E-12 2.66E-11 0.00E+00 2.228-11 5.79E-07 1.45E-06 Tc-1 01 4.65E-14 5.88E-14 5.80E-13 0.00E+00 6.99E-13 4.178-07 6.03E-07 Ru-103 1 .44E-06 0.00E+00 4.85E-07 0.00E+00 3.03E-06 3.94E-04 1 .15E-05 Ru-105 8.74E-10 0.00E+00 2.93E-10 0.00E+00 6.428-1A 1.12E-05 3.46E-05 Ru-106 6.20E-05 0.00E+00 7.778-A6 0.00E+00 7.61E-05 8.26E-03 137E-04

lrllBN TWO.UNIT OFFSITE DOSE CALCULATION Revision I 0 MANUAL (CIDCM) Page 164 of 205 Table 7.7 - INHALATION DOSE FACTORS - ffi"o (mrem/pCi inhaled) (page 8 of 8) INFANT Nuclide bone liver total body thyroid kidney lung Gl-LLl Ag-110m 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 1.01E-05 2.51E-07 6.00E-07 2.47E-07 0.00E+00 6.43E-04 7.26E-05 Te-125m 3.40E-06 1.42E-O6 4.708-07 1.16E-06 0.00E+00 3.19E-04 9.22E-06 T*127m 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 1.748-05 Te-129m 1.01E-05 4.35E-06 1.59E-06 3.91E-06 2.278-AS 1.20E-03 4.93E-05 Te-129 5.638-11 2.48E-11 1.34E-1 1 4.828-11 1.25E-10 2.14E-06 1.88E-05 Te-131m 7.62E-08 3.93E-08 2.59E-08 6.388-08 1.89E-07 1.42E-44 8.51E-05 Te-131 1.248-11 5.878-12 3.578-12 1.13E-11 2.85E-11 1.47E-06 5.87E-06 T*132 2.66E-07 1.69E-07 1.268-07 1.99E47 7.39E-07 2.43E-04 3.1sE-05 t-130 4.54E-06 9.91E-06 3.98E-06 1.14E-03 1.09E-05 0.00E+00 1.42E-06 l-13'l 2.71E-05 3.17E-05 1.40E-05 1.06E-02 3.70E-05 0.00E+00 7.56E-07 l-'132 1.21E-06 2.53E-06 8.99E-07 1.21E-04 2.82E-OO 0.00E+00 1.36E-06 l-133 9.46E-06 1.37E-05 4.00E-06 2.54E-03 1.60E-05 0.00E+00 1.54E-06 l-134 6.58E-07 1.34E-06 4.75E-07 3.18E-05 1.49E-06 0.00E+00 9.21E-oT l-135 2.76E-06 5.43E-06 1.98E-06 4.97E-04 6.05E-06 0.00E+00't.31E-06 Cs-134 2.43E-04 5.02E44 5.32E-05 0.00E+00 1.36E-04 5.69E-05 9.53E-07 Cs-136 3.45E-05 9.61E-05 3.78E-05 0.00E+00 4.03E-05 8.40E-06 1.02E-06 Cs-137 3.92E-04 4.37E-O4 3.25E-05 0.00E+00 '1.23E-U 5.09E-05 9.53E-07 Cs-138 3.61E-07 5.58E-07 2.UE-07 0.00E+00 2.93E-A7 4.67E-08 6.26E-07 Ba-139 1.06E-09 7.03E-13 3.07E-11 0.00E+00 4.23E-13 4.25E-OO 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-Os Ba-141 1.12E-10 7.7AE-14 3.55E-12 0.00E+00 4.64E-14 2.12E^06 3.39E-06 Ba-142 2.8/.E-11 2.36E-14 1.40E-12 0.00E+00 1.36E-14 1.11E-06 4.95E-07 La-140 3.6'lE-07 1.43E-07 3.68E-08 0.00E+00 0.00E+00 1.2OE-04 6.06E-05 La-142 7.36E-10 2.69E-10 6.46E-11 0.00E+00 0.00E+00 5.87E-06 4.25E-05 Ce-141 1.98E-05 1.19E-05 1.42F-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-05 Ce-144 2.28E-O3 8.65E-04 1.26E-04 0.00E+00 3.84E-04 7.03E-03 1.OOE-04 Pr-143 1.00E-05 3.74E-06 4.99E-07 0.00E+00 1.41E-06 3.09E-M 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 5.81E-06 3.57E-07 0.00E+00 2.25e-OO 2.30E-04 2.23E-05 W-l87 9.26E-09 5.44E-09 2.23E-09 0.00E+00 0.00E+00 2.83E-05 2.54E-05 Np239 2.65E-07 2.37E-08 1.34E-08 0.00E+00 4.73E-08 4.25E-05 1.78E-05

Reference:

Dose Factors for Co-57, Zn-69m, Br-82, Nb-97, Sb-124, Sb-125, Sn-125 are from Reference '17, Table 5. All others from: Regulatory Guide 1.109, Table E-l0. NOTE: The tritium dose factorfor bone is assumed to be equal to the total body dose factor. This assumes that tritium will act similarly in all organs (Reference 24).

WBN TWO.UNIT OFFSITE DOSE CALCULATION Revision I 0 MANUAL (ODGM) Page 165 of 205 Figure 7.1 - GASEOUS EFFLUENT RELEASE/DISCHARGE POINTS

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{one per (cclmmCIn) {common) unit) Wast* Ga,s Decay o-RE*90-119 Tanks {s} Containment Purge 1 ,2-RE-SO-1 30.-131 System {one per unit}

                                                                           $hield Building Vent (one psr unit)

WBN TWO.UNIT OFFSITE DOSE CALCULATION Revision 1 0 MANUAL (ODCM) Page 166 of 205 Figure 7.2 - DETAIL OF GASEOUS RELEA$E DI$CHARGE POINTS o oo,E b-U n G (r'i o u o f H$qi r ttrH C)

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WBN TWO.UNIT OFFSITE DOSE CALCULATION Revision 1 0 MANUAL {oDCM} Page 167 of 205 Figure 7.3 - GASEOUS RADWASTE TREATildENT SYSTEM CVS$ \&t*rxs Srpn,tr*l Tank Urt*t 1 fiVf,S Vslume Control Tanh Unit 2 Huldup Tank Units I &2 fteact*r fi,rgin

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WBN TWO-UNIT OFFSTTE DOSE CALCULATTON MANUAL (OtlCM) Revision 0 0 Page 168 of 206 Figure 7.4 - PLUME DEPLETIOiI EFFECT FOR GROUND LEVEL RELEASES (All Stability Classes) 10 h t lry II.HI rrrn sJr t b-.. tr t3 o-s -!r

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WBN OFFSITE DOST CALCULATION Revision 0 0 MANUAL {oDCM} Page 169 of 205 Figure 7.5 -VERTICAL STANDARD DEVIATION OF MAIERIAL lN A PLUME 1 000 tn x. UJ l-UJ 100 a i.l t) 2 g a-l- 5 LT' CI C3 x. C} Z $U' J (} t* r0 u UJ 1"0 pLUMr rRAVf L DlsTANcr {KIL0METIRS} Source: Reference 5, Figure I

WBN TI'I'O.UNIT OFFSITE DOSE CALCULATION Revision 1 0 MANUAL {ODCfrrI} Page 17A of 205 Figure 7.6 - RELATIVE DEPOSITION FOR GROUND LEVEL RELEASES (All Stability Classes) ls-fi.

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WBN TWO.UNIT OFFSITE DOSE CALCULATION Revision I 0 MANUAL {ODCM} Page 17'l of 205 8.0. TOTAL DOSE 8..t TOTAL MA)(IMUM INDIVIDUAL DOSES To determine compliance with 40 CFR 190 as required in ODCM Surveillance Requirement 2.2.3.1 and 2.2.3.2, the dose contributions to the maximum individual from WBN radioactive effluents and all other nearby uranium fuel cycle sources will be considered. The annual dose to the maximum individual will be conservatively estimated by using the following equation: 4 p= SD(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.

WBN TWO-UNIT OFF$ITE DOSE CALCULATION Revision 1 0 MANUAL {ODCM} Page 172 of 205 9.0 - RADIOLOGIGAL ENVIRONMENTAL MONITORING PROGRAI'i (REMP) 9.1 MONITORING PROGRAM DESCRIPTION The REMP shall be conducted in accordance with the requirements of ODCM Gontrol 1.3.'t. 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 tenestrial monitoring prograrn 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 consisb of the collection of samples of surface and ground water, drinking water, sediment, and fish. Samples are collected both downstream 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 mile 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 conective 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 Analytical techniques 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 eonducted 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.

WBN TIII'O.UNIT OFF$ITH DOSE CALCULATION Revision I 0 MANUAL {ODCM} Page 173 of 205 9.4 INTERLABORATORY COMPARISON PROGRAM Analyses shall be performed on radioactive materials supplied as part of an lntedaboratory Comparison Program which is in accordance with RG 4.15. A summary of the results obtained in the intercomparison shall be included in the Annual Radiological Environmental Operating Report. lf analyses are not performed as required corrective actions taken to prevent a recunence shall be reported in the Annual Radiological Environmental Operating Report. 9.5 DATA REVIEW AND REPORTING Results of this program shall be reported in accordance with ODCM Administrative Control 5.1, Annual Radiological Environmental Monitoring Report. Analytical results 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 WBN FSAR Section 11.6, routine releases from WBN will result in environmental concentrations well below the deteclion limits for environmental media, making conelations 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 conelations be made.

WBN TWCI.UNIT OFFSITE DOSE CALCULATION Revision 1

                                                                                   ,,174 0                             MANUAL (oDCM)                         Page       of 205 Table 9.1 - REMP - MONITORING, SAMPLING, AND ANALYSIS (Page 1 of 5)

Exposure Sample Locationsl Sampling and Tlpe 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 ar more dosimeters placed at stations located approximately 5 miles from the plant in each of the 16 sectors 2 ar more dosimeters in at least 8 additional locations of special interest, including at least 2 control stations.

WBN TWO.UNIT OFFSITE DOSE CALCULATION Revision I 0 MANUAL (ODCM) Page 175 of 205 Table 9.1 - REMP - MONITORING, SAMPLING, AND ANALYSIS (Page 2 of 5) Exposure $ample Locationsi $ampling and Tltpe and Frequency of Pathway Collection Frequency Analysis andlor tample

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 onse 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 frorn control location) for gamma locations greater than 10 SCAN. miles from the plant (RM-2 and 3) Radioiodine cartridge: l-131 at least once per 7 days Atmospheric 4 samples from locations Continuous sampler Analyze each sample Moisture (in different sectors) at or operation with for H-3 near the SITE sample collection BOUNDARY biweekly (LM- 1 ,2,3,and 4) 2 samples from communities approximately 4-10 miles distance from the plant. (PM-2,5,) 1 sample from control location greater than 10 miles from the plant (RM-3) Soil Samples from $arne Once per year Gamma scan, Sr-89, location as air particulates. Sr-90 once per year

WBN TWO.UNIT OFFSITE DOSE CALCULATION Revision 1 0 MANUAL (oDCM) Page 176 of 205 Table 9.1 - REMP - MONITORING, SAMPLING, AND ANALYSIS (Page 3 of 5) Exposure Sample Locationsi $ampling and Tl1pe 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 sCIurce once per 31 days upsradient from the plant Drinking 1 sample at the first Collected by Gross beta, gamma potable surface water automatic sequential scan, and H-3 analysis supply downstream from type samplerz 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) l sample at control location3 ffRM 529.3) $horeline 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. Holdins Pond.

WBN TWO.UNIT OFFSITE DOSE CALCULATION Revision I 0 MANUAL {oDCM} Page 177 of 205 Table 9.1 - REMP - MONITORING, SAMPLING, AND ANALYSIS (Page 4 of 5) Exposure $ampls Locationsi Sampling and Tlpe and Frequency of Pathway Collection Frequency Analysis andlor $ample

4. INGESTION Mitk 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 censu$ where once per quarter doses are calculated to be highest. If samples are not available from a milk animal location, 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 control location Fish One sample of At least once per 184 Gamma scan on edible corn mercia ly im portant I days. portion. species (Freshwater Drum or Catfish) and one sample of recreationally important species {Crappie (White or Black), or Bass (Largemouth, Sm all mouth, or Spotted)). One sample of each species from downstream of Watts Bar Nuclear Plant, Chickarna uga reservoir, and Watts Bar reservoir. One control sample of same species in areas not influenced by plant discharge.

WBN TI'YO.UNIT OFFSITE DOSE CALCULATION Revision 1 0 MANUAL (oDCM) Page 178 of 205 Table 9.1 - REMP - MONITORING, SAMPLING, ANI) ANALYSIS (Page 5 of 5) Exposure Sample Locationst Sampling and TlEe and Frequency of Pathway Collection Frequency Analysis andlor $ample 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 andlor harvest. The types of farms in the vicinity of the foods available will plant. vary. Following is a A control sample frorn list of typical foods similar food products which may be grown 15 to 30 km distant available: in the least prevalent wind Cabbage andlor direction. Lettuce Corn Green Beans Potatoes Tomatoes Vegetation4 Samples from farms At least once per 31 l-131 and gamma scan producing milk but not days at least once per 31 providing a milk sample davs. 1 Sample locations, except for Food Products, are listed in Table 9.2 and 9.3, and shown in Figures 9.'1, 9.2, and 9.3. The sample locations for Food Products are provided in the Annual Radioactive Effluent Release Report and are based on the cunent Land Use Survey as addressed in ODCM Surveillance Requirements 2.3.2. 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 = Local Monitor PM = Perimeter Monitor RM = Remote Monitor TRM = Tennessee River Mile

Yl'BN TWO-UNIT OFFSITE DOSE CALCULATION Revision 1 0 MANUAL {ODCM} Page 179 of 205 Table 9.2 - REMP - SAilIPLING LOCATIONS Map Approximate Indicator {l} Samples Location Stationa Sector Distance or Nurnber {mi} Control{C} Collectedb 2 PM.2 NW 7.0 AP, CF, $, AM 3 PM-3 NNE 10.4 AP. CF. S 4 PM.4 NE/ENEC 7.8 AP, CF, S 5 PM.5 S 8.0 AP, CF, S, AM 6 RM.2 SW 15.0 c AP, CF, $, AM 7 RM.3 NNW 15,0 C AP, CF, S, AM 8 LM-1 SSW 0.5 AP, CF, S, AM I LM-2 NNE 0"4 AP, CF, S, AM 10 LM-3 NNE 1.9 AP, CF, D. AM 11 LM-4 SE 0.9 AP, CF, S, AM t8 Well #1 S 0,s W 20 Farm N ESE 4.1 M 23 Well #5 N 0.5 c W 25 TRM 517.9 9.gd SW 26 TRM 523.1 4.7d SW 27 TRM 529-3 1.5d C sw, Ftrye 31 TRM 473.0 {C.f^ lndustries) 54.8d PW 32 TRM 513^0 14.8d I SS 33 TRM 530.2 2.4d C SS 35 TRM 503,8 {Dayton} 24.Ad PW 37 TRM 522.8-527.8 (Downstream of r WBNP) 38 TRM 471-530 {Chickarnau$a Lake} r 39 TRM 530-602 {Watts Bar Lake} c r 81 Yard Pond SSE/SISSW Onsite PS 82 Wel A SSE 0.6 w 83 Wel B SSE 0.5 W 84 Wel C ESE 0.3 W 85 Wel F SE 0.3 W 86 Farm HH SSW 1.4 M 87 Farrn BB SW 18.6 c M a See Figures 9.1. 9.2, and 9.3 bSamplecodes:AP=Airparticulatefiher:CF=Charcoal Filter;F=Fish;S=Soil;AM=atnosphericmoisture,M=Milk'PW= PublicWate4 SS = Shoreline Sediment; SW = Surface Water; W= Well Water, PS= Pond Sediment c Station located on boundary betrrrreen these sectors d Dir,"no from plant discharge [fRM 527.8) e The surface water sample trom TRM 529.3 is also considered a control for raw Public Water samples.

WBN TWCI.UNIT OFF$ITE DOSE CALCULATION Revision t 0 MANUAL TODCM) Page 180 of 206 Table 9.3 - REMP - DOSIMETRY LOCATIONS Map Station Sector Approx. On/ Map Station Sector Approx. On/ Location Dist. Offsitea Location Dist. 0ffsitea Number (rni) Number (mi) 2 NW.3 NW 7.4 off 55 SSE-1A 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 4.7 On 5 s-3 S 7.8 off 58 s-2 S 4.8 off 6 sw-3 SW 15.0 CIff 5g SSW.1 SSW 0.8 On 7 NNW4 NNW 15.0 0fr 60 SSW-3 SSW 5.0 ofr 10 NNE-1A NNE 1.9 0n 62 sw-1 SW 0.8 0n 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 0ff 65 WSW.2 WSW 3,9 0fr 4A N-1 N 1.2 On 66 w-1 w 0.9 On 4',lJ N-2 N 4.7 off 67 WNW-1 WNW 0.9 On 42 NNE.1 NNE 1^2 On 68 WNW-2 WNW 4.9 off 43 NNE.2 NNE 4.1 off 69 NW.1 NW 1.1 On 44 NE-1 NE 0.9 0n 70 NW-2 NW 4.7 off 45 NE.2 NE 2^9 off 71 NNW-1 NNIW 1.0 On 46 NE.3 NE 6.1 0ff 72 NNW.2 NNn/V 4.5 ofr 47 ENE-1 ENE 4.7 On 73 NNW.3 Nf-lw 7.4 off 48 ENE-2 ENE 5.8 off 74 ENE-24 ENE 3,5 off 4g E-1 E 1.3 On 75 SE-zA SE 3.1 off 50 E-2 E 5.0 off 7S S.2A S 2.4 ofr 51 ESE-1 ESE 1.2 On 77 W-2A W 3.2 off 52 ESE-2 ESE 44 off 78 NW.2A NW 3.0 0ff 54 SE.2 SE 5_3 ofr 79 SSE.1 SE 0.5 0n a Dosimeters designated onsite (On ) are those located two miles or less fom the plant. Dosimeters designated offsite (Off) are those located more than two miles from the plant.

WBN TWO.UNIT OFFSITE DOSE CALCULATION Revision 1 0 MANUAL (ODCM) Page 181 of 205 Figure 9.1 - REMP LOCATIONS WITHIN ONE MILE OF THE PLANT NNW NNE 33.75 303.75 5S.25 WNW ENE

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WBN TWO.UNIT OFFSITE DO$E CALCULATION Revision 1 0 MANUAL (oDCM) Page 182 of 205 Figure 9.2 - REMP LOCATIONS FROM ONE TO FIVE MILES FROM THE PLANT ?s t"t5 wATT$ BAR NucLEl& p[e,Nr, YELLOW CfTSEK wlLoLrE MANAGMHilT t6'r i 86*2!, l* tl; 1 Mile*

WBN TWO.UNIT OFFSITE DOSE CALCULATION Revision 1 0 MANUAL TODCM) Page 183 of 205 Fisure 9.3 - REMP LOCATIONS GREATER THAN FIVE MILES FROM THE PLANT

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WBN TWO.UNIT OFFSITE DOSE CALCULATION Revision I 0 MANUAL (ODCM) Page 184 of 205 1O.O REFERENCES

1. NUREG-I301, 'Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Pressurized Water Reactors," Generic Letter 89-01 , Supplement No. 1 . April 199'1.

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

Revisions to 10 CFR Part20, 'Standards for Protection Against Radiation'and 10 CFR 50.36a,

    'Technical Specifications on Effluents from Nuclear Pourer Reactors', (b) Related Cunent lndustry lnitiatives and (c) Miscellaneous Related Editorial Glarifications."

3. NUREG-0133, "Preparation of Radiological Effluent Technical Specifications for Nuclear Power Plants," September 1 978.

4. Regulatory Guide 1 . 1 09, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix 1." Revision 1, October 1977.

5. Regulatory Guide 1.111, "Methods for Estimating Atmospheric Transport and Dhpersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors," Revision 1, July 1977.

6. Regulatory Guide 1 .1 1 3. "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. RadiologicalAssessment Branch Technical Position on EnvironmentalMonitoring, Revision'1, November 1979.

9. WBN Final Environmental Statement, WBNP Units '1,2,3, Chattianooga, TN, November 9,1972.

10. WBN FinalSafety Analysis Report.

1 1. TVA Memorandum, E. E. Driver to 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,o December 15, 1987. 't3. TVA Memorandum, D. L. Stone to B. Eiford-Lee, "Surface area Computations for the Revision of the QWATA Gode," April 26, 1988.

14. Final Supplemental Environmental lmpact Statement, 'Completion and Operation of Watts Bar Nuclear Plant Unit 2,'Tennessee Valley Authority, June, 2007.

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

WBN TWO.UNIT OFFSITE DOS= CALCULATION Revision I 0 MANUAL {ODCM) Page 185 of 205

16. ORNL 4992, 'Methodology for Calculating Radiation Doses from Radioactivity Released to the Environment," March 1976.

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 Occunino in Routine Releases from Nuclear Fuel Cvcle Facilities. D. C. Kocher, Health Physics Volume 38, April 1980.

19. TVA Memorandum, John P. Blackwellto M. L. Millinor, "Development of Atmospheric Dispersion Adjustment Factors for Application in the Watts Bar Nuclear Plant Offsite Dose Calculation Manual,'

November 16,1990.

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

21. NUREG/CR-'l004, "A Statistical Analysis of Selected Parameters for Predicting Food Chain Transport and lnternal Dose of Radionuclides," October 1979.

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

Canbena 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 Offsite Dose Calculation Manual - Changes Required - Revised agreements based on meeting between Nuclear Engineering and Chemistry on March 9, 1994," March 17, 1994 27.TVA Memorandum, Ed Steinhauserand 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 Burnable Absorber Rods fl'PBARS) in Watts Bar Unit 1."

30. WBN Unit 1 and Unit 2 Technical Specifications

31. TVATechnical Paper, "NPG Site Carbon-14 Production and Release Estimates," dated April 19,2011

WBN TWO.UNIT OFFSITE DOSE CALCULATION Revision I 0 MANUAL (ODCM) Page 186 of 205 1,I .O SOURCE NOTES SOURCE Source NOTE Document Summary 1 NCO85019200'l TVA response as described in NRC evaluation SER No. 5, Section 11.7, paragraph 4. 2 NRC lE Bulletin 82-49 Adjust noble gas monitor setpoints based on chamber SQN LER 5U327192019 pressure. 3 Source Note deleted and calibration interval changed to 18 months per NE SSD 1-F-90-4004,8,C,D,452and 2-F-90-400C,-452. 4 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) willalso be included in these specifications. 5 NCO92OO42424 To ensure compliance with Radiological Effluent Tech Specs, cumulative dose calculations will be performed once per month. 6 NCO92AO42422 ODCM shallcontain Radiological EnvironmentalMonitoring Program sampling and analysis frequencies. 7 NCO92OO4250O 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. 8 NCO92AA42501 A complete analysis utilizing the total estimated liquid release for each calendar quarter will be performed and reported as required by Technical Specifications. 9 NCO92OA42502 Dose projections willbe perfonned in accordane,e with Technical Specffications. 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 lor Kurz isokinetic sampling panels will be added to the ODCM.

WBN TWO.UNIT OFFSITE DOSE CALCULATION Revision I 0 MANUAL (oDCM) Page 187 of 205 SOURCE Source NOTE Document Summarv 13 WBPER97O486 Added operability requirements for heat trace on NCO970059002 iodinelparticulate sample lines for Condenser Vacuum NCO970059004 Exhaust and Shield Building Exhausts. 15 WBPER97O492 Changed allowable monitor tolerance factor to 2.0 for ga$eous monitor setpoint calculations. 16 WBPER971 422 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 cunent design output.

WBN TWO.UNIT OFFSITE DOSE CALCULATION Revision I 0 MANUAL (oDCM) Page 188 of 205 APPENDIX A . NOTATION CONVENTIONS (Page 1 of7) SyrnbolKey This symbol key provides a cross-reference between the symbols used in the Watts Bar ODCM and those symbols used in the RegulatoryGuidance documentsforthe 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 syrnbol 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 and C14 is used to denote C-14) 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 ODCM Source Symbol Definition Source Reference $ymbol ct Minimum building cross-sectional area R.G , 1,111 (p. 11) Dr2 A Liquid dose factor NUREG-0133 (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-0133 (p. 15) Ap Dose factor for shoreline resreation N/A ATMW Ratio of average to maximum ingestion N/A rates BKG Background N/A B B ioaccum ul ation factor NUREG-O133 (p. 16) BF b Projected dose for a release N/A Biu Transfer factor for nuclide i from soil to R.G. 1.109 tp. 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 fi

     \,       Concentration                                  NUREG-O133 (p. 15)                   c xlQ        Relative concentration                         R.G. 1.109 (p. 5)                  7J0

WBN TWO.UNIT OFFSITE DOSE CALCULATION Revision I 0 MANUAL (ODCM) Page 189 of 205 APPENDIX A. NOTATION CCIHVTNflONS (Page 2 at 7) m bol Ke WBN ODCM Source Symbol Definition Source Reference Svmbol d Number of days in the current quarter prior NIA to the time of a release D Dose NUREG-O1s3 (p. 1s) D Drur Near-field dilution NUREG-O133 (p. 15) r D/Q Relative deposition R.G . 1.10e (p. 241 d DFB Dose Conversion Factor for total body R.G. 1.109 (p. 6) DTB submersion DFU Dose Conversion Factor for beta air dose R.G. 1.10e (p. s) DFU DFG Dose conversion factor for standing on NUREG-0133 (p. 26) DFG contaminated ground DFs Dose conversion factor for gamma air dose R.G. 1.10e (p. 5) DFg DF lngestion dose cCInversion factor NUREG-O133 tp. 16, 33) DF, DFL DFA lnhalation Dose Conversion Factor NUREG-01 33 (p^ 25) DFA DFS Dose conversion factor for skin submersion R.G. 1.10e (p. 6) DFS 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 Effluent Concentration Lirn it N/A ER Expected Monitor Response NIA F Dilution flow NUREG-0133 Addendum A F f Waste flow NUREG-O133 Addendum A f F1 Transfer factor from cew's feed to beef R.c. 1.10e (p. 28) Fg f0 Fraction of stored vegetables grown locally R.G. 1.10e (p. 7) f* FISH Average amount of fish ingested N/A frt 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. 1.109 (p. 7) F1 locally tr tm Transfer factor from animal's feed to milk R.G . 1.10e {p. 27) tr tm fP Fraction of population in an age group R.G. 1.109 {p" 30} f fn Fraction of time animal spends on pasture R.G. 1.109 (p. 28) fo

WBN TWO.UNIT OFFSITE DOSE CALCULATION Revision I 0 MANUAL (ODCM) Page 190 of 205 APPENDIX A. NOTATION CONVTNflONS (Page 3 of 7) Svrnbol ol Ke K WBN ODCM Source

$ymbol                          Definition                       Source Reference    $ymbol fs         Fraction of time animal spends on           R.G . 1.10e (p. 28)          fs stored feed H          Absolute humidity of the atmosphere         R.G. 'l .109 (p. 27\         H HRSVIS         Length of shoreline resreation visit        N/A HVST          Fish harvest for the Tennessee River        NIA Kc          Transfer coefficient from water to          R.G . 1.10e  (p. 141        Kc shoreline sediment n"        Radioactive decay constant                  N/A 1,p         Effective decay constant                    R.G . 1.109 (p. a)          ?"E LLD          Lower Limit of detection                    NUREG-1 301 (p. 40)        LLD iw          Weathering decay constant                   R.G. 1.109 (p. a)           itw 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. 1.10s (p. 3)             P p         Fraction of radionuclide remaining in       R.G. 1.111 {p. 12],           p plume POP          Population                                  R.G. 1.10e tp. 30)            P POPF          Population dose due to fish ingestion       R.G. 1.10e (p. 30)          pP POPR          Total recreation population dose            R.G , 1,109 (p. 30)         gP POPWTR          Population dose due to water ingestion      R.G . 1.109 (p. 30)         pP 0          Release rate                                NUREG-0133 (p.221            a q         Total release in a period                   NUREG-O133 (p. 2e)            q Q1          Milk animal's consumption rate              R.G . 1.109 (p. 3)           Qt r        Fraction of activity retained on pasture    R.G. 1.109 (p. 3)             r grass.

Rp Gaseous Dose Factor for Pathway P NUREG-0133 (p. 26) P R1 lnhalation dose factor NUREG-0133 (p. 26) P R6 Ground plane dose factor NURHG-0133 (p. 26) P Rcp Pasture grass-milk animal-milk NUREG-O133 (p. 26) P ingestion Rcs Stored feed-milk an mal-milk ingestion NUREG-O133 (p. 26) P Rnltp Pasture grass-beef ngestion NUREG-0133 (p. 2s) P Rnns Stored feed-beef ingestion NUREG-O133 (p. 26) P Rvr Fresh leafy vegetable ingestion NUREG-0133 (p. 26) P

WBN TWO.UNIT OFFSITE DOSE CALCULATION Revision I 0 MANUAL {ODCM} Page 191 of 205 APPENDIX A. NOTATION CONVTNTIONS (Page 4 at 7\ tnnol ne Svrnbol K WBN ODCM Source

$ymbol                       Definition                        Source Reference    Symbol Rvs       Stored vegetable ingestion                   NUREG-O133 (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 sb      Standard deviation                           NUREG-1301 (p, 40)           $g SF       Safety factor                                N/A SHVIS       Shoreline visits per year                    NIA smax       Setpoint corresponding to the ODCM           NIA Limit ZZ      Vertical dispers on coefficient              R.G . 1.111 {p. 1U          zz
    $2      Vertical dispers on coefficient              R.G . 1.111 {p. 1 1}        s7 T       Duration of release                          NUREG-0133 (p, 15)           At At      Elapsed time between midpoint of             NUREG-1 301 (p. 40)          At sample collection and counting time TAF       Terrain adjustment factor                    N/A t6      Time period over which accumulation          R.G. 1.109 (p, 14,26)      tb, t on the ground is evaluated tcb      Time for receptor to consume a whole         N/A beef t6      Distribution time for water, fish, milk,     R.G. 1.10e (p. 4)            tp beef, or vegetables tcsf      Time between harvest of stored feed          R.G . 1.10e (p. a)           tp and consumption by animal te      Exposure time in garden for fresh leafy      R,G. 1.10e (p. 4)            te andlor stored vegetables ten       Time pasture is exposed to deposition        R.G. 'l .109 (p. 4)          te tesf      Time stored feed is exposed to               R.G . 1.10e (p. a)
                                                                                      ,1 re deposition TFDO$       lndividua fish ingestion dose                R.G . 1.109 {p. 30}           D tf*       Transport time from milking to receptor      N/A                         tf*

thc Average time between harvest of R.G. 1.10e {p. 4} t1 vegetables and their consumption and/or storage

WBN TWO.UNIT OFFSITE DOSE CALCULATION Revision 1 0 MANUAL {ODCM} Page 192 of 205 APPENDIX A . NOTATION CONVENTIONS (Page 5 of 7) gymbor Key WBN ODCM Source

 $ymbol                     Definition                        $ource Reference    Symbol ts     Transport time from slaughter to             R.G , 1,109 (p. 28)          ts consurner TSHDOS     Total shoreline dose rate                    R.G. 1.109 (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)           il u     Wind speed                                   R.G. 1.111 (p. e)             u Ug     Fish consumption rate                        NUREG-O133 (p. 16)          Up Urt      Consumption rate of fresh leafy vegetables                                 R.G , 1,109 (p. 7)          gL um      Meat ingestion rate                          R.G. 1.10e {p. 7}           gF UD      Milk ingestion rate                          R.G. 1.109 (p. 7)           un Up      Recreation usage factor                      R.G. 1.10e (p. 14)           U Ug      Consumption rate of stored vegetables        R.G , 1.10s (p. 7)          gV by the receptor uw      Water consumption rate                       NUREG-0133 {p. 16}         Uvv V      Sample size                                  NUREG-1 301 (p. 40)          V W      Dispersion factor                            NUREG-0133 (p,22j           W SWF      Shoreline width factor                       R.G . 1.109 (p. 14)         W x      Downwind distance                            R.G.1.111 (p. 11)            X Y      Radiochemical yield                          NUREG-1 301 (p. 40)          Y Yy      Agricultural yield for fresh leafy           R.G. 1.109 (p. 4)           Vrv vegetables Yp      Agricultural productivity by unit area of    R.G . 1.109 (p. 4)          YV pasture gra$$

Ysf Agricultural productivity by unit area of R.G. 1.109 (p. 4) Yv stored feed Y*r, Agricultural yield for stored vegetables R.G. 1.109 (p. 4) YV

WBN TWO.UNIT OFFSITE DOSE CALCULAT:ON Revision I 0 MANUAL (oDGM) Page 193 of 205 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 Blowdown CVCS - Chemical Volume Control System CVE - Condenser Vacuum Exhaust EPA - Environmental Protection Agency ERCW - EssentialRawCooling Water ESF - Engineered Safety Feature Fl - Flow lndicator 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 - Local Monitor LPF - Loop Flow LRTS - Liquid Radwaste Treatment Sptem 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 TWST - Tritiated Water Storage Tank WBN - Watts Bar Nuclear Plant WGDT - Waste Gas DecayTank

WBN TI'I'O.UNIT OFFSITE DOSE CALCULATION Revision I 0 MANUAL {oBCM} Page 194 of 205 APPENDIX A. NOTATION CONVENTIONS (Page 7 of 7) List of Units The following units are used consistently throughout the WBN ODCM. The table is included to provide the reader with the unil conesponding to each abbreviation used. CC cubic centimeters cfs cubic feet per second ci Curie cpm counts per minute d day g qram gpm gallons per minute h hour ks kilosram L liter tb pound m meters uci mtcrocune mt mile mln minute ml rn lt iter mrad m ll rad mrem m llirem pci plcocune S second v year 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 wlrich are reproduced from Regulatory Guides or NUREGS and used to derive a WBN specific equation are not numbered.

WBN TWO.UNIT OFFSITE DOST CALCULATION Revision 1 0 MANUAL (CIDCM) Page 195 of 205 APPENDIX B - Deviations in the WBN ODCM Controls/Surveillance Requirements from Those Given in NUREG-1301 (Page 1 of4) NOTE: Allfuture deviations to the guidance provided in NUREG-1301 will be documented in the ODCM revision Iog.

1. Controls 1.0.1 and 1.0.2 and Surveillance Requirements 2.0.1-2.0.4 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 WBN ODCM.

2. Control 112.1.1 NUREG-1301 does not list the applicability for liquid monitoring instrumentation.

ApplicabilityforWBN liquid effluent instrumentation is defined in Table't.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 conseryative than required by NUREG-1301. Table 2.1 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. Table 2.1 Footnote 1 is deleted from ltems 1.b (Steam Generator Blowdown Radiation) and 1.c (Condensate Demineralizer radiation). ltem 1.b and 1.e generate an automatic isolation on level above the alarm/trip setpoint, not instrument maffunction. f ab/re2.'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 verify 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 't.1 lncludes operability requirements for heat trace on iodine/particulate sample lines for Condenser Vacuum Exhaust and Shield Building Exhaust. Tables 1.1-2 and 2.1-2 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 clarify 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 pCils, 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 Applicabilityfor ltems 2.a, c , and d (CondenserVacuum 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 sptem 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. Table 2.1 lncludes surveillance requirements for heat trace on iodine/particulate sample lines for Condenser Vacuum Exhaust and Shield Building Exhaust. Table 2.1 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 cannoi be performed.

WBN TWO.UNIT OFFSITE DOSE CALCULATION Revision I 0 MANUAL (oDCM) Page 196 of 205 APPENDIX B - Deviations in the ttVBN ODCM Controls/$urveillance Requirements from Those Given in NUREG-1301 (Page 2 of 4) Table 2.1 The channel check requirements for all iodine and particulate samplers are NlA. A CHANNEL CHECK is defined as verifying indication of flow during periods of release. 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 flow(s) and the weekly sampler filter changeout required by the sampling and analysis program inTable 2.2-2 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 circuil failures that impact the required functions. The notes in Tables 2.1-2 vuhich supplement the COT definition require tests to verify 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 subcomponenl failures. CHANNEL OPERATIONAL TEST frequencies may be extended if justified. The justification includes meeting a 95/95 confidence acceptance criterion based on hardware of similar design.

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 (TBS and SGBD) are for daily grab samples rather than a continuous sampler. This is consistent wilh the requirements of the NRC approved SER and SSER 16 forWBN and the WBN Unit 1 ODCM, Revision 3 (i.e., SER 9407280068, dated July 26, 1994). The definition of a composite liquid effluent sample is somewhat different than that given in NUREG-1301 (WBN 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 analpes for these daily grab samples are daily, rather than weekly. Each sample will be analyzed, rather than compositing the samples for the week.

  'fable 2.2 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 conlrol program. The activity determination is clarified to state that principal gamma emitters will be used for the determination.

6. Control 112.2.2.1:

  'fable 2.2-2 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 requires sampling of containment purge and vent following shutdown, startup, or a thermal power change exceeding 15a/o of RATED THERMAL POWER within a t hour period. This is consistent with the NUREG, but WBN 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 NRC approved SER and SSER 16 forWBN and the WBN Unit't ODCM, Revision 3 (i.e., SER 9407280068, dated July26, 1994).

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

WBN TWO.UNIT OFFSITE DOSE CALCULATION Revision I 0 MANUAL {ODCM} Page 197 of 205 APPENDIX B - Deviations in the WBN ODCM Controls/Surveillance Requirements from Those Given in NUREG-1301 (Page 3 of 4)

c. Table 2.2-2, Footnote 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.

d. Table2.2-2, 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.

e. Table2.2-2, 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.

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

g. lable 2.2-2, the table limits the principal gamma emitters for grab samples to the noble gas nuclides to clarify that particulate releases are quantified from filter analyses.

h. 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.

i. Table 2.2 Requirements for continuous tritium sampling were added for the Auxiliary Building Exhaust, Unit 1 Shield Building, and Unit 2 Shield Building Exhaust to quantify releases during the inadiation and storage of TPBARS. Since tritium samples will be collecled 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.

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

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

7. Control 112.3.1:

a. Table 2.$1 - 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 NUREG-1301. 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 al both SQN and BFN and is reflected in their EnvironmentalMonitoring Programs.

c. Text is added to Table 2.3-1 footnote 8 to state that the hydraulic gradient of the groundwater at the WBN 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 clarify 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.'l - 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.

WBN TWO.UNIT OFFSITE DOSE CALCULATION Revision 1 0 MANUAL (ODCM) Page 198 of 205 APPENDIX B - Deviations in the WBN ODCM GontrolslSurveillance Requirements from Those Given in NUREG-1301 (Page 4 of4)

11. Not used.

12. BASES '112.2.2.1 - 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.

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 112.3.1- An 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 TVA on 111194. The definitions are consistent with that regulation. Similar changes are made to the BASES sections to clarify 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 .6 tor 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 reflect changes made in the definition for SQN (revision 27). The new 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 signalto the photomultiplier tube).

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

18. NUREG-I301 provides guidance for sampling and/or monitoring of specific media, which includes invertebrates. TVA has determined that within the vicinity of WBN, there are no invertebrates that are harvested for commercialor recreational consumption. Therefore, TVA has deleted all requirements regarding invertebrate sampling and/or monitoring for WBN.

19. NUREG-1301 provides guidance for CHANNEL OPERATIONAL TEST (COT) frequency. TVA has extended the COT frequency guidance of NUREG-130'l based on the results of TVA calculation WBN-EBB-EDQ-1090-99005, 'Extending Channel Operational Test Frequency for Radiation Monitors.' The COT frequency was evaluated utilizing the binomial density function referenced in NUREG-1475 to analpethe work orders against 95/95 criteria. The radiation monitoring loops (and subsequent work orders) were divided into four categories due to difiering radiation monitoring equipment function, and calibration frequency. Each category was analyzed separately to the 95/95 probability and confidence that the attribute of interest is indicative of the population. The attribute of interest for this statistical test is the "as-left' band.

WBN TWO.UNIT OFFSITE DOSE CALCULATION Revision 1 0 MANUAL {oDCM) Page 199 of 205 APPENDIX C . WBN ODCM REVISION PROCESS (Page I of7) This Appendix establishes the minimum requirements for preparation, review, and approval of the Wafts 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 Responsi bilities 1.1 Affected Organization Review (AOR) The identification of afiected 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 (lAR) is the process of performing an independent technical review by Qualified Reviewers (QR) of activities potentially affecting nuclear safety. The IQR shall NOT include the person who prepared the ODCM revision. An IQR is performed by QRs designated by responsible department hvel managers to perform an independent technical review of activities potentially affecting nuclear safety. 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 IQR 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 approvalof the ODCM. 1.5 ApprovalAuthority The Plant Manager will approve all revisions to the ODCM as required by Technical Specifications. Signature authority shall not be delegated to a lower level manager.

WBN TWO-UNIT OFFSITE DOSE CALCULATION Revision 1 0 MANUAL (oDCM) Page 200 of 205 APPENDIX C .I/I'BN ODCM REVISION PROCESS (Page 2of 7\ 2.0 Processing ODCM Revisions 2.1 Requestor (lf other than the Sponsor) ldentifythe need for an ODCM improvement. Prepare a justification for the ODCM revision. Aftach a marked-up copy of the existing ODCM. Forward the requested ODCM revision to the sponsoring organization. 2.2 ODCM 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 allchanges in a draft revision on BSL. ldentify the organizations to perform AOR and complete the top portion of Attachment A for each organization. Distribute Attachment A to each Afiected 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 Reviewthe ODCM using all questions on Attachment B as a guideline and forward comments to the Sponsor. ldentify discipline or organization to perform CDR, if needed.

WBN TWO.UNIT OFFSITE DCISE CALCULATION Revision I 0 MANUAL (oBCM) Page 201 of 205 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, identify procedures/documents which require revision to implement the ODCM revision on the Attachment A, and return the Aftachment A to the ODCM Sponsor. 2.4 Sponsor Resolve comments and obtain reviewer's concurrence in BSL. Escalate any unresolved comments to appropriate management. Ensure ODCM has been reviewed by sponsor and IQR 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 Effec'tive Date typically 60 calendar days forward UNLESS there is reasonable justification for making it effective earlier, such as plant operating conditions, test schedules, commitment or conective 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 Manager Approve lhe 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.

WBN TWO.UNIT OFFSITE DOSE CALCULATION Revision 1 0 MANUAL {oDCM} Page 2A2 of 205 APPENDIX C . WBN ODCM REVISION PROCESS (Page 4 ot7) 3.9 ODCM Sponsor Ensure all Affected Organizations have completed and returned Attachment A prior to the effective date of the ODCM. Forward the approved ODCM change to Management SeMces 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. Forward a completed copy of each revision to Licensing to be filed and forwarded 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.

WBN TWO-UNIT OFFSITE DOSE CALCULATION Revision 1 0 MANUAL (0DCM) Page 203 of 205 APPENDIX C . WBN ODCM RTUTION PROCESS (Page 5 of 7) Attachment A ODCM Affected Organization Review/lmplementation Proposed ODCM Revision No. Expected PORC Review Date: Expected Effective Date: AffectedOrganization: t] Operations tI RADCON II Chemistry I] Maintenance I I Technical Support tI Scheduling II Engineering t] Licensing tI Other The following procedures/documents will require revision to implement this ODCM change: PROCEDUREIDOGUMENT PROCEDURilDOCUMENT ODCM Approval Date: ODCM Effsctive 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

WBN TWO.UNIT OFFSITE DOSE CALCULATION Revision I 0 MANUAL (ODCM) Page 2A4 of 205 APPENDIX G . WBN ODCM REVISION PROCESS {Page 6 of 7) Attachment B ODCM 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. Changes to Sectionts) 1.0-5.0 YES NO NIA 1 Does the revision meet the intent of the guidance provided in NUREG-1301 for radiological effluent and environmental monitoring co ntrol s/su rveil lance req u i rem ents?

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

5- 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?

tr i.r. Does the numbering of the Control and its accompanying $urveillance Requ irement 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?

L Are referenced documents applicable, valid, and listed in the reference section? o 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: I Preparer Date I IQR Date

WBN TWO.UNIT OFFSITE DOSE CALCULATION Revision I 0 MANUAL {ODCM} Page 205 of 205 APPENDIX C - VI'BN ODCM REVISION PROCESS (Page 7 ot 7) Attachment B ODCM Review Checklist {continued} Changes to Section{s} 6.0-11.0 YES NO N'A

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

11 Are references to ODCM Controls and Surveillance Reguirements accurate and correct?

12. Are changes to setpoint calculation methodologies consistent with the suidance provided in NUREG-0133?

13. Are changes to liquid effluent concentration compliance methodologies consistent with the guidance provided in NUREG-O133 and 10 CFR Part 2A?

14. Are changes to gaseous effluent dose rate calculation/compliance methodologies consistent with the guidance provided in NUREG-01 33 and/or Resulatory Guide 1 .109?

15. Are changes to dose or dose projection calculationlcompliance methodologies consistent with the guidance provided in NUREG-0133 andlor Regulatory 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 conect?

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

21 . Are any ne\M acronyms defined in Appendix A?

22. Are equation$ numbered consecutivelv?

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 siven 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 given 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 Fisures 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 I IQR ilate}}

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