ML11166A154

2011/05/23 Watts Bar 2 OL - Chapter 11 FSAR RAI Response

ML11166A154
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Site:	Watts Bar
Issue date:	05/23/2011
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To:	Division of Operating Reactor Licensing
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1 WBN2Public Resource From: Stockton, Rickey A [rastockton@tva.gov]

Sent: Monday, May 23, 2011 4:46 PM To: Poole, Justin; Milano, Patrick Cc: Crouch, William D; Boyd, Desiree L; Bryan, Robert H Jr

Subject:

Chapter 11 FSAR RAI Response Attachments:

2011-05 Chapter 11 FSAR RAI Response Final.pdf Justin/Pat, HereistheChapter11FSARRAIResponseAsalways,pleasecallusifyoushouldhaveanyquestions, Rickey Stockton Unit 2 Licensing (423) 365-7741 Hearing Identifier: Watts_Bar_2_Operating_LA_Public Email Number: 394 Mail Envelope Properties (6B28FBDBF05ED74B8991E9374A9F54D90B1AC103)

Subject:

Chapter 11 FSAR RAI Response Sent Date: 5/23/2011 4:46:13 PM Received Date: 5/23/2011 4:47:31 PM From: Stockton, Rickey A Created By: rastockton@tva.gov Recipients: "Crouch, William D" <wdcrouch@tva.gov> Tracking Status: None "Boyd, Desiree L" <dlboyd@tva.gov>

Tracking Status: None "Bryan, Robert H Jr" <rhbryan@tva.gov> Tracking Status: None "Poole, Justin" <Justin.Poole@nrc.gov> Tracking Status: None "Milano, Patrick" <Patrick.Milano@nrc.gov>

Tracking Status: None Post Office: TVANUCXVS2.main.tva.gov

Files Size Date & Time MESSAGE 202 5/23/2011 4:47:31 PM 2011-05 Chapter 11 FSAR RAI Response Final.pdf 2735140 Options Priority: Standard Return Notification: Yes Reply Requested: Yes Sensitivity: Normal Expiration Date: Recipients Received:

Tennessee Valley Authority, Post Office Box 2000, Spring City, Tennessee 37381-2000 May 20, 2011 10 CFR 50.4(b)(6) 10 CFR 50.34(b)

U.S. Nuclear Regulatory Commission

ATTN: Document Control Desk Washington, D.C. 20555-0001 Watts Bar Nuclear Plant, Unit 2 NRC Docket No. 50-391

Subject:

WATTS BAR NUCLEAR PLANT (WBN) UNIT 2 - RESPONSE TO FINAL SAFETY ANALYSIS REPORT (FSAR), CHAPTER 11 AND FINAL SUPPLEMENTAL ENVIRONMENTAL IMPACT STATEMENT (FSEIS) REQUEST FOR ADDITIONAL INFORMATION

References:

1. NRC Letter to TVA dated April 13, 2011, "Watts Bar Nuclear Plant Unit 2 - Status of Operating License Application Review and Project Schedule Implications (TAC No. ME0853)" 2. TVA letter to NRC dated February 15, 2008, "Watts Bar Nuclear Plant (WBN) - Unit 2 - Final Supplemental Environmental Impact Statement for the Completion and Operation of Unit 2" 3. TVA letter to NRC dated December 17, 2010, "Watts Bar Nuclear Plant (WBN) - Unit 2 - Final Safety Analysis Report (FSAR),

Amendment 102" 4. TVA letter to NRC dated February 25, 2011, "Watts Bar Nuclear Plant (WBN) Unit 2 - Final Safety Analysis Report (FSAR) -

Response to Chapters 11 and 12 Request for Additional Information" 5. E-mail from Justin C. Poole, U.S. Nuclear Regulatory Commission to William D. Crouch, TVA dated March 4, 2011 The purpose of this letter is for the Tennessee Valley Authority (TVA) to respond to the NRC regarding the status of Unit 2 FSAR Chapter 11 and Chapter 3 of the FSEIS (Reference 2).

U.S. Nuclear Regulatory Commission Page 2 May 20, 2011 Enclosure 1 provides the responses to RAIs received via email on March 4, 2011 (Reference 5), with respect to Reference 4. The NRC questions and associated numbering are retained herein. Attachments 1 and 2 to this enclosure provide excerpted supporting information regarding liquid and gaseous release tables for the FSAR and FSEIS. The Enclosure 1, Attachments 1 and 2 tables are repeated in Enclosure 2, Attachments 2 through 5. Enclosure 2, Attachment 1, provides a summary of proposed changes to FSAR and FSEIS text and tables. The purpose of this document is to provide a summary description of the changes that have been proposed. Two of the primary issues addressed are Terrain Adjustment Factors and Feeding Factors. A summary of these issues is specifically addressed describing TVA's research and proposed resolutions to address these issues. Attachment 2 provides proposed markups of the FSAR pages and tables, followed by Attachment 3, which incorporates these changes to clean copy of FSAR Sections 11.1, 11.2 and 11.3. Attachment 4 provides similar markups for the FSEIS, followed by Attachment 5, which also incorporates these proposed revisions into a clean copy of FSEIS, Chapter 3. The proposed FSAR revision (Enclosure 2, Attachment 3) will be included in FSAR Amendment A104. The proposed FSEIS revisions will be issued by June 20, 2011. TVA will not meet all 10 CFR 50, Appendix I addendum RM 50-2 dose limits for the site. As a result, TVA will complete a Cost Benefit Analysis per Regulatory Guide 1.110 by July 29, 2011. TVA also received additional request for information at a public meeting on May 11, 2011, regarding inputs for the dose calculations. This additional information will be provided by May 27, 2011. Enclosure 3 provides the commitments as described in this submittal. Should you have any questions, please contact Bill Crouch at (423) 365-2004.

U.S. Nuclear Regulatory Commission Page 4 May 20, 2011 cc (Enclosures): U. S. Nuclear Regulatory Commission Region II Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, Georgia 30303-1257 NRC Resident Inspector Unit 2 Watts Bar Nuclear Plant 1260 Nuclear Plant Road Spring City, Tennessee 37381 Response to FSAR Chapter 11 and FSEIS Chapter 3 Request For Additional Information Response to Chapter 11 RAIs ENCLOSURE 1 WATTS BAR NUCLEAR PLANT UNIT 2 RESPONSE TO FINAL SAFETY ANALYSIS REPORT CHAPTER 11 AND FSEIS CHAPTER 3 REQUEST FOR ADDITIONAL INFORMATION NRC Requested Clarification 1The biggest issues are associated with the calculation of offsite doses from gaseous effluent releases (Table 11.3-10 FSAR Section 11.3). TVA has not provided an adequate basis for the changes they made to the feeding factor (in Amendment 98) nor the terrain adjustment factors (and X/Q, D/Q) in Amendment 100 and in the mark up Amendment 103 included in their response. The information in the responses to questions (22), and (23) in Enclosure 1 (& 11.3.a in Enclosure 2), respectively, do not provide an adequate basis for either. These changes form the basis for the complete revision to Table 11.3-10 that is included in the Amendment 103 mark up (Enclosure 3). The TVA re-analysis of the offsite doses may impact their Environmental Impact Statement (EIS), as well as the NRC's draft EIS. TVA ResponseLand Use Data Correction Prior to Amendment 100, Unit 2 FSAR Table 11.3-8 in Section 11.3 contained the same Land Use Survey (LUS) data as the Unit 1 FSAR Table 11.3-9. In Amendment 100, Unit 2 FSAR Table 11.3-8 was revised to match the 2007 LUS data listed in Table 3-19 of the Final Supplemental Environmental Impact Statement (FSEIS), as a result the Terrain Adjustment Factor (TAF), Atmospheric Dispersion Coefficients (X/Q), and Atmospheric Deposition Coefficients (D/Q) for each receptor also changed. See excerpted FSAR Table 11.3-8 and FSEIS Table 3-19 in Enclosure 1, Attachment 1. Feeding Factor Correction TVA has revised FSAR Table 11.3-8 "Data on Points of Interest near Watts Bar Nuclear Plant" to show the use of a feeding factor of 0.65 for all cow receptors in the 2007 LUS. The value is taken from a chart in NUREG/CR-4653 that provides the growing season across the US. The value chosen is on the high end for the middle Tennessee Valley. This a conservative value as land use survey data for two of the three farms showed that supplemental feed is used almost exclusively. The third farm is unwilling to participate in the survey; however there is public information available as to the size of the farm and number of cattle. This information would support a much lower feeding factor than is being used. Table 3-19 of the FSEIS is being revised to match FSAR Table 11.3-8. See excerpted FSAR Table 11.3-8 and FSEIS Table 3-19 in Enclosure 1, Attachment 1.

Supplemental feed is assumed to be grown in the vicinity of Watts Bar and have the same nuclide source as the pasture. The approach used for decay is similar to that provided in Regulatory Guide 1.109 as described in FSAR Section 11.3.10.1. Terrain Adjustment Factor Correction The computer code titled Gaseous Effluent Licensing Code (GELC) was used to perform routine dose assessments for WBN. During Unit 1 licensing, terrain adjustment factors (TAF) were developed to account for recirculation effects due to the river valley location of the plant. The results in Unit 2 FSAR Table 11.3-8 were revised to use TAFs developed on the same basis that were used for Unit 1 licensing.

E1-1 ENCLOSURE 1 WATTS BAR NUCLEAR PLANT UNIT 2 RESPONSE TO FINAL SAFETY ANALYSIS REPORT CHAPTER 11 AND FSEIS CHAPTER 3 REQUEST FOR ADDITIONAL INFORMATIONUnit 2 FSAR Table 11.3-8 was revised to match the data listed in Table 3-19 of the FSEIS and as a result the TAF, X /Q, and D/Q for each receptor also changed. Table 3-19 of the FSEIS only lists the receptor, the sector, and the distance. See excerpted FSAR Table 11.3-8 and FSEIS Table 3-19 in Enclosure 1, Attachment 1. Sector Distance Correction Although not specifically questioned in this RAI, the sector distances listed in Table 3-19 of the FSEIS were reviewed and compared to the values in FSAR Table 11.3-8. It was discovered

that Table 3-19 contained several errors. These have been fixed in and the data is now

consistent in both the FSEIS and the FSAR. See excerpted FSAR Table 11.3-8 and FSEIS Table 3-19 in Enclosure 1, Attachment 1. Doses from Gaseous Effluents A vegetable pathway has supplanted the milk pathway as the primary pathway since a local resident has established a garden near or almost on the site boundary. This resulted in a revision to Table 11.3-10 and FSEIS Table 3-21. See excerpted FSAR Table 11.3-10 and FSEIS Table 3-21 in Enclosure 1, Attachment 1.

Conclusion The doses listed in Table 11.3-10 Unit 2 FSAR Section 11.3 were recalculated using the 2007 LUS with a feeding factor of 0.65, GELC with TAFs developed on the same basis that was used for Unit 1 licensing, and updated X/Q, and D/Q values for each receptor. The FSAR text in Section 11.3 has been revised to reflect the changes discussed in this RAI response. These changes form the basis for a revision to Unit 2 FSAR Chapter 11 and the FSEIS Chapter 3.

NRC Requested Clarification 2TVA still has not cleared up the uncertainty over which source term was used to calculate the offsite doses (both the liquid effluent doses in Table 11.2-7 and the gaseous doses in Table 11.3-10). [1]The answer to question (9) in Enclosure 1, concerning the source term used for liquid effluent doses, appears inconsistent with the answer to question (3.c) in Enclosure 2. [2]In addition, answer to questions (18) and (20) in Enclosure 1 appear incorrect. The answer to (18) states that table 3-20 of TVA's FSEIS is in error and that the correct source term that was used to calculate the offsite doses is given in FSAR Table 11.3-7c. [3]The answer to (20) indicates that Table 11.3-7c is based on the normal values in NUREG-0017 adjusted for WBN.

However, the isotopic source term in Table 11.3-7c reflects a 1% failed fuel maximum design basis, not the normal release assumption of NUREG-0017 which are the appropriate source term assumption for demonstrating that the design criteria of 10 CFR 50 Appendix A are met. TVA ResponseThere are multiple parts to this requested clarification. Numbering has been added to the individual parts. The individual questions and answers are provided below.

E1-2 ENCLOSURE 1 WATTS BAR NUCLEAR PLANT UNIT 2 RESPONSE TO FINAL SAFETY ANALYSIS REPORT CHAPTER 11 AND FSEIS CHAPTER 3 REQUEST FOR ADDITIONAL INFORMATION1. The answer to question (9) in Enclosure 1, concerning the source term used for liquid effluent doses, appears inconsistent with the answer to question (3.c) in Enclosure 2. Response to 1 There have been a number of RAIs concerning FSAR Table 11.2-5 due to its complexity and lack of description of the planned operational modes for the liquid radwaste system in the text of FSAR Section 11.2 and thus what source term was used to develop the doses provided in FSAR Table 11.2-7. Section 11.2.6.5 has been revised to provide a description of the various plant operational modes. In addition, two operational modes discussed have been removed as they were either never used or were non-limiting. Columns 6, 7, and 8 of the table were revised to provide the source term for the liquid release, the steam generator blowdown release and the

total release for the normal plant operational alignment of the liquid radwaste system. The source term from Column 8 is used to calculate the doses presented in FSAR Table 11.2-7. The Column labeled "1 Unit LWR" in Table 3-16 of the FSEIS is now the same as FSAR Table 11.2-5 Column 6 for the liquid release. The Column labeled "1 Unit SGB" in Table 3-16 of the

FSEIS is now the same as FSAR Table 11.2-5 Column 7. The Column labeled "1 Unit Totals" in Table 3-16 of the FSEIS is now the same as FSAR Table 11.2-5 Column 8. The table in Enclosure 2 of TVA's Reference 4 response to NRC Question 3.c is now the same as the first three source term columns of Table 3-16 in the FSEIS. Thus, all three tables (i.e., FSAR Table

11.2-5, FSEIS Table 3-16 and the table in TVA's February 25, 2011 letter) are consistent. , Attachment 1 provides the three tables discussed. 2. In addition, answer to questions (18) and (20) in Enclosure 1 appear incorrect. The answer to (18) states that table 3-20 of TVA's FSEIS is in error and that the correct source term that was used to calculate the offsite doses is given in FSAR Table 11.3-7c. Response to 2 NRC Question 18 identified that there was a significant inconsistency between the gaseous release source term shown in the FSEIS (Table 3-20) and FSAR Table 11.3-7c. The FSAR table contained the correct values. The FSEIS table needed to be updated. WBN uses the continuous containment vent as the normal operational mode. The necessary changes have been made and now the two tables will show the same values. As stated in the response to NRC Question 20 (Reference 4), the source term used for the gaseous releases as shown in FSAR Table 11.3-7c were based on ANSI 18.1-1984 as adjusted for plant specific conditions.

The nominal values in the ANSI standard are the same values used in NUREG-0017. The title of FSAR Table 11.3-7c is being changed to make it clear that the values are based on ANSI-18.1-1984 and will be included in Amendment 104. See excerpted FSAR Table 11.3-7c in Enclosure 1, Attachment 1. 3. The answer to (20) indicates that Table 11.3-7c is based on the normal values in NUREG-0017 adjusted for WBN. However, the isotopic source term in Table 11.3-7c reflects a 1%

failed fuel maximum design basis, not the normal release assumption of NUREG-0017 which are the appropriate source term assumption for demonstrating that the design criteria of 10 CFR 50 Appendix A are met.

E1-3 ENCLOSURE 1 WATTS BAR NUCLEAR PLANT UNIT 2 RESPONSE TO FINAL SAFETY ANALYSIS REPORT CHAPTER 11 AND FSEIS CHAPTER 3 REQUEST FOR ADDITIONAL INFORMATION E1-4Response to 3 The isotopic source term provided in FSAR Table 11.3-7c is based on ANSI-18.1-1984 (NUREG-0017). The data in the Table is much lower than would be the case if a 1% failed fuel assumption had been used. FSAR Table 11.3-7b provides the 1% failed fuel design case. The second column of Table 11.3-7b labeled "Exp. Rel." is the ANSI values. The fourth column labeled "Design" provides the 1% failed fuel values. Enclosure 1, Attachment 1 provides FSEIS table 3-20, FSAR Tables 11.3-7b and 11.3-7c. , Attachment 1 Response to FSAR Chapter 11 and FSEIS Chapter 3 Request For Additional Information Gaseous Release Tables (includes 11.3-7b, 11.3-7c, 11.3-8, 11.3-10, 11.3-11; FSEIS Tables 3-19, 3-20, 3-21)

FSAR Tale 113 Design For 1 Failed Fuel Epected Gas Release Concentration Effluent Concentration Limit Wit Continuous Filtered Containment Vent Seet 1 of 2 Exp.Rel.(Ci/yr) Des/Ex p Design(Ci/yr) Design(Ci/c c)10CFR 20(ECL) Single Unit OperationC/ECL Dual Unit Operation C/ECLr-85m 9.48E00 12.28 1.16E02 4.02E-11 1.0E-070.0004024 0.0008048 r-856.78E02 33.082.24E04 7.75E-09 7.0E-070.0110743 0.0221486 r-87 5.81E00 7.454.33E01 1.50E-11 2.0E-080.0007480 0.0014960 r-881.32E01 12.331.63E02 5.63E-11 9.0E-090.0062505 0.0125010 Xe-131m 1.09E03 2.913.18E03 1.10E-09 2.0E-060.0005489 0.0010978 Xe-133m 4.31E01 43.24 1.86E03 6.44E-10 6.0E-070.0010735 0.0021470 Xe-133 2.90E03 111.07 3.22E05 1.11E-07 5.0E-070.2227110 0.4454220 Xe-135m 4.68E00 5.042.36E01 8.15E-12 4.0E-080.0002038 0.0004076 Xe-135 8.88E01 6.976.19E02 2.14E-10 7.0E-080.0030561 0.0061122 Xe-138 4.34E00 5.432.36E01 8.15E-12 2.0E-080.0004073 0.0008146 Br-84 5.07E-02 2.501.27E-01 4.38E-14 8.0E-080.0000005 0.0000010 I-1311.53E-01 52.418.00E00 2.77E-12 2.0E-100.0138277 0.0276554 I-132 6.73E-01 4.002.69E00 9.30E-13 2.0E-080.0000465 0.0000930 I-1334.57E-01 26.851.23E01 4.24E-12 1.0E-090.0042433 0.0084866 I-134 1.07E00 1.651.77E00 6.10E-13 6.0E-080.0000102 0.0000204 I-135 8.42E-01 7.916.66E00 2.30E-12 6.0E-090.0003837 0.0007674 Cs-134 2.27E-03 40.60 9.20E-02 3.18E-14 2.0E-100.0001589 0.0003178 Cs-136 8.01E-05 165.20 1.32E-02 4.57E-15 9.0E-100.0000051 0.0000102 Cs-137 3.48E-03 153.22 5.33E-01 1.84E-13 2.0E-100.0009203 0.0018406 Cr-51 5.92E-04 0.291.73E-04 5.96E-17 3.0E-080.0000000 0.0000000 n-54 4.31E-04 0.472.03E-04 7.01E-17 1.0E-090.0000001 0.0000002 Fe-59 7.70E-05 3.482.68E-04 9.27E-17 5.0E-100.0000002 0.0000004 Co-58 2.32E-02 5.371.24E-01 4.30E-14 1.0E-090.0000430 0.0000860 Co-60 8.74E-03 1.381.21E-02 4.17E-15 5.0E-110.0000833 0.0001666 Sr-892.98E-03 22.456.69E-02 2.31E-14 1.0E-090.0000231 0.0000462 Sr-901.14E-03 13.491.54E-02 5.33E-15 6.0E-120.0008877 0.0017754 r-95 1.00E-03 1.711.71E-03 5.92E-16 4.0E-100.0000015 0.0000030 Nb-95 2.45E-03 2.345.73E-03 1.98E-15 2.0E-090.0000010 0.0000020 Ba-140 4.00E-04 0.311.26E-04 4.34E-17 2.0E-090.0000000 0.0000000 -3 1.39E02 11.39E02 4.80E-11 1.0E-070.0004811 0.0009622 -3 (TPC)3.70E02 1 3.70E02 1.28E-10 1.0E-070.0012775 0.0012775 1 rod 1.53E03 11.53E03 5.29E-10 1.0E-070.0052869 0.0052869 2 rod 2.69E03 12.69E03 9.30E-10 1.0E-070.0092962 0.0092962 C-14 7.30E00 17.30E00 2.52E-12 3.0E-090.0008410 0.0016820 Ar-41 3.40E01 13.40E01 1.18E-11 1.0E-080.0011752 0.0023504 Total0.2696131 0.5392262 Total (TPC) 0.2704095 0.5400226 1 rod 0.2744189 0.5440320 2 rod 0.2784283 0.5480413 FSARTale 113 Design For 1 Failed Fuel Epected Gas Release ConcentrationEffluent Concentration Limit Wit Continuous Filtered Containment Vent Seet 2 of 2 Note The "Dual Unit peration" column in the above calculation considers dual unit operation. Based on the evaluation done for Revision 7, the per unit concentrations are the same for both units. Therefore, the last column is twice the preceding column except in the case of TPC. Note Dual unit operation considers only Unit 1 with TPC.

FSAR Tale 113c Total Releases ased on ANSI 111 in Cir it Continuous Filtered Containment Vent Seet 1 of 1 Table based on operation of one unit TotalNuclide Containment Building Auxiliary BuildingTurbine Buildingr-85m 3.72E00 4.53E00 1.23E00 9.48E00 r-856.69E02 7.05E001.86E00 6.78E02 r-874.48E-01 4.27E001.09E00 5.81E00 r-883.10E00 7.95E002.13E00 1.32E01 Xe-131m 1.07E03 1.73E01 4.53E00 1.09E03 Xe-133m 4.07E01 1.90E00 5.21E-01 4.31E01 Xe-133 2.82E03 6.70E01 1.77E01 2.90E03 Xe-135m 2.26E-02 3.68E00 9.80E-01 4.68E00 Xe-135 5.83E01 2.40E01 6.46E01 8.88E01 Xe-137 3.76E-04 9.67E-01 2.58E-01 1.23E00 Xe-138 1.69E-02 3.42E00 9.06E-01 4.34E00 Ar-413.40E01 0.00E000.00E00 3.40E01 Br-848.16E-07 5.02E-024.81E-04 5.07E-02 I-1316.74E-03 1.39E-017.08E-03 1.53E-01 I-1321.36E-04 6.56E-011.70E-02 6.73E-01 I-1332.36E-03 4.35E-012.03E-02 4.57E-01 I-1344.26E-05 1.06E001.47E-02 1.07E00 I-1358.80E-04 8.10E-013.13E-02 8.42E-01 -31.39E02 0.00E000.00E00 1.39E02 Cr-519.21E-05 5.00E-040.00E00 5.92E-04 n-54 5.30E-05 3.78E-04 0.00E00 4.31E-04 Co-578.20E-06 0.00E000.00E00 8.20E-06 Co-582.50E-04 2.29E-020.00E00 2.32E-02 Co-602.61E-05 8.71E-030.00E00 8.74E-03 Fe-59 2.70E-05 5.00E-05 0.00E00 7.70E-05 Sr-891.30E-04 2.85E-030.00E00 2.98E-03 Sr-905.22E-05 1.09E-030.00E00 1.14E-03 r-954.80E-08 1.00E-030.00E00 1.00E-03 Nb-951.80E-05 2.43E-030.00E00 2.45E-03 Ru-1031.60E-05 6.10E-050.00E00 7.70E-05 Ru-1062.70E-08 7.50E-050.00E00 7.50E-05 Sb-125 0.00E00 6.09E-05 0.00E00 6.09E-05 Cs-134 2.53E-05 2.24E-03 0.00E00 2.27E-03 Cs-136 3.21E-05 4.80E-05 0.00E00 8.01E-05 Cs-137 5.58E-05 3.42E-03 0.00E00 3.48E-03 Ba-140 2.30E-07 4.00E-04 0.00E00 4.00E-04 Ce-1411.30E-05 2.64E-050.00E00 3.95E-05 C-14 2.80E00 4.50E00 0.00E00 7.30E00 FSAR Tale 113 Data On Points Of Interest Near Watts Bar Nuclear Plant Page 1 of 2Sector Distance (eters)Chi-over(s/m3)D-over-Q(1/m2)Terrain Adjustment Factor ilkFeeding FactorUnrestricted Area Boundary N 15505.12e-068.13e-091.70 Unrestricted Area Boundary NNE19806.35e-061.23e-081.80 Unrestricted Area Boundary NE 15801.05e-051.10e-082.10 Unrestricted Area Boundary ENE 13701.23e-058.77e-091.70 Unrestricted Area Boundary E 12801.37e-059.66e-091.60 Unrestricted Area Boundary ESE 12501.43e-051.16e-081.80Unrestricted Area Boundary SE 12501.11e-059.49e-091.50 Unrestricted Area Boundary SSE 12506.04e-068.21e-091.50Unrestricted Area Boundary S 13405.33e-061.17e-081.90 Unrestricted Area Boundary SSW 15504.14e-061.05e-082.00 Unrestricted Area Boundary SW 16704.46e-067.34e-092.10 Unrestricted Area Boundary WSW14305.47e-066.37e-091.80 Unrestricted Area Boundary W 14602.11e-062.07e-091.20 Unrestricted Area Boundary WNW14002.49e-062.38e-092.50 Unrestricted Area Boundary NW14002.05e-062.13e-091.70 Unrestricted Area Boundary NNW14602.68e-063.08e-091.60 Nearest Resident N2134 2.84e-06 4.21e-09 1.50 Nearest Resident NNE 36002.69e-064.41e-091.80 Nearest Resident NE3353 3.84e-06 3.22e-09 2.20 Nearest Resident ENE2414 6.26e-06 3.83e-09 1.90 Nearest Resident E3268 3.97e-06 2.14e-09 1.70 Nearest Resident ESE 44162.64e-061.46e-091.90Nearest Resident SE 13729.66e-068.16e-091.50 Nearest Resident SSE 15244.18e-065.56e-091.40Nearest Resident S1585 3.91e-06 8.42e-09 1.80 Nearest Resident SSW1979 2.76e-06 6.64e-09 1.90 Nearest Resident SW4230 1.15e-06 1.43e-09 2.00 Nearest Resident WSW 18293.61e-064.03e-091.70 Nearest Resident W2896 7.30e-07 6.01e-10 1.10 Nearest Resident WNW 16462.26e-062.12e-092.90 Nearest Resident NW20611.03e-069.95e-101.50 Nearest Resident NNW 43893.50e-072.97e-101.00 Nearest Garden N7664 3.13e-07 3.00e-10 1.00 Nearest Garden NNE61731.06e-061.42e-091.50 Nearest Garden NE3353 3.84e-06 3.22e-09 2.20 Nearest Garden ENE4927 2.01e-06 9.39e-10 1.60 Nearest Garden E6372 1.35e-06 5.42e-10 1.40 Nearest GardenESE 4758 2.26e-061.21e-091.80Nearest Garden SE 46331.58e-068.97e-101.30 Nearest GardenSSE 7454 3.73e-072.80e-101.10Nearest Garden S2254 2.50e-06 4.94e-09 1.90 FSAR Tale 113 Data On Points Of Interest Near Watts Bar Nuclear Plant Page 2 of 2Sector Distance (eters)Chi-over(s/m3)D-over-Q(1/m2)Terrain Adjustment Factor ilkFeeding FactorNearest Garden SSW1979 2.76e-06 6.64e-09 1.90Nearest Garden SW8100 4.28e-07 4.03e-10 1.80Nearest Garden WSW46678.70e-077.11e-101.50 Nearest Garden W5120 3.03e-07 2.03e-10 1.00Nearest Garden WNW59091.72e-071.05e-101.30 Nearest Garden NW31704.13e-063.50e-101.10 Nearest Garden NNW46023.28e-072.74e-101.00 ilk Cow ESE 67061.35e-066.18e-101.70 0.65ilk Cow SSW 22862.24e-065.20e-091.90 0.65ilk Cow SSW 33531.36e-062.84e-092.00 0.65 FSARTale 1131 Watts Bar Nuclear Plant Indiidual Doses From Gaseous Effluents For 1 Unit itout TPC EffluentPathwayGuidelineLocation Dose Noble Gases Air dose 10 mrad aximum Exposed Individual 1 0.801 mrad/yr Air dose 20 mrad aximum Exposed Individual 1 2.710 mrad/yr Total body 5 mrem aximum Residence 2,3 0.571 mrem/yrIodines/ Particulate Skin 15mrem aximum Residence 2,3 1.540 mrem/yr Bone (critical organ) 15 mrem aximum Real Pathway 49.15 mrem/yr Breakdown of Iodine/Particulate Doses (mrem/yr)

Total Vegetable Ingestion 6.57Inhalation 0.0704GroundContamination 0.0947

Submersion Beef Ingestion 5 Total 0.130 2.28 9.145 mrem/yr Guidelines are defined in Appendix I to 10 CFR Part 50.

1aximum exposure point is at 1250 meters in the ESE sector.

2 Dose from air submersion.

3aximum exposed residence is at 1372 meters in the SE sector.

4aximum exposed individual is a child at 1979 meters in the SSW sector.

5aximum dose location for all rece ptors is 1250 in the ESE sector.

FSAR Tale 11311 Summar of Population Doses THYROIDInfantChildTeenAdultTotalSubmersion1.26e-021.41e-011.28e-015.57e-018.38e-01Ground2.31e-032.59e-022.36e-021.03e-011.54e-01Inhalation 6.62e-021.24e006.64e-012.36e004.33e-00 Cow ilk Ingestion 3.22e-011.57e006.63e-011.25e003.81e00Beef Ingestion 0.00e003.17e-011.59e-018.04e-011.28e00 VegetableIngestion 0.00e001.04e004.16e-011.09e002.55e00Total man-rem 4.04e-014.34e002.05e006.17e001.30e01 TOTAL BODY InfantChildTeenAdultTotalSubmersion1.26e-021.41e-011.28e-015.57e-018.38e-01Ground2.31e-032.59e-022.36e-021.03e-011.54e-01Inhalation 3.93e-031.05e-016.65e-022.76e-014.52e-01 Cow ilk Ingestion 1.04e-015.73e-012.17e-013.85e-011.28e00Beef Ingestion 0.00e003.06e-011.53e-017.74e-011.23e00 VegetableIngestion 0.00e001.05e004.40e-011.21e002.70e00Total man-rem 1.23e-012.20e001.03e003.31e006.66e00 Completion and peration of Watts Bar Nuclear Plant Unit 2FSEIS Tale 31 Receptors from Actual Land Use Sure Results Used for Potential Gaseous Releases From WBN Unit 2 ReceptorNumer ReceptorTpe Sector Distance meters1.Nearest Resident N21342.Nearest Resident NNE36003.Nearest Resident NE33534.Nearest Resident ENE24145.Nearest Resident E32686.Nearest Resident ESE44167.Nearest Resident SE13728.Nearest Resident SSE15249.Nearest Resident S158510.Nearest Resident SSW 197911.Nearest Resident SW423012.Nearest Resident WSW182913.Nearest Resident W289614.Nearest Resident WNW164615.Nearest Resident NW206116.Nearest Resident NNW 438917.Nearest Garden N766418.Nearest Garden NNE617319.Nearest Garden NE335320.Nearest Garden ENE492721.Nearest Garden E637222.Nearest Garden ESE475823.Nearest Garden SE463324.Nearest Garden SSE745425.Nearest Garden S225426.Nearest Garden SSW 197927.Nearest Garden SW810028.Nearest Garden WSW466729.Nearest Garden W512030.Nearest Garden WNW590931.Nearest Garden NW317032.Nearest Garden NNW 460233.ilk Cow ESE670634.ilk Cow SSW 228635.ilk Cow SSW 335386Final Supplemental Environmental Impact Statement Chapter 3 FSEIS Tale 32 WBN Total annual Gaseous discarge Per Operating Unit curiesearreactor Nuclide Containment BuildingAuiliar BuildingTurine Building Totalr-85m 3.72E004.53E001.23E009.48E00r-856.69E027.05E001.86E006.78E02r-874.48E-014.27E001.09E005.81E00r-883.10E007.95E002.13E001.32E01Xe-131m 1.07E031.73E014.53E001.09E03Xe-133m 4.07E011.90E005.21E-014.31E01Xe-133 2.82E036.70E011.77E012.90E03Xe-135m 2.26E-023.68E009.80E-014.68E00Xe-135 5.83E012.40E016.46E018.88E01Xe-137 3.76E-049.67E-012.58E-011.23E00Xe-138 1.69E-023.42E009.06E-014.34E00Ar-413.40E010.00E000.00E003.40E01Br-848.16E-075.02E-024.81E-045.07E-02I-1316.74E-031.39E-017.08E-031.53E-01I-1321.36E-046.56E-011.70E-026.73E-01I-1332.36E-034.35E-012.03E-024.57E-01I-1344.26E-051.06E001.47E-021.07E00I-1358.80E-048.10E-013.13E-028.42E-01-31.39E020.00E000.00E001.39E02-3 (TPC) 3.70E020.00E000.00E003.70E02Cr-519.21E-055.00E-040.00E005.92E-04n-54 5.30E-053.78E-040.00E004.31E-04Co-578.20E-060.00E000.00E008.20E-06Co-582.50E-042.29E-020.00E002.32E-02Co-602.61E-058.71E-030.00E008.74E-03Fe-592.70E-055.00E-050.00E007.70E-05Sr-891.30E-042.85E-030.00E002.98E-03Sr-905.22E-051.09E-030.00E001.14E-03r-954.80E-081.00E-030.00E001.00E-03Nb-951.80E-052.43E-030.00E002.45E-03Ru-1031.60E-056.10E-050.00E007.70E-05Ru-1062.70E-087.50E-050.00E007.50E-05Sb-1250.00E006.09E-050.00E006.09E-05Cs-1342.53E-052.24E-030.00E002.27E-03Cs-1363.21E-054.80E-050.00E008.01E-05Cs-1375.58E-053.42E-030.00E003.48E-03Ba-1402.30E-074.00E-040.00E004.00E-04Ce-1411.30E-052.64E-050.00E003.95E-05C-142.80E004.50E000.00E007.30E00Final Supplemental Environmental Impact Statement 87 Chapter 3 A tabulation of the resulting calculated gaseous doses to individuals per operational unit is given in Table 3-21. FSEIS Tale 321 WBN Doses From Gaseous Effluent for Unit 2 Witout Tritium Production for Year 2 EffluentPata GuidelineLocationDose Noble Gases Air dose 10 mrad aximum Exposed Individual 1 0.801 mrad/year Air dose 20 mrad aximum Exposed Individual 1 2.710 mrad/year Total body 5 mrem aximum Residence2,3 0.571 mrem/year Iodines/Particulate Skin15mremaximum Residence2,3 1.540 mrem/year Bone (critical organ) 15 mrem aximum Real Pathway 49.15 mrem/year Breakdown of Iodine/Particulate Doses (mrem/yr) Total Vegetable Ingestion 6.57Inhalation 0.0704Ground Contamination 0.0947Submersion0.130 Beef Ingestion 5 2.28Total9.145Guidelines are defined in Appendix I to 10 CFR Part 50.

1aximum exposure point is at 1250 meters in the ESE sector.

2 Dose from air submersion.

3aximum exposed residence is at 1372 meters in the SE sector.

4aximum exposed individual is a child at 1979 meters in the SSW sector.

5aximum dose location for all receptors is 1250 meters in the ESE Sector.

The estimated annual airborne releases and resulting doses as presented by the 1972 FES, the WBN Unit 1 FSAR, Unit 2, Unit 1 and 2 totals, a nd recent historical data from WBN Unit 1 (as submitted in the Annual Radioactive Effluent Reports to the NRC) with NRC guidelines given in 10 CFR 50 Appendix I are compared in Table 3-22. These guidelines are designed to assure that releases of radioactive material from nuclear power reactors to unrestricted areas during normal conditions, including expected occurrences, are kept as low as practicable.Final Supplemental Environmental Impact Statement 89 , Attachment 2 Response to FSAR Chapter 11 and FSEIS Chapter 3 Request For Additional Information Liquid Source Term Tables (includes in addition to the table from TVA's 2/25/2011 letter (Reference 4), FSEIS Table 3-16, FSAR Tables 11.2-5 and 11.2-7)

Ecerpt from TVA Letter to NRC dated Feruar 2 211 Liquid Source Term Tale from Response to NRC Question 3c Nuclide Single Unit Liquid Radaste CirSingle Unit Steam Generator Blodon Cir Single Unit Totals CirBr-841.65E-045.23E-046.88E-04I-1312.63E-021.14E001.16E00I-1321.32E-021.08E-011.21E-01I-1335.29E-028.57E-019.10E-01I-1346.26E-032.65E-023.28E-02I-1354.75E-024.22E-014.70E-01Rb-886.89E-037.84E-047.68E-03Cs-1342.93E-021.68E-011.98E-01Cs-1362.55E-031.72E-021.98E-02Cs-1374.03E-022.21E-012.61E-01Na-241.86E-020.0E001.86E-02Cr-517.03E-039.27E-029.98E-02n-54 4.99E-035.10E-025.59E-02Fe-558.09E-030.0E008.09E-03Fe-592.42E-039.05E-031.15E-02Co-582.20E-021.44E-011.66E-01Co-601.44E-021.72E-023.16E-02n-653.82E-040.0E003.82E-04Sr-891.92E-044.33E-034.52E-03Sr-902.20E-053.88E-044.10E-04Sr-912.84E-042.18E-032.47E-03-91m1.68E-040.0E001.68E-04-919.00E-053.00E-043.90E-04-931.27E-030.0E001.27E-03r-951.39E-031.20E-021.34E-02Nb-952.10E-038.98E-031.11E-02o-99 4.20E-039.95E-021.04E-01Tc-99m3.35E-030.0E003.35E-03Ru-1035.88E-030.0E005.88E-03Ru-1067.63E-020.0E007.63E-02Te-129m1.41E-040.0E001.41E-04Te-1297.30E-040.0E007.30E-04Te-131m8.05E-040.0E008.05E-04Te-1312.03E-040.0E002.03E-04Te-1321.11E-032.93E-023.05E-02Ba-1401.02E-023.48E-013.58E-01La-1401.62E-024.98E-015.14E-01Ce-1413.41E-040.0E003.41E-04Ce-1431.53E-030.0E001.53E-03Ce-1446.84E-031.26E-011.33E-01Np-2391.37E-030.0E001.37E-03-31.25E030.0E001.25E03 Totals o H33E1EETotals H 312E3E12E3 FSEIS Tale 31 WBN Total Annual DiscargeLiquid Waste Processing Sstem for To Unit Operation Nuclide 1 Unit LRW 1 1 Unit SGB 2 1 Unit Totals 2 Unit TotalsBr-84 1.65E-04 5.23E-04 6.88E-04 1.38E-03 I-131 2.63E-02 1.14E00 1.16E00 2.33E00 I-132 1.32E-02 1.08E-01 1.21E-01 2.43E-01 I-133 5.29E-02 8.57E-01 9.10E-01 1.82E00 I-134 6.26E-03 2.65E-02 3.28E-02 6.55E-02 I-135 4.75E-02 4.22E-01 4.70E-01 9.39E-01 Rb-88 6.89E-03 7.84E-04 7.68E-03 1.54E-02 Cs-134 2.93E-02 1.68E-01 1.98E-01 3.95E-01 Cs-136 2.55E-03 1.72E-02 1.98E-02 3.96E-02 Cs-137 4.03E-02 2.21E-01 2.61E-01 5.23E-01 Na-24 1.86E-02 0.0E00 1.86E-02 3.72E-02 Cr-51 7.03E-03 9.27E-02 9.98E-02 2.00E-01 n-54 4.99E-03 5.10E-02 5.59E-02 1.12E-01 Fe-55 8.09E-03 0.0E00 8.09E-03 1.62E-02 Fe-59 2.42E-03 9.05E-03 1.15E-02 2.29E-02 Co-58 2.20E-02 1.44E-01 1.66E-01 3.31E-01 Co-60 1.44E-02 1.72E-02 3.16E-02 6.32E-02 n-65 3.82E-04 0.0E00 3.82E-04 7.65E-04 Sr-89 1.92E-04 4.33E-03 4.52E-03 9.03E-03 Sr-90 2.20E-05 3.88E-04 4.10E-04 8.19E-04 Sr-91 2.84E-04 2.18E-03 2.47E-03 4.94E-03 -91m 1.68E-04 0.0E00 1.68E-04 3.37E-04 -91 9.00E-05 3.00E-04 3.90E-04 7.80E-04 -93 1.27E-03 0.0E00 1.27E-03 2.54E-03 r-95 1.39E-03 1.20E-02 1.34E-02 2.68E-02 Nb-95 2.10E-03 8.98E-03 1.11E-02 2.22E-02 o-99 4.20E-03 9.95E-02 1.04E-01 2.07E-01 Tc-99m 3.35E-03 0.0E00 3.35E-03 6.70E-03 Ru-103 5.88E-03 0.0E00 5.88E-03 1.18E-02 Ru-106 7.63E-02 0.0E00 7.63E-02 1.53E-01 Te-129m 1.41E-04 0.0E00 1.41E-04 2.82E-04 Te-129 7.30E-04 0.0E00 7.30E-04 1.46E-03 Te-131m 8.05E-04 0.0E00 8.05E-04 1.61E-03 Te-131 2.03E-04 0.0E00 2.03E-04 4.06E-04 Te-132 1.11E-03 2.93E-02 3.05E-02 6.09E-02 Ba-140 1.02E-02 3.48E-01 3.58E-01 7.16E-01 La-140 1.62E-02 4.98E-01 5.14E-01 1.03E00 Ce-141 3.41E-04 0.0E00 3.41E-04 6.81E-04 Ce-143 1.53E-03 0.0E00 1.53E-03 3.05E-03 FSEIS Tale 31 continued Nuclide 1 Unit LRW1 1 Unit SGB2 1 Unit Totals 2 Unit TotalsCe-1446.84E-031.26E-011.33E-012.66E-01Np-2391.37E-030.0E001.37E-032.75E-03-31.25E030.0E001.25E032.51E03-3 (TPC) 3.33E030.0E003.33E034.58E03Totals o H3 3E1EETotals H3 12E312E322E3Total H3 TPC3333E3333E3E3 1 Liquid Radwaste 2Steam Generator Blowdown 3Tritium Production Core (single unit)

FSAR Tale 112 Total Annual Discarge Liquid Waste Processing Sstem Annual Discarge Ci After Processing Total Releases Per Unit TPC Unit 1 Onl Page 1 of 3 Column 1 Column 2 Column 3 Column 4 Column 5 Column 6 Column 7 Column 8 CD Condensate Polishing Demineralizer, D obile Demineralizer TER PERATINAL DES EXPECTED PERATIN D DF CVCS DF SGB processedSGB processed LRWSGB with Column 6 by CD by CD and D No SGBno CD process and Column 7 Br-84100050 0.0003696 0.000165534 1.65E-045.23E-046.88E-04I-131100050 0.471244 0.0267889 2.63E-021.14E001.16E00I-132100050 0.055475 0.01319732 1.32E-021.08E-011.21E-01I-133100050 0.388058 0.0531932 5.29E-028.57E-019.10E-02I-134100050 0.0166222 0.00627256 6.26E-032.65E-023.26E-03I-135100050 0.212508 0.047673 4.75E-024.22E-014.70E-01Rb-8810002 0.0071992 0.006893007 6.89E-037.84E-047.68E-03Cs-134 1000 20.095136 0.02934186 2.93E-021.68E-011.98E-01Cs-136 1000 20.0092913 0.00255804 2.55E-031.72E-021.98E-02Cs-137 1000 20.126735 0.04035147 4.03E-022.21E-012.61E-01Na-24100050 0.089752 0.01867315 1.86E-020.00E001.86E-02Cr-51100050 0.0432857 0.00706196 7.03E-039.27E-029.98E-02n-54 1000 500.0249083 0.0050082 4.99E-035.10E-025.59E-02Fe-55 1000 500.0232248 0.00810991 8.09E-030.00E008.09E-03Fe-59 1000 500.0059574 0.002422938 2.42E-039.05E-031.15E-02Co-5810050 0.078189 0.0225906 2.20E-021.44E-011.66E-01Co-60100050 0.021121 0.014406681 1.44E-021.72E-023.16E-02n-65 1000 500.0065754 0.000388573 3.82E-040.00E003.82E-04 FSAR, Table 11.2-5 Total Annual Discharge Liquid Waste Processing System Annual Discharge (Ci) After Processing Total Releases Per Unit (TPC Unit 1 Only)*** (Page 2 of 3) Column 1 Column 2 Column 3 Column 4 Column 5 Column 6 Column 7 Column 8 CD = Condensate Polishing Demineralizer, MD = Mobile Demineralizer OTHER OPERATIONAL MODES EXPECTED OPERATION MD DF CVCS DF SGB processed SGB processed LRW SGB with Column 6 by CD by CD and MD No SGB no CD process and Column 7 Sr-89 1000 50 0.0018825 0.000193215 1.92E-044.33E-034.52E-03Sr-90 1000 50 0.0001736 2.21026E-05 2.20E-053.88E-044.10E-04Sr-91 1000 50 0.0011378 0.000284704 2.84E-042.18E-032.47E-03Y-91m 1000 50 0.0006694 0.000168895 1.68E-040.00E+001.68E-04Y-91 1000 50 0.0002072 9.00858E-05 9.00E-053.00E-043.90E-04Y-93 1000 50 0.0051829 0.001273833 1.27E-030.00E+001.27E-03Zr-95 1000 50 0.0060943 0.001395024 1.39E-031.20E-021.34E-02Nb-95 1000 50 0.0056138 0.002108301 2.10E-038.98E-031.11E-02Mo-99 1000 500.0430858 0.00423469 4.20E-039.95E-021.04E-01Te-99m 1000 50 0.0386898 0.00338514 3.35E-030.00E+003.35E-03Ru-103 1000 50 0.0975742 0.00597589 5.88E-030.00E+005.88E-03Ru-106 1000 50 1.184324 0.077432 7.63E-020.00E+007.63E-02Te-129m 1000 50 0.0023849 0.000143146 1.41E-040.00E+001.41E-04Te-129 1000 50 0.0030182 0.000732508 7.30E-040.00E+007.30E-04Te-131m 1000 50 0.0056795 0.000809335 8.05E-040.00E+008.05E-04Te-131 1000 50 0.0011229 0.00020385 2.03E-040.00E+002.03E-04Te-132 1000 50 0.0125817 0.00112321 1.11E-032.93E-023.05E-02Ba-140 1000 50 0.14614560.01038151.02E-023.48E-013.58E-01 FSAR, Table 11.2-5 Total Annual Discharge Liquid Waste Processing System Annual Discharge (Ci) After Processing Total Releases Per Unit (TPC Unit 1 Only)*** (Page 3 of 3) Column 1 Column 2 Column 3 Column 4 Column 5 Column 6 Column 7 7Column 8 CD = Condensate Polishing Demineralizer, MD = Mobile Demineralizer OTHER OPERATIONAL MODES EXPECTED OPERATION MD DF CVCS DF SGB processed SGB processed LRW SGB with Column 6 by CD by CD and MD No SGB no CD process and Column 7 La-140 1000 50 0.2108406 0.0164352 1.62E-024.98E-015.14E-01Ce-141 1000 50 0.0021085 0.000342306 3.41E-040.00E+003.41E-04Ce-143 1000 50 0.0114277 0.00153622 1.53E-030.00E+001.53E-03Ce-144 1000 50 0.0560926 0.00689185 6.84E-031.26E-01 1.33E-01Np-239 1000 50 0.0135434 0.00138559 1.37E-030.00E+001.37E-03H3 (TPC) 1 1 1252.80 (3326.4)1252.80 (3326.4) 1257.64 (3326.4) Unplanned Releases** 0.160.160.160.16Total (w/o H3) w/unplanned 3.5252328 3.6850.4416449 0.602 0.438 0.598 4.402 2 4.84 5.000 Total (w/H3) w/unplanned 1256.33 (3329.93)1256.49 (3330.09) 1253.24 (3326.84)1253.40 (3327.00) 1257.64 (3331.24) 1257.80 (3331.40)

FSAR Tale 112 Total Annual Discarge Liquid Waste Processing Sstem Annual Discarge Ci After Processing Total Releases Per Unit TPC Unit 1 Onl Notes (TPC) The values within the parentheses () represent the tritium values due to the Tritium Production Core. Total Release Tank CVCS /D DF LST TB cond. demin/D DF CVCS DF D obile Demineralizer (Processes Tanks, CVCS) DF Decontamination Factor CVCS DF Decontamination Factor of CVCS prior to treatment with D. Cond. demin. condensate demineralizer regeneration waste 0.16 Ci/yr is the unplanned release from NUREG-0017 Column 1 Source term isotopes Column 2 Decontamination factors for the obile Demineralizer Column 3 CVCS Demineralizer decontamination factors Column 4 ((AB/C)/D) E F/ G Column 5 ((AB/C)/D) E F//D G Column 6 ((AB/C)/D) E F G Column 7 Column 8 ((AB/C)/D) E G (See below definition for items A thru A (Ci/yr) Reactor Coolant Drain Tank Tritiated Drain Collector Tank Floor Drain Collector Tank B (Ci/yr) Chemical Volume Control System (CVCS) Letdown C CVCS Demineralizer decontamination factor D obile Demineralizer decontamination factor E(Ci/yr) Laundry and ot Shower Drain Tank F (Ci/yr) Condensate Demineralizer flow (Condensate flow Steam Generator Blow Down six day collection volume) G(Ci/yr) Turbine Building drains CondensateDemineralizer decontamination factors (2 for Rb-88, Cs-134,-136, -137, 10 for all other isotopes-ref. 1) (Ci/yr) Steam Generator Blow down at max allowable untreated concentration of 3.65E-5 uCi/cc. This calculated value is based on an average of 365 days but does not represent a constraint on the plant since the actual value for individual releases may be greater. owever, the total of all yearly releases must remain 5CI

.

FSAR Tale 112 Watts Bar Nuclear Plant Doses from Liquid Effluents For Year 2 Indiidual Dose mrem Adult Total Body 0.72 Bone 0.56GI Tract 0.132 Thyroid 0.88 Liver 0.96 idney 0.352Lung 0.136Skin 0.031 Teen Total Body 0.44 Bone 0.60GI Tract 0.104 Thyroid 0.80 Liver 1.00 idney 0.356Lung 0.152Skin 0.031Cild Total Body 0.188 Bone 0.76GI Tract 0.06 Thyroid 0.92 Liver 0.88 idney 0.312Lung 0.128Skin 0.031 Infant Total Body 0.032 Bone 0.036GI Tract 0.033 Thyroid 0.264 Liver 0.036 idney 0.034Lung 0.032Skin 0.031Population Dose PersonremTotal Bod 1.619 Bone 1.761 GI Tract 1.420 Thyroid 15.336 Liver 2.130 idney 1.392 Lung 1.037 Skin 0.315 Response to FSAR Chapter 11 and FSEIS Chapter 3 Request For Additional Information FSAR Chapter 11 and FSEIS Chapter 3 Changes Attachment 1 - Summary of Proposed Changes to FSAR and FSEIS Text and TablesAttachment 2 - Proposed Markups for FSAR Chapter 11, Text and Tables Attachment 3 - Proposed Clean Copy of FSAR Sections 11.1, 11.2 and 11.3 - Proposed Markups for FSEIS Chapter 3 Attachment 5 - Proposed Clean Copy of FSEIS Chapter 3 , Attachment 1 Response to FSAR Chapter 11 and FSEIS Chapter 3 Request For Additional Information Summary of Proposed Changes to FSAR and FSEIS Text and Tables ENCLOSURE 2 ATTACHMENT 1 WATTS BAR NUCLEAR PLANT UNIT 2

SUMMARY

OF PROPOSED CHANGES TO FSAR CHAPTER 11 AND FSEIS CHAPTER 3 The following provides a summary of proposed changes to the Watts Bar Unit 2 Final Safety Analysis Report and Final Supplemental Environmental Impact Statement (FSEIS). The changes described in this enclosure are for the primary changes resulting from discussions with the NRC, review of the NRC Requests for Additional Information (RAIs) and review of the results of an independent third party assessment of the Watts Bar Unit 2 licensing documentation. Additional minor changes may have been made to provide clarity or correct inconsistencies. This summary document was developed to provide an overview of changes that have been made to FSAR sections and tables and FSEIS Tables. Two of the primary issues addressed are Feeding Factors and Terrain Adjustment Factors. Accordingly, a summary of these issues including the TVA resolution to address them, are specifically addressed below.

Feeding Factors NRC staff review of the operating license application for Watts Bar Nuclear Plant (WBN) Unit 2 discovered inconsistencies in the usage of feeding factors amongst various TVA documents.

The feeding factor inconsistency and the value itself are questioned in several NRC RAIs on Chapter 11 of the Unit 2 FSAR. Regulatory guidance concerning feeding factors is found in Regulatory Guide 1.109 Ref. 1, and NUREG/CR-4653 Ref. 2. These documents provide guidance on determination of annual doses. The dose equations used to calculate annual doses include the feeding factor. The documents encourage the use of site-specific values. owever, to use site-specific values, the guidance indicates that the assumptions and methods used to obtain these values should be fully described and documented. These site-specific values are typically based on data collected during annual land use surveys performed by the licensee. NUREG/CR-4653 provides default values that may be used in lieu of site-specific information provided in the annual land use census report. NUREG/CR-4653 provides a figure that determines the feeding factors based on pasture growing seasons. Assuming the cattle feed completely on pasture grass while on pasture, the feeding factor is in the range of 0.58 to 0.67 (7 to 8 months per year). TVA has determined that a feeding factor value of 0.65 based on NUREG/CR-4653 "GASPAR II Technical Reference and User Guide," 1987 will be used. Changes to Table 11.3-8 and 11.3-10 have been proposed to reflect the use of the revised feeding factor.

REFERENCES1. Regulatory Guide 1.109, "Calculation of Annual Doses to an from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Rev. 1, ctober 1977. 2. NUREG/CR-4653 "GASPAR II Technical Reference and User Guide," 1987. Terrain Adjustment FactorsThe NRC has always been cognizant and recognized the potential need to account for the impact of terrain effects on meteorological dispersion. A terrain correction factor need be applied only if the spatial and temporal variations in the airflow in the site vicinity would result in an underestimate of the annual average /Q value.

ENCLOSURE 2 ATTACHMENT 1 WATTS BAR NUCLEAR PLANT UNIT 2

SUMMARY

OF PROPOSED CHANGES TO FSAR CHAPTER 11 AND FSEIS CHAPTER 3 In a letter dated February 27, 1985, the NRC raised concerns regarding TVAs justification for use of a straight-line dispersion model without adjustment factors in the calculation of annual average atmospheric dispersion (/Q) values presented in the draft Watts Bar ffsite Dose Calculation anual (DC) Ref. 1. The NRC presented two options (1) adopt /Q values calculated by NRC using default adjustment factors or (2) provide a quantitative assessment of adjustments to the straight-line trajectory mode The NRC described a method that other applicants and licensees used to develop site-specific adjustment factors. In those cases, the annual average /Q values are calculated using an appropriate variable-trajectory model with hourly meteorological data for a representative one year period and compared with those calculated using the straight-line model using the same data base. The results of the straight- line model (/Q and D/Q) are adjusted using a multi-year data base and the ratios generated by the comparison of the variable-trajectory and straight-line models.TVA developed a methodology to compare the results of TVA's GELC code with results from the ESPUFF II model. ESPUFF II is a regional scale, variable trajectory, Gaussian puff model. ESPUFF II simulates the deformation of a continuous plume by temporarily varying the wind field. TVA developed site-specific adjustment factors for the WBN site by comparing results from the GELC model with results from the ESPUFF II model. TVA will continue to use the methodology described in TVA Report TVA/NRED/AWR--87/24 Ref. 2. GELC will continue to be used with terrain adjustment factors based on comparison to ESPUFF II. This approach retains existing licensing commitments for WBN Unit 1 and utilizes methodology that has been accepted by the NRC.

REFERENCES 1. Letter, Elinor G. Adensam NRC to . G. Parris TVA, "Comments on the Proposed ffsite Dose Calculation anual (DC) - Watts Bar Units 1 and 2," February 27, 1985. 2. TVA Report TVA/NRED/AWR-87/24, "The Development of /Q Adjustment Factors for Potential Use in Routine Calculation of Annual Average /Q Values in the Watts Bar Nuclear Plant ffsite Dose Calculation anual," 1987.

ENCLOSURE 2 ATTACHMENT 1 WATTS BAR NUCLEAR PLANT UNIT 2

SUMMARY

OF PROPOSED CHANGES TO FSAR CHAPTER 11 AND FSEIS CHAPTER 3 FSAR Section 11121. Clarification was provided to assure that it was clear the Tritium Producing Burnable Absorber Rods are only applied to Watts Bar Unit 1. FSAR Section 1111. Clarification was provided to describe when the relief path from steam generator blowdowns to the river via the cooling tower blowdown line is used. The following text was added "This route is used primarily during periods when there is no significant primary to secondary leakage." FSAR Section 112 and Tales 112 112a 112 and 112dThe previous FSAR Section 11.2.6.5 has been replaced with new Sections, 11.2.6.5, 11.2.6.5.1 and 11.2.6.5.2. The primary results of these revisions are described below. 1. The text has been revised to describe Table 11.2.5 columns that have been modified. Columns 6, 7 and 8 of this table have been revised. Column 6 provides the liquid radioactive waste source term. Column 7 provides the source term for steam generator blowdown assuming an annual untreated SG Blowdown concentration of 3.65E-5 uCi/cc. Column 8 is the combined source term from Column 6 and 7. In addition, FSAR Sections 11.2.6.5, 11.2.6.5.1 and 11.2.6.5.2 have been revised to assure the text describes the columns in Table 11.2.5. 2. The text has been revised to describe the untreated steam generator blowdown.

3. The text has been revised to discuss Tables 11.2-5a, 11.2-5b, and 11.2-5d. This description includes the steps taken to prevent exceeding 10 CFR Part 20.1302(b) limits. 4. The text has been revised to describe the scenarios associated with the columns presented in Table 11.2-5. 5. The text states the rationale and acceptability of operating without Condensate Demineralizer backwash and blowdown effluent considerations as long as primary-to-secondary leakage is insignificant. 6. Table 11.2-5c has been deleted due to the clarifications incorporated into Section 11.2.6.5. FSAR Section 11211. This section has been revised to reflect the use of a 1.42 growth factor based on the 2000 census, rather than 1.24 factor based on the 1990 census. FSAR Section 1131. Revised the table cited from "11.3-10" to "11.3-7" ENCLOSURE 2 ATTACHMENT 1 WATTS BAR NUCLEAR PLANT UNIT 2

SUMMARY

OF PROPOSED CHANGES TO FSAR CHAPTER 11 AND FSEIS CHAPTER 3 FSAR Section 1131. Clarification has been added to describe the basis for Table 11.3-7c (the basis is ANSI N18.1-1984).FSAR Tale 1131. This table has been revised to more accurately describe the use of a continuous filtered containment vent. 2. Item 2 was revised to state that the activities are based on ANSI N18.1-1984. FSAR Tale 113c1. The table has been revised to demonstrate it was based on ANSI 18.1-1984 and to delete Tritium Production Core value for -3 (Unit 1 only). FSAR Section 1131. The description of the Turbine Building vents was revised to describe that non-radioactive ventilation air is exhausted from the Turbine Building rather than "ventilation air". Tale 1131. TVA verified the validity of the land census used in FSAR Table 11.3-8. 2. The distance, /Q and D/Q were revised to be consistent with the Terrain Adjustment Factor determined using the methodology established in TVA/NRED/AWR--87/24. The table provides the Terrain Adjustment Factor used for each point of interest. 3. The Feeding Factors were revised to reflect the growing season. The table provides the Feeding Factor used for each point of interest. FSAR Section 1131. The Section has been revised to identify the date of the land-use census that is used and discusses the rationale and assumptions for the information used. 2. The section was revised to describe that TAFs, /Q and D/Q were calculated for the locations based on the 2007 Land Use Survey and 1984 through 2005 meteorology data.

Reference is made to table 11.3-8 which provides the Terrain Adjustment Factor used for each point of interest. 3. Additional text was added describing that the computer code GELC was used with terrain adjustment factors to account for recirculation effects. FSAR Section 113111. The Section has been revised to identify the feeding factor that TVA has used and to provide the basis for its use. The tables cited at the end of the section have changed from "11.3-10 and 11.3-11" to "11.3-11 to 11.3-12". New text has been added to the end of the section describing the vegetable ingestion is the critical pathway.

ENCLOSURE 2 ATTACHMENT 1 WATTS BAR NUCLEAR PLANT UNIT 2

SUMMARY

OF PROPOSED CHANGES TO FSAR CHAPTER 11 AND FSEIS CHAPTER 3 FSAR Section 113121. The section has been revised to update the annual total body dose for the population expected to live within a 50 mile radius of Watts Bar in the year 2040. It also revises the total body dose from effluents. Tale 1131. This table has been revised to ensure consistency with other sections of the FSAR and the FSEIS. Population dose calculations have been revised. Tale 11311. The individual doses listed in Table 11.3-10 were determined using each nuclide's total curies/year listed in Table 11.3-7c with Continuous Filtered Containment Vent. 2. The doses were revised to incorporate the latest parameters including use of updated Feeding Factor and Terrain Adjustment Factors. Tale 113111. This table has been revised to describe the results of TVA's estimate of the radiological impact to regional population groups in the year 2040 from the normal operation of the Watts Bar Nuclear Plant. FSEIS Tale 311. FSEIS Table 3-19 was revised for receptor locations based on the 2007 Land Use Survey and is consistent with FSAR Table 11.3-8. FSEIS Tale 321. FSEIS Table 3-20 was revised to use the source term associated with Continuous Filtered Containment Vent. FSEIS Tale 3211. The doses were revised to incorporate the latest parameters including use of updated Feeding Factors and Terrain Adjustment Factors. FSEIS Tale 3221. Table 3-22 has been revised to reflect the comparison of Annual Releases from Unit 1 and Unit , Attachment 2 Response to FSAR Chapter 11 and FSEIS, Chapter 3 Request For Additional Information Proposed Markups for FSAR Chapter 11, Text and Tables 11.1-2SOURCE TERMS WATTS BARWP-13B = boron concentration reduction rate by eed and bleed, ppm per sec. = remoal eiciency o puriication cycle or nuclide = radioactie decay constant = escape rate coeicient or diusion into coolantt = elapsed time (seconds) since the beginning o cycle subscriptsC = reers to core w = reers to coolant i = reers to parent nuclide = reers to daughter11.1.1.2 olume Control Tan istorical Design ActiityTable 11.1-3 lists the actiities in the olume control tan us ing the assumptions summarized in Table 11.1-1. 11.1.1.3 Pressurier istorical Design ActiityThe actiities in the pressurizer are separated between the liuid and the steam phase and the results obtained are gien in Table 11.1-4 using t he assumptions summarized in Table 11.1-1.11.1.1. aseous Waste Processing System istorical Design ActiitiesThe actiities to be ound in the Gaseous Waste Processing System are gien in Table

11.1-5.11.1.1.5 Secondary Coolant istorical Design ActiitiesThe secondary cleanup system design actiities used or shielding design calculations are discussed in Subsection 12.2.1.5.11.1.2 Realistic odel for Radioactiities in Systems and ComonentsThis section and associated Tables 11.1-6 and 11.1-7 present results which supersede the calculations in the preious sections. The Tritium Producing Burnable Absorber Rods (TPBARs) are designed and abricated to retain all the tritium produced within the TPBAR. Since the TPBAR produced tritium is chemically bonded within the TPBAR, irtually no tritium is aailable in a orm that could permeate through the TPBAR cladding. Howeer, it is assumed that while operating with a Tritium Production Core (TPC), some o the tritium inentory in the TPBARs may permeate the cladding Insert(Unit1only) 11.1-4SOURCE TERMS WATTS BARWP-13 (4)Auiliary Building Ventilation System (5)Turbine Building Ventilation System (6)Steam Generator Blowdown SystemEstimates or the release o radioactie materials rom sources 1 through 5 (aboe) are presented in Section 11.3.7. The release paths and transport mechanism or these sources o radioactie material are also presented in Section 11.3.8.The Steam Generator Blowdown System (SGBS) is another source o liuid radioactie material that is not normally considered part o the radioactie waste system. The system description, release paths, and low rates are presented in Section 11.2 and in Section 10.4.8. The release path that is o concern in ealuating the radiological conseuences o liuid releases rom steam generator blowdowns is the path to the rier ia the cooling tower blowdown line. This route is used primarily during startups, when non-radioactie impurity leels are higher than normal and when SGBS is bypassing the condensate demineralizers. The normal route or the blowdown liuid is to the Turbine Building, where it is cooled, and then routed to either the condensate system upstream o the condensate demineralizers or cooling tower blowdown lines or condenser hotwell. The discharge to the rier is monitored or radioactiity as speciied in Section 11.4. An alarm in the Main Control Room alerts the operator o an increasing radioactiity leel in the discharge. I the radiation setpoint is eceeded, the blowdown discharge is automatically dierted to the condensate demineralizers. The basis or the setpoint is presented in Section 11.4.

References (1)ANSI/ANS-18.1-1984, Radioactie Source Term For Normal Operation o Light Water Reactors, December 31, 1984.

(2)WCAP-8253, Source Term Data or Westinghouse Pressurized Water Reactors, Westinghouse Electric Corp oration, Pittsburgh, Pa. 15230, April 1974.(3)WCAP-7664, R1 Radiation Analysis Design Manual Loop Plant, October 1972.Replacethetwosentenceswiththefollowingsentence:"Thisrouteisusedprimarilyduringperiodswhenthereisnosignificantprimarytosecondaryleakage."

11.2-18U WASTE SSTEMS WATTS BARWP-1311.2...2 DescritionThe TB drains are not normally radioactie.The Turbine Building drainage consists o the ollowing categories

()Condensate Polishing Demineralizer System Drains

()Other TB drainage

()Oil and oily water drainage.11.2...2.1 Condensate Polishing Demineralier System DrainsThe Condensate Polishing Demineralizer System (CPDS) area is sericed by separate loor and euipment drains. The drains or CPDS are routed to the Condensate Demineralizer sump where they are pumped to the Neutralization Tan (NT). These drains hae a potential to be low-leel radioactie during periods o primary to secondary leaage. The NT is proided with the capability o adusting pH, and i the inentory is not radioactie or less th an the dischargeable limit , it is normally discharged with a batch release to the CTB line. The NT is normally processed by a endor i the inentory is aboe dischargeable limits. Any radioactie discharge rom this release point is handled in accordance with the ODCM. Section 10.4.6 discusses the CPDS, and this chapter discusses the wastes rom the system and their disposal under radioactie and non-radioactie conditions.11.2...2.2 Other Turbine uilding DrainageDrainage rom the Turbine Building areas other than the CPDS area is directed to the yard holding pond, normally, ia the low olume waste treatment (LVWT) pond. Floor and euipment drainage in Turbine Building is irst collected in the Turbine Building Station sump and is then pumped to the yard holding pond, normally, ia the LVWT pond. Roo drainage lows by graity directly to the yard holding pond.11.2...2.3 Oil and Oily Water Drainage Oil is drained directly to drums or tan trucs or reuse or remoal rom the plant. Oily water drains are urnished in the Turbine Building and are routed to the oil sump which is located in the low point o the Turbine Building. Oil may be accumulated in the sump until a suicient amount is collected to be pumped into tan trucs or osite disposal.11.2..5 stimated Total Liquid ReleasesThe potential releases hae been ealuated as indicated in the aboe sections. The epected liuid releases rom Watts Bar are well below the limit o 5 Curies (Ci) per year as prescribed in 10 CFR 50, Appendi I as shown by the alues gien in column 4 and 5 o Table 11.2-5. Column 6 (no CD processing) indicates a yearly release o 30.03 Ci with no Condensate Demineralizer (CD) processing o waste and no limitations on steam generator blow down concentrations. This operational mode is not normally used since long term use results in eceeding the 5 Ci/yr limit in 10 CFR 50, Appendi I. Column 7 o Table 11.2-5 indicates that the total release, including ReplaceSection11.2.6.5withthe insertfromthe followingpage.

U WASTE SSTEMS 11.2-19WATTS BARWP-13untreated steam generator blow down, is signiicantly below the 10 CFR 50, Appendi I limit o 5 Ci/yr i the steam generator blow down concentration is restricted to the Lower Limit o Detection (LLD) o 5E-7 uCi/cc gross gamma during the release and no other Condensate Demineralizer waste is processed during the release. Howeer, column 7 does include other releases rom waste holdup tans which are treated using the Mobile Demineralizers. Column 8 o Table 11.2-5 indicates steam generator blow down can be released untreated and remain within the 10 CFR 50, Appendi I limit o 5 Ci/yr i the Steam Generator Blow down concentration is restricted to a maimum concentration o 3.65E-5 uCi/cc gross gamma during the release and no other Condensate Demineralizer waste is processed during the release. Howeer, column 8 does include other releases rom waste holdup tans which are treated using the Mobile Demineralizers.Tables 11.2-5a, 11.2-5b, 11.2-5c, and 11.2-5d describe liuid releases or 1 ailed uel or both treated and untreated waste relatie to the reuirements o 10 CFR 20.1302(b). The sum oer all isotopes o the concentrations/ECL (C/ECL) alue rom the Table 11.2-5a is greater than unity or the case where all isotopes are at design alues and the released liuid is not processed by the Mobile Demineralizers. This mode o operation is not normally used since the C/ECL alue eceeds the reuirements o 10 CFR 20.1302(b). The bul o the release is due to the untreated condensate resin regeneration waste. In order to preent eceeding the 10 CFR 20.1302(b) limits, the condensate regeneration waste is rerouted through the Mobile Demineralizers i the long term releases rom the condensate regeneration waste is greater than the 10 CFR 20 concentration limits. With Mobile Demineralizer processing o condensate regeneration waste, the release co ncentrations are shown in Table 11.2-5b and are less than the limits speciied in 10 CFR 20.1302(b). Table 11.2-5c shows releases remain within the 10CFR 20 limits i the steam generator blow down concentration is restricted to the Lower Limit o Detection (LLD) o 5E-7 uCi/cc gross gamma during the release and no other Condensate Demineralizer waste is processed during the release. Howeer, these releases do include other releases rom waste holdup tans which are treated using the Mobile Demineralizers. Table 11.2-5d shows releases remain within the 10CFR 20 limits i the steam generator blow down concentration is restricted to a maimum concentration o 3.65E-5 uCi/cc gross gamma during the release and no other Condensate Demineralizer waste is processed during the release. Howeer, these releases do include other releases rom waste holdup tans which are treated using the Mobile Demineralizers.Based on the aboe, the releases rom the plant are in accordance with the design obecties as outlined in Section 11.2.1 and the Osite Dose Calculation Manual.11.2. RLAS POTSAll radioactie liuid wastes are released rom the plant through the cooling tower blowdown line. The discharge points rom the waste disposal system are shown in Figure 11.2-1 and 11.2-2. The connection to the cooling tower blowdown line is shown in Figure 10.4-5. ReplaceSection11.2.6.5withthe insertfromthe followingpage.

11.2..5 stimated Total Liquid Releases 10 CFR 50 Appendi I and 10 CFR 20 prescribe the allowable limits o radionuclide liuid releases rom Watts Bar. The Osite Dose Calculation Manual is the process document that describes how releases are measured, monitored, controlled and reported. The liuid waste management system at Watts Bar can be operated in a ariety o conigurations depending on plant conditions and the amount and composition o radionuclides in the waste stream.

Irrespectie o the speciic modes described, the annual releases are reuired to be eual to or less than the limits proided in the ODCM, Appendi I and 10CFR 20. Table 11.2-5 proides the total annual discharge rom the liuid waste processing system or our dierent leels o processing prior to discharge. The annual discharge or Unit 2 is epected to be similar to Unit 1 with the eception that tritium production is not currently planned. A alue o 0.16 Ci/yr is included as an unplanned release in each o the plant alignment to proide conseratism as discussed in NUREG-0017. The discussions to ollow are based on the luid uantities and actiities speciied in Table 11.2-1. 11.2..5.1 ected ormal Plant Oeration The epected plant alignment and the our resultant release paths are as ollows demineralizer. The reactor coolaCVCS letdown waste processed by the CVCS demineralizers and then by the mobile nt drain tan, the tritiated drain collector tan, and the loor drain collector tan discharges and processed using the mobile demineralizer ilding Steam Generator Blowdown released without processing. he results or this alignment are shown in Column 8 o Table 11.2-5. Column 8 is the ned source term rom Column 6 and 7. Column 6 proides the liuid radwaste source wdown assuming an annual ntreated SG Blowdown concentration o 3.65 E-5 uCI/cc. Concentrations aboe this alue 1 8 this set te relatie to the uirements o 10 CFR 20.1302(b). Table 11.2- 5d shows releases remain within the 10CFR Liuid releases rom the Laundry and Hot Shower Drain Tan and the Turbine Budrains can be released without processing by mobile demineralizer. This combination o aboe three paths is called liuid radwaste.

T combi term. Column 7 proides the source term or steam generator blo ucannot be released continuously on an annual basis without additional processing. Unit currently operates without the condensate demineralizers in serice. The condensate demineralizers will not be utilized unless signiicant primary to secondary leaage occurs.

Operating eperience has shown that annual releases are below the alues shown in Column and thus that processing o SG Blowdown is not epected to be reuired. There is no condensate demineralizer blowdown or bacwashing when the plant is operating undero conditions. SG Blowdown concentrations aboe 3.65E-5 uCi/cc can be released without processing by the condensate demineralizers or short periods o time and are acceptable as long as total releases rom the site are below the ODCM and 10 CFR limits. The epected liuid releases rom Watts Bar based on the alues in Column 8 are below thelimit o 5 Curies per year as prescribed in 10 CFR 50, Appendi I. Tables 11.2-5c and 11.2-5d describe liuid releases or 1 ailed uel or both treated and untreated was

reReplaceSection11.2.6.5withfollowingtwopages:

20 limits i the steam generator blow down concentration is restricted to a maimum concentration o 3.65E-5 uCi/cc gross gamma during the release. 11.2..5.2 Other Plant Alignment aluations The alues in Table 11.2-5 Column 4 assume the ollowing demineralizers and then by the mobile demineralizer.ctor tan, and the loor drain collector tan discharges and processed using the mobile demineralizer Condensate Demineralizer Flow including SG Blowdown processed the condensate rom the Laundry and Hot Shower Drain Tan and the Turbine Building drains can be released without processing by mobile demineralizer.

leThe reactor coolant drain tan, the tritiated drain collector tan, and the loor drain by the condensate demineralizer with additional processing by the mobile demineralizer. n Tan and the Turbine Building drains can be released without processing by mobile demineralizer.

lld in 10 CFR 50, Appendi I.

d er all isotopes concentrations/ECL (C/ECL) alue rom the Table 11.2-5a is greater than unity or the imits, the nsate regeneration waste is rerouted through the Mobile Demineralizers i the long term ste, the release oncentrations are shown in Table 11.2-5b and are less than the limits speciied in 10 CFR ased on the aboe, the releases rom the plant are in accordance with the design obecties as CVCS letdown waste processed by the CVCS The reactor coolant drain tan, the tritiated drain colledemineralizer Liuid releases . The alues in Table 11.2-5 Column 5 assume the ollowing CVCS letdown waste processed by the CVCS demineralizers and then by the mobi demineralizer.collector tan discharges and processed using the mobile demineralizer Condensate Demineralizer Flow including SG Blowdown processed Liuid releases rom the Laundry and Hot Shower DraiThe epected liuid releases rom Watts Bar based on the alues in columns 4 and 5 are webelow the limit o 5 Curies per year as prescribeTables 11.2-5a and 11.2-5b describe liuid releases or 1 ailed uel or both treated anuntreated waste relatie to the reuirements o 10 CFR 20.1302(b). The sum o o the case where all isotopes are at design alues and the released liuid is not processed by the Mobile Demineralizers. In order to preent eceeding the 10 CFR 20.1302(b) l condereleases rom the condensate regeneration waste is greater than the 10 CFR 20 concentration limits. With Mobile Demineralizer processing o condensate regeneration wa

c 20.1302(b).

Boutlined in Section 11.2.1 and the Osite Dose Calculation Manual.

11.2-20U WASTE SSTEMS WATTS BARWP-1311.2. DLUTO FACTORSThe dosimetry calculations or drining water are based on the assumption that the liuid eluent will be mied with 10 o the rier low between the point o discharge and Tennessee Rier Mile (TRM) 510.0, where 100 dilution is assumed to occur. Further discussion o these calculations and dilution lows used is presented in section 11.2.9.1. 11.2. STATD DOSS FRO RADOUCLDS LUD FFLUTSDoses rom the ingestion o water, rom the consumption o ish, and rom shoreline recreation are calculated or eposures to radionuclides routinely released in liuid eluents.11.2..1 Assumtions and Calculational ethodsInternal doses are calculated using methods outlined in NRC Regulatory Guide 1.109, Reision 1, October 1977. This model is used or estimating the doses to bone, gastro-intestinal (G.I.) tract, thyroid, lier, idney, lung, sin, and total body o man rom ingestion o water, consumption o ish, and rom eternal eposures due to recreational actiities. Population doses are estimated or the year 2040 based on the populations gien in Table 2.1-12.

(1)Doses to Man rom the Ingestion o WaterData listed in Table 11.2-6 or public water supplies is used to calculate dose commitments rom the consumption o Tennessee Rier water. The 2040 populations or the water supplies are estimated by multiplying the 1990 populations by a population growth actor o 1.24. This actor is the ratio o the 2040 population (Table 2.1-12) to the 1990 population. It is assumed that the plant eluent is mied with one-tenth o the rier low in the 18-mile reach between the nuclear plant site and TRM 510.0. Although natural water turbulence will continue to increase the dispersion downstream, it is assumed that one-tenth dilution is maintained as ar as TRM 510.0, where ull-dilution is assumed.Dilution is calculated using aerage annual low data or the Tennessee Rier as measured during the 69-year period 1899-1968. The aerage low past the site is approimately 28,000 t 3/sec.Radioactie decay between the time o intae in a water system and the time o consumption is handled in accordance with Regulatory Guide 1.109. Maimum and aerage consumption rates are those recommended by Regulatory Guide 1.109.Due to a lac o deinitie data, no credit is taen or remoal o actiity rom the water through absorption on solids and sedimentation, by deposition in the biomass, or by processing within water tre atment systems.Replacewith2000publicwatersupplypopulations byapopulation growthfactorof

1.42.Replacewith2000population(Table2.1-8).

11.2-34U WASTE SSTEMS WATTS BARWP-13Table 11.2-5 Total Annual Discharge Liquid Waste Processing System*Annual Discharge (Ci) After ProcessingTotal Releases Per Unit (TPC Unit 1 Only)*** (Page 1 of 3)Column 1Column 2Column 3Column 4Column 5Column 6Column 7Column 8CD = Condensate Polishing Demineralizer, MD = Mobile DemineralizerMD DFCVCS DFw/o CD process by MDw/CD processing by MDno CD processingno CD process, SGB rel=LLD no CD process, SGB rel=maBr-841000500.00036960.0001655340.002208330.000165330.0001653 I-1311000500.4712440.02678894.4753440.0263440.026344I-1321000500.0554750.013197320.4363550.0131550.013155I-1331000500.3880580.05319323.4048580.0528580.052858I-1341000500.01662220.006272560.10986220.00626220.0062622I-1351000500.2125080.0476731.6975080.0475080.047508Rb-88100020.00719920.0068930070.00750570.00689270.0068927 Cs-134100020.0951360.029341860.1609960.0292760.029276Cs-136100020.00929130.002558040.01603130.00255130.0025513 Cs-137100020.1267350.040351470.2132050.0402650.040265Na-241000500.0897520.018673150.7301020.0186020.018602 Cr-511000500.04328570.007061960.36962570.00702570.0070257Mn-541000500.02490830.00500820.204188280.004988280.0049883Fe-551000500.02322480.008109910.159394780.008094780.0080948 Fe-591000500.00595740.0024229380.03779940.00241940.0024194Co-58100500.0781890.02259060.5836290.0220290.022029Co-601000500.0211210.0144066810.081609960.014399960.0144Zn-651000500.00657540.0003885730.062312380.000382380.0003824ReplacewithInsertA U WASTE SSTEMS 11.2-35WATTS BARWP-13Sr-891000500.00188250.0001932150.017101520.000191520.0001915Sr-901000500.00017362.21026E-050.001537952.1951E-052.195E-05 Sr-911000500.00113780.0002847040.008822850.000283850.0002839 Y-91m1000500.00066940.0001688950.005178390.000168390.0001684 Y-911000500.00020729.00858E-050.001261978.9969E-098.997E-05 Y-931000500.00518290.0012738330.040399920.001269920.0012699Zr-951000500.00609430.0013950240.048430320.001390320.0013903 Nb-951000500.00561380.0021083010.037194790.002104790.0021048Mo-991000500.04308580.004234690.39309580.00419580.0041958Te-99m1000500.03868980.003385140.35674980.00334980.0033498Ru-1031000500.09757420.005975890.92278420.00588420.0058842Ru-1061000501.1843240.07743211.1563240.0763240.076324Te-129m1000500.00238490.0001431460.02258090.00014090.0001409Te-1291000500.00301820.0007325080.023610220.000730220.0007302 Te-131m1000500.00567950.0008093350.049554460.000804460.0008045Te-1311000500.00112290.000203850.009402930.000202930.0002029 Te-1321000500.01258170.001123210.115811740.001111740.0011117Ba-1401000500.14614560.01038151.36924560.01024560.0102456Table 11.2-5 Total Annual Discharge Liquid Waste Processing System*Annual Discharge (Ci) After ProcessingTotal Releases Per Unit (TPC Unit 1 Only)*** (Page 2 of 3)Column 1Column 2Column 3Column 4Column 5Column 6Column 7Column 8CD = Condensate Polishing Demineralizer, MD = Mobile DemineralizerMD DFCVCS DFw/o CD process by MDw/CD processing by MDno CD processingno CD process, SGB rel=LLD no CD process, SGB rel=maReplacewithInsertB 11.2-36U WASTE SSTEMS WATTS BARWP-13La-1401000500.21084060.01643521.96224060.01624060.0162406Ce-1411000500.00210850.0003423060.018020540.000340540.0003405 Ce-1431000500.01142770.001536220.100545720.001525720.0015257Ce-1441000500.05609260.006891850.49934260.00684260.0068426 Np-2391000500.01354340.001385590.123073420.001373420.0013734

H-3 (TPC)111252.80 (3326.4)1252.80 (3326.4)1252.80 (3326.4)1252.80 (3326.4)1252.80 (3326.4)unplanned0.160.160.160.160.16SGBD contribution0.064.402 ****total (w/o H3) w/unplanned3.5252328 3.6850.44164490.602 30.034845330.195 0.50 0.658 4.84 5.000total (w/H3) w/unplanned1256.33 (3329.93)1256.49 (3330.09)1253.24 (3326.84)1253.40 (3327.00)1282.83 (3356.43)1283.00 (3356.60)1253.30 (3326.90)1253.46 (3327.06)1257.64 (3331.24)1257.80 (3331.40)Table 11.2-5 Total Annual Discharge Liquid Waste Processing System*Annual Discharge (Ci) After ProcessingTotal Releases Per Unit (TPC Unit 1 Only)*** (Page 3 of 3)Column 1Column 2Column 3Column 4Column 5Column 6Column 7Column 8CD = Condensate Polishing Demineralizer, MD = Mobile DemineralizerMD DFCVCS DFw/o CD process by MDw/CD processing by MDno CD processingno CD process, SGB rel=LLD no CD process, SGB rel=maReplacewithInsertC LIQUID WASTE SYSTEMS 11.2-35WATTS BARTable 11.2-5 Total Annual Discharge Liquid Waste Processing SystemAnnual Discharge (Ci) After ProcessingTotal Releases Per Unit (TPC Unit 1 Only)*** (Page 1 of 3)Column 1Column 2Column 3Column 4Column 5Column 6Column 7Column 8CD = Condensate Polishing Demineralizer, MD = Mobile DemineralizerOTHER OPERATIONAL MODESEXPECTED OPERATIONMD DFCVCS DFSGB processed by CD S G B processed by CD and MDLRWNo SGBSGB with no CD process Column 6 and Column 7Br-841000500.00036960.0001655341.65E-045.23E-046.88E-04I-1311000500.4712440.02678892.63E-021.14E+001.16E+00I-1321000500.0554750.013197321.3 2E-01.08E-01 1.21 E-01I-1331000500.3880580.05319325.29E-028.57E-019.10E-01I-1341000500.01662220.006272566.26E-032.65E-023.28E-02I-1351000500.2125080.0476734.75E-024.22E-014.70E-01Rb-88100020.00719920.0068930076.89E-037.84E-047.68E-03Cs-134100020.0951360.029341862.93E-021.68E-011.98E-01Cs-136100020.00929130.002558042.55E-031.72E-021.98E-02Cs-137100020.1267350.040351474.03E-022.21E-012.61E-01Na-241000500.0897520.018673151.86E-020.00E+001.86E-02Cr-511000500.04328570.007061967.03E-039.27E-029.98E-02Mn-541000500.02490830.00500824.99E-035.10E-025.59E-02Fe-551000500.02322480.008109918.09E-030.00E+008.09E-03 Fe-591000500.00595740.0024229382.42E-039.05E-031.15E-02Co-58100500.0781890.02259062.20E-021.

44E-011.66E-01Co-601000500.0211210.0144066811.44E-021.72E-023.16E-02Zn-651000500.00657540.0003885733.82E-040.0E+003.82E-04InsertA 1.32E-02 11.2-36LIQUID WASTE SYSTEMS WATTS BARSr-891000500.00188250.0001932151.92E-044.33E-034.52E-03Sr-901000500.00017362.21026E-052.20E-053.88E-044.10E-04Sr-911000500.00113780.0002847042.84E-042.18E-032.47E-03Y-91m1000500.00066940.0001688951.68E-040.00E+001.68E-04 Y-911000500.00020729.00858E-059.00E-053.00E-043.90E-04Y-931000500.00518290.0012738331.27E-030.00E+001.27E-03Zr-951000500.00609430.0013950241.39E-031.20E-021.34E-02Nb-951000500.00561380.0021083012.10E-038.98E-031.11E-02Mo-991000500.04308580.004234694.20E-039.95E-021.04E-01Te-99m1000500.03868980.003385143.35E-030.00E+003.35E-03Ru-1031000500.09757420.005975895.88E-030.00E+005.88E-03Ru-1061000501.1843240.0774327.63E-020.00E+007.63E-02 T c-12910 00Te-1291000500.00301820.0007325087.30E-040.00E+007.30E-04 Te-131m1000500.00567950.0008093358.05E-040.00E+008.05E-04 Te-1311000500.00112290.000203852.03E-040.00E+002.03E-04Te-1321000500.01258170.001123211.11E-032.93E-023.05E-02Ba-1401000500.14614560.01038151.02E-023.48E-013.58E-01Table 11.2-5 Total Annual Discharge Liquid Waste Processing System*Annual Discharge (Ci) After ProcessingTotal Releases Per Unit (TPC Unit 1 Only)*** (Page 2 of 3)Column 1Column 2Column 3Column 4Column 5Column 6Column 7Column 8CD = Condensate Polishing Demineralizer, MD = Mobile DemineralizerOTHER OPERATIONAL MODESEXPECTED OPERATIONMD DFCVCS DFSGB processed by CD S G B processed by CD and MDLRWNo SGBSGB with no CD process Column 6 and Column 7InsertB 50 0.0023849 0.000143146 1.41E-04 0.00E+00 1.41E-04 Tc-99m LIQUID WASTE SYSTEMS 11.2-37WATTS BARLa-1401000500.21084060.01643521.62E-024.98E-015.14E-01Ce-1411000500.00210850.0003423063.41E-040.00E+003.41E-04 Ce-1431000500.01142770.001536221.53E-030.00E+001.53E-03 Ce-1441000500.05609260.006891856.84E-031.26E-011.33E-01Np-2391000500.01354340.001385591.37E-030.00E+001.37E-03 H-3 (TPC)111252.80 (3326.4)1252.80 (3326.4)1257.64 (3326.4)Unplanne0.160.0.10.16total (w/o H3)w/unplanned3.52523283.6850.4416449 0.6020.4380.5984.4024.84 5.000total (w/H3) w/unplanned1256.33 (3329.93)1256.49 (3330.09)1253.24 (3326.84)1253.40 (3327.00)1257.64 (3331.24)1257.80 (3331.40)Table 11.2-5 Total Annual Discharge Liquid Waste Processing System*Annual Discharge (Ci) After ProcessingTotal Releases Per Unit (TPC Unit 1 Only)*** (Page 3 of 3)Column 1Column 2Column 3Column 4Column 5Column 6Column 7Column 8CD = Condensate Polishing Demineralizer, MD = Mobile DemineralizerOTHER OPERATIONAL MODESEXPECTED OPERATIONMD DFCVCS DFSGB processed by CD S G B processed by CD and MDLRWNo SGBSGB with no CD process Column 6 and Column 7InsertC 0.16 0.16UnplannedReleases**

0.16 U WASTE SSTEMS 11.2-37WATTS BARWP-13 Table 11.2-5 Total Annual Discharge Liquid Waste Processing System*Annual Discharge (Ci) After ProcessingTotal Releases Per Unit (TPC Unit 1 Only)***

Notes *The 0.16 Ci/yr is the unplanned release.** MD = Mobile Demineralizer (Processes Tans, CVCS) DF = Decontamination Factor CVCS DF = Decontamination Factor o CVCS prior to treatment with MD. Cond. demin. = condensate demineralizer regeneration waste

• • • Total Release = Tan + CVCS /MD DF + LHST = TB + cond. demin/MD DF C VCS DF****This calculated alue is based on an aerage o 365 days but does not represent a constraint on the plant since the actual alue or indiidual releases may be greater. Howeer, the total o all yearly releases must remain 5 Ci.(TPC) The alues within the parentheses () represent the tritium alues due to the Trtium Production Core.Column 1Source term isotopesColumn 2Decontamination actors or the Mobile DemineralizerColumn 3CVCS Demine ralizer decontamination actorsColumn 4((A+B/C)/D) + E + F/H + GColumn 5((A+B/C)/D) + E + F/H1D + G Column 6((A+B/C)/D) + E + F + GColumn 7((A+B/C)/D)+ E + G + IColumn 8((A+B/C)/D) + E + G + (See below deinition or items A thru A (Ci/yr) =Reactor Coolant Drain Tan + Tritiated Drain Collector Tan + Floor Drain Collector TanB (Ci/yr) =Chemical Volume Control System (CVCS) LetdownC=CVCS Demineralizer decontamination actorD=Mobile Demineralizer decontamination actorE(Ci/yr) =Laundry and Hot Shower Drain TanF (Ci/yr) =Condensate Demineralizer low = (Condensate low + Steam Generator Blow Down si day collection olume)G(Ci/yr) =Turbine Building drainsH=CondensateDemineralizer decontamination actors (2 or Rb-8 8, Cs-134,-136,-137, 10 or all other isotopes-re. 1)I(Ci/yr) =Steam Generator Blow Down at untreated lower limit o detect ability (LLD) concentration (5E-7 uCi/cc gross Gamma-re.2)* (Ci/yr) =Steam Generator Blow down at ma allowable untreated concentration o 3.65E-5 uCi/cc* This is eual to 3E+04 Ib/hr*453.59 g/lb*1 cc/g*24 hr/day*365 day/yr*5E-07 uCi/cc*1 E-06 Ci/UCi = 0.06 Ci/yrReplacewithInsertD Table 11.2-5 Total Annual Discharge Liquid Waste Processing System Annual Disharge (Ci) After Processing Total Releases Per Unit (TPC Unit 1 Only)*** (Page of )

Notes (TPC) The values within the parentheses () represent the tritium values due to the Trtium Production Core. *** Total Release = Tan + CVCS /MD DF + LHST + TB + cond. demin/MD DF MD = Mobile Demineralizer (Processes Tans, CVCS) DF = Decontamination Factor CVCS DF = Decontamination Factor o CVCS prior to treatment with MD. Cond. demin. = condensate demineralizer regeneration waste

• • 0.16 Ci/yr is an unplanned release from NUREG-0017. Column 1 Source term isotopes Column 2 Decontamination actors or the Mobile DemineralizerColumn 3 CVCS Demineralizer decontamination actors Column 4 ((A+B/C)/D) + E + F/H + G Column 5 ((A+B/C)/D) + E + F/H

/D + G Column 6 ((A+B/C)/D) + E + F + G Column 7 Column 8 ((A+B/C)/D) + E + G + (See below deinition or items A thru A (Ci/yr) = Reactor Coolant Drain Tan + Tritiated Drain Collector Tan + Floor Drain Collector TanB (Ci/yr) = Chemical Volume Control System (CVCS) Letdown C= CVCS Demineralizer decontamination actor D = Mobile Demineralizer decontamination actor E(Ci/yr)= Laundry and Hot Shower Drain Tan F (Ci/yr) = Condensate Demineralizer low = (Condensate low + Steam Generator Blow Down si day collection olume) G(Ci/yr) = Turbine Building drains H= CondensateDemineralizer decontamination actors (2 or Rb-88, Cs-134,-136,-137, 10 for all other isotopes-re. 1) (Ci/yr) = Steam Generator Blow down at ma allowable annual untreated concentration o 3.65E-5 uCi/cc. This calculated alue is based on an aerage o 365 days but does not represent a constraint on the plant since the actual alue or indiidual releases may be greater. Howeer, the total o all yearly releases must remain 5 Ci. InsertDCVCSDF 11.2-40U WASTE SSTEMS WATTS BARWP-13 Table 11.2-5c no CD rocess SD at LLD ith 2 gmdilution otherrelease aths at design limit ASCiyr Scaled to. CidesansiCiyr liquiduCicc liquid1CFR2CCLBr-840.000165337.122E-062.50 0.000420451.06E-11 4.0E-04 2.642E-08I-1310.0263441.551E-0252.41 1.396222673.51E-08 1.0E-06 0.0350911 I-1320.013155 1.475E-034.00 0.054095341.36E-09 1.0E-04 1.36E-05I-1330.0528581.169E-0226.85 1.430692293.60E-08 7.0E-06 0.0051368I-1340.00626223.612E-041.65 0.010683472.69E-10 4.0E-04 6.713E-07I-1350.0475085.752E-037.91 0.381714749.59E-09 3.0E-05 0.0003198 Rb-880.00689271.069E-0518.14 0.125025343.14E-09 4.0E-04 7.856E-06Cs-1340.0292762.296E-0340.60 1.190766882.99E-08 9.0E-07 0.0332526Cs-1360.00255132.350E-04165.20 0.421705231.06E-08 6.0E-06 0.0017664Cs-1370.0402653.014E-03153.22 6.172319891.55E-07 1.0E-06 0.155128Cr-510.00702571.264E-030.29 0.003311448.32E-11 5.0E-04 1.665E-07Mn-540.004988286.944E-040.47 0.003040127.64E-11 3.0E-05 2.547E-06Fe-590.00241941.233E-043.48 0.00854532.15E-10 1.0E-05 2.148E-05Co-580.0220291.958E-035.37 0.120295423.02E-09 2.0E-05 0.0001512Co-600.014399962.343E-041.38 0.020105225.05E-10 3.0E-06 0.0001684 Sr-890.0001915245.895E-0522.45 0.004358471.10E-10 8.0E-06 1.369E-05Sr-900.0000219515.285E-0613.49 0.000301457.58E-12 5.0E-07 1.515E-05Sr-910.000283852.977E-051.86 0.000558511.40E-11 2.0E-05 7.018E-07Y-9000.000E+0015.87 00.00E+00 7.0E-06 0 Y-918.99686E-054.086E-061115.17 0.10033472.52E-09 8.0E-06 0.0003152Zr-950.001390321.640E-041.71 0.002537716.38E-11 2.0E-05 3.189E-06Nb-950.0021047921.223E-042.34 0.00504541.27E-10 3.0E-05 4.227E-06Mo-990.00419581.356E-03785.19 3.295835768.28E-08 2.0E-05 0.0041417Te-1320.001111743.999E-04145.25 0.161881654.07E-09 9.0E-06 0.0004521 Ba-1400.01024564.738E-030.31 0.007953452.00E-10 8.0E-06 2.499E-05La-1400.01624066.784E-030.06 0.007706811.94E-10 9.0E-06 2.152E-05Ce-1440.00684261.717E-030.08 0.002269545.70E-11 3.0E-06 1.901E-05 Pr-14400.000E+000.08 00.00E+00 6.0E-04 0H-31252.8011252.803.15E-05 1.0E-03 0.0314864H-3 (TPC)3326.4013326.408.36E-051.0E-030.0836019Total0.2675585Total (TPC)0.319674Note This Table is based on column 7 o Table 11.2-5, ratioed up to 1 ailed uel with SGBD at lower limit o detection (LLD) (5E-7 uCi/cc gross gamma) (TPC Unit 1 only).DeleteTable ASEOUS WASTE SSTEMS 11.3-7WATTS BARWP-1311.3..3 ected aseous Waste Processing System ReleasesGaseous wastes consist o nitrogen and hydrogen gases purged rom the Chemical Volume and Control System olume control tan when degassing the reactor coolant, and rom the closed gas blaneting system. The gas decay tan capacity permits at least 60 days decay or waste gases beore discharge during normal operation.The uantities and isotopic concentration o gases discharged rom the GWPS hae been estimated. The analysis is based on input sources to the GWPS per NUREG0017, modiied to relect WBN plant-speciic parameters.The epected gaseous releases in curies per year per reactor unit are gien in Table 11.3-5. 11.3.. Releases from entilation SystemsA detailed reiew o the entire plant has been made to ascertain those items that could possibly contribute to airborne radioactie releases.During normal plant operations, airborne noble gases and/or iodines can originate rom reactor coolant leaage, euipment drains, enting and sampling, secondary side leaage, condenser air eector and gland seal condenser ehausts, and GWPS leaage.The assumptions used to estimate the annual uantity o radioactie gaseous eluents are gien in Table 11.3-6. These assumptions are in accordance with NUREG-0017. The noble gases and iodines discharged rom the arious sources are entered in Table 11.3-10.11.3..5 stimated Total ReleasesThe estimated releases listed in Table 11.3-7c hae been used in calculating the site boundary doses as shown in Table 11.3-10. Table 11.3-7a is the epected gases released or 1 ailed uel with containment purge. Table 11.3-7 is the annual releases with purge air ilters. Table 11.3-7b is the epected gases released or 1 ailed uel with continuous iltered containment ent, and Table 11.3-7c or approimately 1/8 ailed uel with continuous iltered containment ent.

The dose calculations, based on the estimated total plant releases, show that the releases are in accordance with the design obecties in Section 11.3.1 and meet the regulations as outlined in Section 11.3.7.1. Further, the total plant releases are within the ODCM limits.11.3. Release Points Gaseous radioactie wastes are released to the atmosphere through ents located on the Shield Building, Auiliary Building, Turbine Building, and Serice Building. A brie description, including unction and location o each type ent, is presented below.Replacewith"7"Replacewith"basedonANSIN18.1-1984" 11.3-8ASEOUS WASTE SSTEMS WATTS BARWP-12Shield uilding entWaste gases rom containment purge and the waste gas decay tans are discharged to the enironment through a Shield Building ent. Each Shield Building has one ent. The ent is o rectangular cross section (dimension - 2 eet by 7 eet 6 inches) and discharges approimately 130 eet aboe ground leel. The location o the Reactor Building ents is shown in the euipment layout drawings, Figure 1.2-1. The location o the Shield Building in relation to the site is shown on the main plant general plan, Figure 2.1-5. All releases rom the Shield Building ent ecept containment purge air ehaust monitor discharges are passed through HEPA ilters and charcoal adsorbers prior to release. The eluent discharge rate through the ent is ariable occasionally, during containment purge, the rate may approach the alue which is listed in Figure 9.4-28. The low path or waste gases ehausted through the ent rom the waste gas decay tans is shown in Figure 11.3-1.Auiliary uilding entWaste gases in the Auiliary Building are discharged through the Auiliary Building ehaust ent. In addition, containment atmosphere is continuously ented, during normal operation or pressure control, into the annulus ater it is iltered through HEPA and charcoal ilters, and subseuently, discharged into the Auiliary Building ehaust ent. The ent is o the chimney type haing a rectangular cross section o 10 by 30 eet. The top o the ent is located atop the Auiliary Building and discharges approimately 106 eet aboe grade. Under normal operating conditions, gases are continuously discharged through the ent. Eluent low rates can be near 224,000 cm when two Auiliary Building general ehaust ans and one uel-handling area ehaust an are operating at ull capacity. Under accident conditions, the Auiliary Building is isolated, and the Auiliary Building gas treatment system (ABGTS) is used to treat gaseous eluents. When in serice, the ABGTS discharges to the Shield Building ehaust ent. The location o the Auiliary Building ehaust ent is shown in the euipment layout diagram, Figure 1.2-1. The Auiliary Building is shown on the main plant general plan, Figure 2.1-5.Turbine uilding entsVentilation air is ehausted rom the Turbine Building through the Turbine Building ents. There are eighteen ents at the 755-oot leel and twenty ents at the 824-oot leel (roo leel). The eluent low rates ary or each type o ent. Generally, the normal low rates through a typical ent at the 755-oot leel is 22,888 cm and the low rates through typical ent at the 824-oot leel is 28,500 cm. The general arrangement o ents on the Turbine Building is shown on Figure 1.2-1. The turbine building is shown on the main plant general plan, Figure 2.1-5.Condenser acuum haust entGaseous wastes rom the condenser are discharged through the condenser acuum ehaust ent. The ent, which is a 12-inch diameter pipe, discharges at approimately the 760-oot leel. Under normal operating conditions the discharge low rate will typically be less than 45 cm. No.4-Replacewith:TurbineBuildingVents Gaseouswastesfromthecondenseraredischargedthroughthecondenservacuumexhaustvent.Thevent,whichisa12-inchdiameterpipe,dischargesatapproximately the760-footlevel.Undernormaloperatingconditionsthedischargeflowratewilltypically belessthan45cfm.Non-radioactiveventilationairisexhaustedfromtheTurbineBuildingthroughtheTurbineBuildingvents.Thereareeighteenventsatthe755-footlevelandtwentyvents atthe824-footlevel(rooflevel).Theeffluentflowratesvaryforeachtypeofvent.

Generally,thenormalflowratesthroughatypicalventatthe755-footlevelis22,888cfm andtheflowratesthroughtypicalventatthe824-footlevelis28,500cfm.Thegeneral arrangementofventsontheTurbineBuildingisshownonFigure1.2-1.Theturbine buildingisshownonthemainplantgeneralplan,Figure2.1-5.

ASEOUS WASTE SSTEMS 11.3-9WATTS BARWP-13Serice uilding ent Radiologically monitored potentially radioactie waste gases rom the radiochemical laboratory and the titration room are ehausted through HEPA ilters ia a common duct which discharges to the common Serice Building roo ehaust plenum. Ehaust air rom the general area discharges to the common Serice Building roo ehaust plenum. Separate ents rom the common roo ehaust plenum discharge to atmosphere approimately 24 eet aboe grade. The Serice Building is shown on the site plot plan, Figure 2.1-5.11.3. Atmosheric DilutionCalculations o atmospheric transpo rt, dispersion, and ground deposition are based on the straight-line airlow model discussed in NRC Regulatory Guide 1.111 (Reision 1, uly 1977). Releases are assumed to be continuous. Releases nown to be periodic, e.g., those during containment purging and waste gas decay tan enting, are treated as continuous releases.Releases rom the Shield Building, Turbine Building (TB), and Auiliary Building (AB) ents are treated as ground leel. The ground leel oint reuency distribution (FD) is gien in Section 2.3. Air concentrations and deposition rates were calculated considering radioactie decay and buildup during transit. Plume depletion was calculated using the igures proided in Regulatory Guide 1.111.Estimates o normalized concentrations (X/) and normalized deposition rates (D/) or gaseous releases at points where potential dose pathways eist are listed in Table11.3-8.11.3.1 stimated Doses from Radionuclides in aseous ffluentsIndiiduals are eposed to gaseous eluents ia the ollowing pathways (1) eternal radiation rom radioactiity in the air and on the ground (2) inhalation and (3) ingestion o bee, egetables, and mil. No other additional eposure pathway has been identiied which would contribute 10 or more to either indiidual or population doses.11.3.1.1 Assumtions and Calculational ethodsEternal air eposures are ealuated at points o potential maimum eposure (i.e., points at the unrestricted area boundary). Eternal sin and total body eposures are ealuated at nearby residences. The dose to the critical organ rom radioiodines, tritium (Unit 1 only) and particulates is calculated or real pathways eisting at the site during a land use sur ey conducted in 1994.To ealuate the potential critical organ dose, mil animals and nearest gardens were identiied by a detailed surey within ie miles o the plant (Table 11.3-8). Inormation on grazing seasons and eeding regimes are relected in the eeding actor. The eeding actor is the raction o the year an animal grazes on pasture. During the 1994 land use surey, there was one mil cow location identiied in which inormation regarding the eeding regime or the animals, and the ages o onsite consumers o the mil could not be established. Because no speciic inormation is nown, it is conseratiely assumed that the eeding actor or that location is eual to the worst-Re placewith"batch"Insertthefollowing:"ThecomputercodetitledGaseousEffluentLicensingCode(GELC)wasusedtoperformroutinedoseassessmentsforWBN.DuringUnit1 licensing,terrainadjustmentfactors(TAF)weredevelopedtoaccountfor recirculationeffectsduetotherivervalleylocationoftheplant."Insertthefollowingasparagraphlead-in:"Table11.3-8providesthereceptorlocationsfor performingthedoseassessmentsinthischapter.Thedataisbasedonthe2007landuse survey.TheTAF,X/Q,andD/Qforeachreceptorarecalculatedforthelocationsbasedon thissurvey.TheTAFpresentedinTable11.3-8weredevelopedonthesamebasisthat wasusedforUnit1licensing.Meteorologydatafromthe1986to2005timeperiodwas usedinthedevelopmentoftheX/QsandD/Qs." DeleteReplacewith"2007"Replacewithinsertfromnextpage 11.3-10ASEOUS WASTE SSTEMS WATTS BARWP-13case eeding actor identiied during the 1994 land use census or any real cow location (i.e., 70 pasture eeding) and that all our age groups are present. Since speciic data on bee animals were not aailable, the nearest bee animal was assumed to be at the point o maimum osite eposure. Mil ingestion is the critical pathway. TVA assumes that enough resh egetables are produced at each residence to supply annual consumption by all members o that h ousehold. TVA assume s that enough meat is produced in each sector annulus to supply the needs o that region. Watts Bar proected population distribution or the year 2040 is gien in Table 11.3-9.Doses are calculated using the dose actors and methodology contained in NRC Regulatory Guide 1.109 with certain eceptions as ollows (1)Inhalation doses are based on the aerage indiiduals inhalation rates ound in ICRP Publication 23 o 1,400 5,500 8,000 and 8,100 m 3/year or inant, child, teen, and adult, respectiely.

(2)The mil ingestion pathway has been modeled to include speciic inormation on grazing periods or mil animals obtained rom a detailed arm surey. A eeding actor (FF) has been deined as that raction o total eed intae a dairy animal consumes that is rom resh orage. The remaining portion o eed (1-FF) is assumed to be rom stored eed. Doses calculated rom mil produced by animals consuming resh orage are multiplied by these actors. Concentrations o radioactiity in stored eed are adusted to relect radioactie decay during the maimum assumed storage period o 180 days by the actorThis actor replaces the actor ep (-i t h) in euation C-10 o Regulatory Guide 1.109.

(3)The stored egetable and bee ingestion pathways hae been modeled to relect more accurately the actual dietary characteristics o indiiduals. For stored egetables the assumption is made that home grown stored egetables are consumed when resh egetables are not aailable, i.e., during the 9 months o all, winter, and spring. Rather than use a constant 1 180---------expi t-t d 0 1801i 180-ep-180i--------------

---

=Insertthefollowinghereandontotheprecedingpage:"Thecalculationassumesfeedingfactorof0.65forallcowreceptorsinthe2007LUS.ThevalueistakenfromFigure2.2inNUREG/

CR-4653"GASPARII-TechnicalReferenceandUserGuide,"1987thatprovidesthegrowing seasonacrosstheUS.ThevaluechosenisonthehighendforthemiddleTennesseeValley.

TheLUSandpubliclyavailableinformationsupportthatthisisaconservativefeedingfactor.

SupplementalfeedisassumedtobegrowninthevicinityofWattsBarandhavethesame nuclidesourceasthepasture."

11.3-12ASEUS WASTE SYSTEMS WATTS BARWP-13* e.g., someone who is 1 year, 11 months is an inant, while someone who is eactly two years old is a child.Tables 11.3-10 and 11.3-11 proide the doses estimated or indiiduals and the population within 50 miles o the plant site.11.3.1.2 Summary of Annual Poulation DosesTVA has estimated the radiological impact to regi onal population groups in the year 2040 rom the normal operation o the Watts Bar Nuclear Plant. Table 11.3-11 summarizes these population doses. The total body dose rom bacground to indiiduals within the United States ranges rom approimately 100 mrem to 250 mrem per year. The annual total body dose due to bacground or a population o about 1,100,000 persons epected to lie within a 50 mile radius o the Watts Bar Nuclear Plant in the year 2040 is calculated to be approimately 154,000 man-rem assuming 140 mrem/year/indiidual. By comparison, th e same population (ecluding onsite radiation worers) will receie a total body dose o approimately 3.85 man-rem rom eluents. Based on these results, TVA concludes that the normal operation o the Watts Bar Nuclear Plant will present minimal ris to the health and saety o the public.RFRCS NoneTeen 13A19 0.153Adult 19A 0.665Category Ages (A)* FractionReplacewith"11.3-11and11.3-12"Insertwith"TVAassumesthatenoughfreshvegetablesareproducedateachresidencetosupplyannualconsumptionbyallmembersofthathousehold.TVA assumesthatenoughmeatisproducedineachsectorannulustosupplytheneeds ofthatregion.WattsBarprojectedpopulationdistributionfortheyear2040isgiven inTable11.3-9.Vegetableingestionisthecriticalpathway."Replacewith"1,500,000"Replacewith"210,000"Replacewith"6.66" ASEUS WASTE SYSTEMS 11.3-19WATTS BARWP-13Table 11.3- Radioactie aseous ffluent Parameters (Page 1 of 2)1.Thermal Power Rating is 3582 MWt. (For Unit 1 only, Tritium releases based on 3425 MWt. Tritium isotope determination or the Non-Tritium Production Cor e based on 3480 MWt)2.Primary and secondary side coolant and steam actiities are based on NUREG-0017 and hae been plant adusted or WBN speciic parameters.3.RCS water parametersVolume = 11,375 t 3Press. = 2250 psiaTemp. = 588.2 F Spec. Vol. = 0.02265 t 3/lb4.Containment releases are iltered through a HEPA and charcoal ilter with minimum iltration eiciencies o 99 and 70, respectiely.5.Containment gaseous source terms are based on a 3/day (noble gas) and 8.0E-4/day (iodines) release o RCS coolant into the containment air borne atmosphere.6.WCDT releases are based on a 173 t 3/day ( STP) input o RCS coolant ogas to the waste gas disposal system and a WGDT holdup time o 60 days.7.Auiliary Building (AB) entilation noble gas source terms are based on a 160 lb/day release o RCS coolant actiity into the AB atmosphere.8.AB entilation iodine releases are based on 1.85 Ci/yr per Ci/gm o RCS or 300 days and 6.8 Ci/yr per Ci/gm or 65 days.9.Reueling Area iodine releases are based on 0.16 Ci/yr per Ci/gm o RCS or 300 days and 0.3Ci/yr per Ci/gm or 65 days.10.Turbine Building (TB) entilation noble gas sour ce terms are based on a 1700 lb/hr release o secondary steam into the TB atmosphere.11.TB entilation iodine source terms are based on 8500 Ci/yr per Ci/gm o secondary steam or 300days and 1400 Ci/yr per Ci/gm or 65 days. 12.Condenser acuum ehaust noble gas source terms are based on a steam lowrate to the condenser o 8.5E6 lb/hr at secondary steam actiities.13.Condenser acuum ehaust iodine source terms are based on a 3500 Ci/yr per Ci/gm o secondary steam released to the condenser acuum ehaust.14.Steam generator blowdown lash tan source terms are based on a maimum steam generator blowdown low o 12.5 gpm/steam generator. Iodines are urther reduced in the ogases by applying a 0.05 partition actor. There are no noble gas releases rom this path as there are no noble gas source terms in th e secondary coolant. 15.Ar-41 releases are 34 Ci/yr.

16.Total tritium releases are based on 0.4 Ci/yr per MWt, with 10 o that aailable or release ia gaseous pathways.17.Total particulate releases are taen directly rom Table 2-17 o NUREG-0017. Since these alues are prior to treatment, the releases rom the Containm ent Building either through the purge air, or containment ent ilters, are reduced by applying a HEPA iltration actor o 0.01 (99 eiciency).Replacewith"ANSIN18.1"Replacewith"WGDT" 11.3-20ASEUS WASTE SYSTEMS WATTS BARWP-1318.C-14 releases are 1.6 Ci/yr rom containment, 4.5 Ci/yr rom the AB, and 1.2 Ci/yr rom the GWPS or a total o 7.3 Ci/yr.19.The WGS discharge is iltered with a HEPA (eiciency o 99) and charcoal (eiciency 70) ilter prior to release.20.NUREG-0017 suggests 22 containment purges a year during power operation, and 2 purges during reueling. Howeer, one purge eery two wees will be used in the calculation. In addition, continuous containment ent with 100 cm will be ealuated.Table 11.3- Radioactie aseous ffluent Parameters (Page 2 of 2)Replacewith"Acontinuousfilteredcontainmentventof100cfmistheexpectednormalreleaseandisevaluated.Aseparateevaluationassumingonepurgeeverytwoweekswill beperformed.NUREG-0017suggests22containmentpurgesayearduring poweroperation,and2purgesduringrefueling."

11.3-26ASEUS WASTE SYSTEMS WATTS BARWP-13Table 11.3-c Total Releases (y1 failed fuel inCiyr), ith Continuous Filtered Containment ent (Sheet1of 1)Table based on operation o one unit NuclideContain.(1)BuildingAu.BuildingTurbine BuildingTotal r-85m r-85 r-87 r-88 Xe-131m Xe-133m Xe-133 Xe-135m Xe-135 Xe-137 Xe-138 Ar-41 Br-84 I-131 I-132 I-133 I-134 I-135 H-3 H-3 (TPC)

Cr-51Mn-54 Co-57 Co-58 Co-60Fe-59 Sr-89 Sr-90 Zr-95 Nb-95 Ru-103 Ru-106 Sb-125 Cs-134 Cs-136 Cs-137 Ba-140 Ce-141 C-14 3.72E+00 6.69E+02 4.48E-01 3.10E+00 1.07E+03 4.07E+01 2.82E+03 2.26E-02 5.83E+01 3.76E-04 1.69E-02 3.40E+01 8.16E-07 6.74E-03 1.36E-04 2.36E-03 4.26E-05 8.80E-04 1.39E+02 3.70E+02 9.21E-05 5.30E-05 8.20E-06 2.50E-042.61E-052.70E-05 1.30E-04 5.22E-054.80E-08 1.80E-05 1.60E-05 2.70E-08 0.00E+00 2.53E-05 3.21E-05 5.58E-05 2.30E-07 1.30E-05 2.80E+00 4.53E+00 7.05E+00 4.27E+00 7.95E+00 1.73E+01 1.90E+00 6.70E+01 3.68E+00 2.40E+01 9.67E-01 3.42E+00 0.00E+00 5.02E-02 1.39E-01 6.56E-01 4.35E-01 1.06E+00 8.10E-01 0.00E+00 0.00E+00 5.00E-04 3.78E-04 0.00E+00 2.29E-02 8.71E-03 5.00E-05 2.85E-03 1.09E-03 1.00E-03 2.43E-03 6.10E-05 7.50E-05 6.09E-05 2.24E-03 4.80E-05 3.42E-03 4.00E-04 2.64E-05 4.50E+001.23E+001.86E+00 1.09E+00 2.13E+00 4.53E+00 5.21E-01 1.77E+01 9.80E-01 6.46E+01 2.58E-01 9.06E-01 0.00E+00 4.81E-04 7.08E-03 1.70E-022.03E-021.47E-02 3.13E-02 0.00E+00 0.00E+000.00E+000.00E+00 0.00E+00 0.00E+000.00E+000.00E+00 0.00E+00 0.00E+000.00E+00 0.00E+000.00E+00 0.00E+00 0.00E+00 0.00E+000.00E+000.00E+00 0.00E+00 0.00E+00 0.00E+00 9.48E+00 6.78E+02 5.81E+00 1.32E+01 1.09E+03 4.31E+01 2.90E+03 4.68E+00 8.88E+01 1.23E+00 4.34E+00 3.40E+01 5.07E-02 1.53E-01 6.73E-01 4.57E-01 1.07E+00 8.42E-01 1.39E+02 3.70E+02 5.92E-04 4.31E-04 8.20E-06 2.32E-02 8.74E-03 7.70E-05 2.98E-03 1.14E-03 1.00E-03 2.45E-03 7.70E-05 7.50E-05 6.09E-05 2.27E-03 8.01E-05 3.48E-03 4.00E-04 3.95E-05 7.30E+00(TPC) Tritium alues or a Tritium Production Core (Unit 1 only)

ANSIN18.1-1984 Delete ASEUS WASTE SYSTEMS 11.3-27WATTS BARWP-13Table 11.3- Data On Points Of nterest ear Watts ar uclear Plant (Page 1 of 2)

SectorDistance(eters)Chi-oer-(sm3)D-oer-(1m2)TerrainAdustmentFactor ilFeedingFactorUnrestricted Area Boundary Unrestricted Area BoundaryUnrestricted Area Boundary Unrestricted Area BoundaryUnrestricted Area Boundary Unrestricted Area BoundaryUnrestricted Area Boundary Unrestricted Area BoundaryUnrestricted Area Boundary Unrestricted Area BoundaryUnrestricted Area Boundary Unrestricted Area BoundaryUnrestricted Area Boundary Unrestricted Area BoundaryUnrestricted Area Boundary Unrestricted Area Boundary NNNE NE ENE EESE SESSE SSSW SWWSW W WNW NWNNW155019801580 137012801250125012501340 155016701430 146014001400 1460 5.12e-06 6.35e-06 1.05e-05 1.23e-05 1.37e-05 1.43e-051.11e-05 6.04e-06 5.33e-06 4.14e-06 4.46e-06 5.47e-062.11e-06 2.49e-06 2.05e-06 2.68e-06 8.13e-09 1.23e-08 1.10e-08 8.77e-09 9.66e-09 1.16e-08 9.49e-09 8.21e-09 1.17e-08 1.05e-08 7.34e-09 6.37e-09 2.07e-09 2.38e-09 2.13e-09 3.08e-09 1.70 1.80 2.10 1.70 1.60 1.80 1.50 1.50 1.90 2.00 2.10 1.80 1.20 2.50 1.70 1.60 Resident Resident Resident Resident Resident Resident Resident Resident Resident Resident Resident Resident Resident Resident Resident Resident Gar den Garden Garden Garden Garden Garden Garden Garden Garden NNNE NE ENE EESE SESSE SSSW SWWSW W WNW NWNNW NNNE NE ENE EESE SESSE S213436003353 2414326844161372 152415851979 423018292896 164620614389766461733829 492749916096 463374542254 2.84e-06 2.69e-06 3.84e-06 6.26e-06 3.97e-06 2.64e-06 9.66e-06 4.18e-06 3.91e-06 2.76e-06 1.15e-06 3.61e-06 7.30e-07 2.26e-06 1.03e-06 3.50e-07 3.13e-07 1.06e-06 3.06e-06 2.01e-06 1.99e-06 1.63e-06 1.58e-06 4.74e-07 2.50e-06 4.21e-09 4.41e-09 3.22e-09 3.83e-09 2.14e-09 1.46e-09 8.16e-09 5.56e-09 8.42e-09 6.64e-09 1.43e-09 4.03e-09 6.01e-10 2.12e-09 9.95e-10 2.97e-10 3.00e-10 1.42e-09 2.44e-09 9.39e-10 9.02e-10 7.77e-10 8.97e-10 3.57e-10 4.94e-09 1.50 1.80 2.20 1.90 1.70 1.90 1.50 1.40 1.80 1.90 2.00 1.70 1.10 2.90 1.50 1.00 1.00 1.50 2.10 1.60 1.50 1.80 1.30 1.40 1.90 Insert"Nearest"in frontofeach

listing.Replacewith"NearestGarden"NE33533.84e-063.22e-092.20 Replacewith"NearestGarden"E63721.35e-065.42e-101.40 Replacewith"NearestGarden"ESE47582.26e-061.21e-091.80 Replacewith"NearestGarden"SSE74543.73e-072.80e-101.10 11.3-28ASEUS WASTE SYSTEMS WATTS BARWP-13 Garden Garden Garden Garden Garden Garden GardenMil CowMil CowMil Cow Mil CowSSW SWWSW W WNW NWNNW ESEESESSW SSW8100810046675120590931704698 609667062286 3353 2.79e-07 4.28e-07 9.86e-07 3.33e-07 1.85e-07 5.63e-07 3.18e-07 1.63e-06 1.35e-06 2.24e-06 1.36e-06 4.16e-10 4.03e-10 8.06e-10 2.23e-10 1.13e-10 4.78e-10 2.64e-10 7.77e-10 6.18e-10 5.20e-09 2.84e-09 1.40 1.80 1.70 1.10 1.40 1.50 1.00 1.80 1.70 1.90 2.000.250.030.05 0.33Table 11.3- Data On Points Of nterest ear Watts ar uclear Plant (Page 2 of 2)

SectorDistance(eters)Chi-oer-(sm3)D-oer-(1m2)TerrainAdustmentFactor ilFeedingFactorReplacewith"NearestGarden"SSW19792.76e-066.64e-091.90Replacewith"NearestGarden"SW81004.28e-074.03e-101.80 Replacewith"NearestGarden"WSW46678.70e-077.11e-101.50 Replacewith"NearestGarden"W51203.03e-072.03e-101.00 Replacewith"NearestGarden"WNW59091.72e-071.05e-101.30 Replacewith"NearestGarden"NW31704.13e-063.50e-101.10 Replacewith"NearestGarden"NNW46023.28e-072.74e-101.00MilkCowESE67061.35e-066.18e-101.700.65 MilkCowSSW22862.24e-065.20e-091.900.65 MilkCowSSW33531.36e-062.84e-092.000.65 ASEUS WASTE SYSTEMS 11.3-29WATTS BARWP-12Table 11.3- Proected 2 Poulation Distribution Within 5 iles Of Watts ar uclear Plant Poulation Within ach Sectorlement Distance From Site (iles)

S S SS S

SSW SWWSW W

WW W W Total-1 0 0 0 0 0

0 0

12 0

0 0

0 2

5 0

0 19 1-2 111 25 0 2 2

2 0 23 54 34 0 10 5 30 10 0 3082-3 32 25130 55 7 4 16 3

14 7 5 40 19 10111 62540 3-47 76 208 53 53 47 35 27 24 19 2

38 59 140 113 87 1028-5 135 43 130 78 38 58 29 24 257 32 0

30 65 121 387 98 15255-1 893 796 861 252 482 591 505 714 1368 739 5191281 837 244 2279 2081144421-2 2071 8591 3381 2445 9716 4514 17835 4018 1141 5653 6490 10369 965 1461 314 874 798382-3 2166 19187 19210 9497 8837 12085 10818 8056 34699 17523 9411 2091 5337 2925 7266 18279 187387 3-3453 9342 30623 38457 10649 3420 3969 3899 40812 25829 68565 7134 2839 3440 7004 4784 264219-5 4040 1194 54111136395 17404 300 3756 6362 11522 117868 125338 6571 2035 17598 9802 2983517279Replacewithattachedrevised

table Table 11.3- Proected 2 Poulation Distribution Within 5 iles of Watts ar uclear Plant Poulation Within ach Sector lement Distance from Site (iles) Direction -1 1-2 2-3 3- -5 Total N 2,619 1,885 2,778 4,768 6,172 18,222 NNE 2,150 11,762 18,766 14,502 2,547 49,727 NE 1,441 3,783 16,734 29,838 78,334 130,130 ENE 1,110 3,553 29,539 63,798 253,831 351,832 E 1,915 11,352 18,647 30,063 44,013 105,990 ESE 135 6,230 20,120 5,068 3,280 34,833 SE 203 19,852 15,185 3,950 4,822 44,012 SSE 782 8,951 12,907 2,918 48,593 74,151 S 5,823 4,586 42,883 56,430 17,985 127,707 SSW 567 5,725 42,517 46,281 106,392 201,482 SW 1,051 12,978 14,499 62,307 111,795 202,630 WSW 938 12,791 2,837 2,840 3,372 22,778 W 937 3,406 5,555 2,944 5,474 18,316 WNW 717 2,091 4,372 5,654 20,511 33,345 NW 3,998 2,889 18,634 10,462 15,956 51,940 NNW 3,413 1,536 33,843 11,609 5,890 56,290 TOTAL 27,799 113,368 299,818 353,432 728,968 1,523,385 NewDataforTable11.3.9 11.3-30ASEUS WASTE SYSTEMS WATTS BARWP-13Table 11.3-1 Watts ar uclear Plant- ndiidual Doses From aseous ffluents (For1Unit ithout TPC)EluentPathway Guideline*LocationDose Noble Gases Air dose 10 mradMaimum Eposed Indiidual 1 0.801 mrad/yr Air dose 20 mradMaimum Eposed Indiidual 1 2.710 mrad/yrTotal body 5 mremMaimum Residence 2,30.571 mrem/yr Iodines/ParticulatesSinThyroid(critical organ) 15 mrem 15 mremMaimum Residence 2,3Maimum Real Pathway 41.540 mrem/yr 2.715 mrem/yrreadon of odineParticulate Doses (mremyr)Cow Mil withFeeding Factor o 0.332.44Inhalation0.174Ground Contamination0.0405 Submersion Bee Ingestion 1Total 0.0603 0.0 2.7148 *Guidelines are deined in Appendi I to 10 CFR Part 50.

1Maimum eposure point is at 1250 meters in the SE sector.

2Dose rom air submersion.

3Maimum eposed residence is at 1372 meters in the SE sector.

4Maimum eposed indiidual is an inant at 3353 meters in the SSW sector.

Replace with 9.15 Replace with"Bone"Replacewith

"6.57 0.0704 0.0947 0.130 2.28 9.145mrem/yr"Replacewith TotalVegetable IngestionReplacewith"ESE"Replacewith "achild"Replacewith

"1979"Insertthefollowin g:" 5Maximumdoselocationforallreceptorsis1250metersintheESEsector."Replacewith"5" ASEUS WASTE SYSTEMS 11.3-31WATTS BARWP-13Table 11.3-11 Summary Of Poulation DosesTROD Submersion Ground Inhalation Cow Mil Ingestion Bee IngestionVegetable Ingestion Total man-remInant 8.28E-02 3.11E-03 7.45E-02 4.09E-01 0.00E+00 0.00E+00 5.01E-01 Child 1.59E-01 3.49E-02 1.39E-00 1.98E-00 3.52E-01 1.18E-00 5.10E+00Teen 1.44E-01 3.17E-02 7.44E-01 8.42E-01 1.77E-01 4.76E-01 2.42E+00 Adult 6.28E-01 1.38E-01 2.64E+00 1.60E-00 8.93E-01 1.26E-01 7.15E+00Total 9.45E-01 2.08E-01 4.85E+00 4.83E+00 1.42E-00 2.92E+00 1.52E+01TOTAL OD Submersion Ground InhalationCow Mil Ingestion Bee IngestionVegetable Ingestion Total man-remInant 1.42E-02 3.11E-03 4.28E-03 1.14E-01 0.00E+00 0.00E+00 1.36E-01 Child 1.59E-01 3.49E-02 1.14E-01 6.30E-01 3.36E-01 1.20E-00 2.47E+00Teen 1.44E-01 3.17E-02 7.23E-02 2.39E-01 1.69E-01 5.08E-01 1.16E-00 Adult 6.28E-01 1.38E-01 2.99E-01 4.25E-01 8.52E-01 1.42E-00 3.76E+00Total 9.45E-01 2.08E-01 4.90E-01 1.41E-00 1.36E-00 3.12E+00 7.53E+00Replacewithinformationprovidedbythefollowing

page Table 11.3-11 Summary of Population Doses THYROID I Tee A T Se 1e-0 11e-01 18e-01 e-01 88e-01 G 1e-0 e-0 e-0 10e-01 1e-01 I e-0 1e00 e-01 e00 e-00 Ie e-01 1e00 e-01 1e00 81e00 Bee Ie 000e00 1e-01 1e-01 80e-01 18e00 eee Ie 000e00 10e00 1e-01 10e00 e00 T -e 0e-01 e00 0e00 1e00 10e01 TOTAL BODY I Tee A T Se 1e-0 11e-01 18e-01 e-01 88e-01 G 1e-0 e-0 e-0 10e-01 1e-01 I e-0 10e-01 e-0 e-01 e-01 Ie 10e-01 e-01 1e-01 8e-01 18e00 Bee Ie 000e00 0e-01 1e-01 e-01 1e00 eee Ie 000e00 10e00 0e-01 11e00 0e00 T -e 1e-01 0e00 10e00 1e00 e00 Usethisdatatoreplaceinformationinpreceding

table. , Attachment 3 Response to FSAR Chapter 11 and FSEIS, Chapter 3 Request For Additional Information Proposed Clean Copy of FSAR Sections 11.1, 11.2 and 11.3 SURE TERMS 11.1-1WATTS BAR11.RADOACT WAST AAT11.1 SOURC TRSThe ission product inentory in the reactor core and the diusion to the uel pellet/cladding gap are presented in Section 15.1.7.11.1.1 istorical Design odel for Radioactiities in Systems and Comonents This section and associated Tables 11.1-1 through 11.1-5 present results o the original Westinghouse Design Calculations using methodology in Reerences 2 and 3. The results are presented as bacground and are superseded by calculations described in Section 11.1.2 and Tables 11.1-6 and 11.1-7.11.1.1.1 Reactor Coolant istorical Design ActiityThe parameters used in the calculation o the reactor coolant ission product design inentories together with the pertinent inormation concerning the design reactor coolant cleanup low rate and demineralizer eectieness, are summarized in Table 11.1-1. The results o the calculations are presented in Tables 11.1-2 through 11.1-4. In these calculations the deectie uel rods are assumed to be present at the initial core loading and to be uniormly distributed throughout the core thus, the ission product escape rate coeicient are based upon aerage uel temperature.For uel ailure and burnup eperience, see Section 4.2.1.3.3.The ission product actiities in the reactor coolant during o peration with small cladding deects (uel rods containing pin-holes or ine cracs) are computed using the ollowing dierential euationsor parent nuclides in the coolantor daughter nuclides in the coolant symbolsN = nuclide concentration D = clad deects, as a raction o rated core thermal power being generated by rods with clad deectsR = puriication low, coolant system olumes per sec.

B o= initial boron concentration, ppm dN wi dt-------------Di N c ii Ri B B o tB---------------------

++N wi-=dN w dt------------

-DN cRB B o tB--------------------

-N w-i N wi=

11.1-2SURE TERMS WATTS BARB = boron concentration reduction rate by eed and bleed, ppm per sec. = remoal eiciency o puriication cycle or nuclide = radioactie decay constant = escape rate coeicient or diusion into coolantt = elapsed time (seconds) since the beginning o cycle subscriptsC = reers to core w = reers to coolant i = reers to parent nuclide = reers to daughter11.1.1.2 olume Control Tan istorical Design ActiityTable 11.1-3 lists the actiities in the olume control tan us ing the assumptions summarized in Table 11.1-1. 11.1.1.3 Pressurier istorical Design ActiityThe actiities in the pressurizer are separated between the liuid and the steam phase and the results obtained are gien in Table 11.1-4 using t he assumptions summarized in Table 11.1-1.11.1.1. aseous Waste Processing System istorical Design ActiitiesThe actiities to be ound in the Gaseous Waste Processing System are gien in Table

11.1-5.11.1.1.5 Secondary Coolant istorical Design ActiitiesThe secondary cleanup system design actiities used or shielding design calculations are discussed in Subsection 12.2.1.5.11.1.2 Realistic odel for Radioactiities in Systems and ComonentsThis section and associated Tables 11.1-6 and 11.1-7 present results which supersede the calculations in the preious sections. The Tritium Producing Burnable Absorber Rods (TPBARs) (Unit 1 only) are designed and abricated to retain all the tritium produced within the TPBAR. Since the TPBAR produced tritium is chemically bonded within the TPBAR, irtually no tritium is aailable in a orm that could permeate through the TPBAR cladding. Howeer, it is assumed that while operating with a Tritium Production Core (TPC), some o the tritium inentory in the TPBARs may permeate the SURE TERMS 11.1-3WATTS BAR cladding material and be released to the primary coolant. The design goal or this permeation process is less than 1000 Ci per 1000 TPBARs per year. Thus a single TPBAR may release more than 1 Ci/year, but the total release or 1,000 TPBARs will be less than 1000 Ci/year. As the TPC will contain up to 2,304 TPBARs at WBN (Unit 1 only), the total design basis tritium input rom the maimum number o TPBARs is 2,304 Ci/year into the Reactor Coolant System.The parameters used to describe Watts Bar are gien in Table 11.1-6 together with the nominal alues gien in ANS-18.1-1984. In order to obtain primary coolant actiities, the correction ormula rom ANSI/ANS-18.1-1984 1, was applied to the actiities listed in Reerence 1. Secondary side water and steam actiities were similarly obtained rom the alues gien in Reerence 1.The speciic actiities or primary and secondary sides are calculated by ANSI/ANS-18.1-1984 1 methodology and gien in Table 11.1-7.11.1.3 Plant Leaage As a necessary part o the eort to reduce eluent o radioactie liuid wastes, Westinghouse sureyed arious PWR acilities which are in operation, to identiy design and operating problems inluencing reactor coolant and nonreactor grade leaage and hence the load on a waste processing system. Liuid leaage sources hae been identiied primarily in connection with pump shat seals and ale stem leaage.Where paced glands are proided, leaage may be anticipate d, while mechanical shat seals proide essentially zero leaage. Vale stem leaage was eperienced where the originally speciied pacing was used. A combination o a graphite ilament yarn pacing sandwiched with asbestos sheet pacing is used with improed results in seeral plants. For Watts Bar the maority o the ales used are diaphragm ales. This type o ale proides positie control stem leaage and is suitable or use as an isolation ale as well as a throttling ale.Epected leaage rates o liuids to be treated in the liuid waste processing system are summarized in Table 11.2-1.Total plant liuid and gaseous releases are discussed in Subsections 11.2.6 and 11.3.7, respectiely.11.1. Additional SourcesDuring normal operation, the sources o radioactie material not normally considered part o the radioactie waste system are as ollows (1)Containment Purging System (2)Turbine Gland Sealing System (3)Main Condenser Eacuation System 11.1-4SURE TERMS WATTS BAR (4)Auiliary Building Ventilation System (5)Turbine Building Ventilation System (6)Steam Generator Blowdown SystemEstimates or the release o radioactie materials rom sources 1 through 5 (aboe) are presented in Section 11.3.7. The release paths and transport mechanism or these sources o radioactie material are also presented in Section 11.3.8.The Steam Generator Blowdown System (SGBS) is another source o liuid radioactie material that is not normally considered part o the radioactie waste system. The system description, release paths, and low rates are presented in Section 11.2 and in Section 10.4.8. The release path that is o concern in ealuating the radiological conseuences o liuid releases rom steam generator blowdowns is the path to the rier ia the cooling tower blowdown line. This route is used primarily during periods when there is no signiicant primary to secondary leaage. The discharge to the rier is monitored or radioactiity as speciied in Section 11.4. An alarm in the Main Control Room alerts the operator o an increasing radioactiity leel in the discharge. I the radiation setpoint is eceeded, the blowdown discharge is automatically dierted to the condensate demineralizers. The basis or the setpoint is presented in Section 11.4.References (1)ANSI/ANS-18.1-1984, Radioactie Source Term For Normal Operation o Light Water Reactors, December 31, 1984.

(2)WCAP-8253, Source Term Data or Westinghouse Pressurized Water Reactors, Westinghouse Electric Corp oration, Pittsburgh, Pa. 15230, April 1974.(3)WCAP-7664, R1 Radiation Analysis Design Manual Loop Plant, October 1972.

SURE TERMS 11.1-5WATTS BARTable 11.1-1 Parameters Used n The Calculation of Reactor CoolantFission and Corrosion Product istorical Design Actiities (Page 1 of 2)1.Core thermal power, MWt 2.Clad deects, as a percent o rated core thermal power being generated by rods with clad deects 3.Reactor coolant liuid olume, t 3 4.Reactor coolant ull power aerage temperature, F 5.Puriication low rate (normal) gpm 6.Eectie cation demineralizer low, gpm 7.Volume control tan olumesa.Vapor, t 3b.Liuid, t 3 8.Fission product escape rate coeicients*

a.Noble gas isotopes, sec

-1b.Br, I and Cs isotopes, sec

-1c.Te isotopes, sec

-1d.Mo isotopes, sec

-1e.Sr and Ba isotopes, sec

-1.Y, La, Ce, Pr isotopes, sec

-1 9.Mied bed demineralizer decontamination actorsa.Noble gases and Cs-134, 136, 137Y-90, 91 and Mo-99b.All other isotopes including corrosion products10.Cation bed demineralized decontaminationactor or Cs-134, 136, 137, Y-90, 91, Mo-993565 1.011,781588 75 7.52401606.5 10-81.3 10-81.0 10-92.0 10-91.0 10-111.6 10-12 1.010.010.0*Escape rate coeicients are based on uel deect tests perormed at the Saton Reactor. Eperience at two plants operating with uel rod deects has eriied the listed escape rate coeicients.

11.1-6SURE TERMS WATTS BAR11.Volume control tan noble gas stripping ractionsStriing Fractionsotoe r-85 r-85m r-87 r-88 Xe-131m Xe-133 Xe-133m Xe-135 Xe-135m Xe-138 2.3 X 10-5 2.7 X 10-1 6.0 X 10-1 4.3 X 10-1 7.1 X 10-3 1.6 X 10-2 3.7 X 10-2 1.8 X 10-1 8.0 X 10-1 1.012.Boron concentra tion and reduction ratesa.B o (initial cycle)B (initial cycle)b.B o (euilibrium cycle)B (euilibrium cycle)860 3.0 ppm/day1200 ppm 4.0 ppm/day13.Pressurizer olumesa.Vaporb.Liuid720 t 31080 t 314.Spray line low1.0 gpm15.Pressurizer stripping ractionsa.Noble gasesb.All other elements

1.0 0Table

11.1-1 Parameters Used n The Calculation of Reactor CoolantFission and Corrosion Product istorical Design Actiities (Page 2 of 2)

SURE TERMS 11.1-7WATTS BAR *Corrosion Product actiities based on actiity leels measured at o perating reactors.Table 11.1-2 Reactor Coolant quilibrium Fission AndCorrosion Product istorical Design ActiitiessotoeActiity Cigm Br-84 Rb-88 Rb-89 Sr-89 Sr-90 Sr-91 Y-90 Y-91 Y-92 Zr-95 Nb-95 Mo-99 I-131 I-132 I-133 I-134 I-135 Te-132 Te-134 Cs-134 Cs-136 Cs-137 Cs-138 Ba-140 La-140 Ce-144 Pr-144 r-85 r-85m r-87 r-88 Xe-131m Xe-133 Xe-133m Xe-135 Xe-135m Xe-138 Mn-54*

Mn-56*

Co-58*

Co-60*Fe-59*Cr-51*4.2 10-2 3.71.0 10-13.8 10-31.1 10-41.9 10-31.3 10-45.5 10-37.3 10-46.7 10-46.4 10-4 5.3 2.5 9.0 10-1 4.0 5.6 10-1 2.2 2.6 10-12.9 10-22.1 10-11.4 10-1 1.0 9.5 10-14.2 10-31.5 10-32.7 10-42.7 10-44.7 (Pea) 2.2 1.2 3.7 1.9 2.88 10 2 3.2 6.31.9 10-16.8 10-17.7 10-42.9 10-22.5 10-27.4 10-41.0 10-39.3 10-4 11.1-8SURE TERMS WATTS BARTable 11.1-3 quilibrium olume Control Tan istorical Design Actiities(ased on arameters gien in Table 11.1-1)sotoeaor actiity (Curies) r-85 r-85m r-87 r-88 Xe-131m Xe-133 Xe-133m Xe-135 Xe-135m Xe-138 7.65.6 10 12.2 10 11.1 10 28.8 10 11.4 10 41.5 10 22.5 10 2less than 1 4.6Liquid actiity (Curies)

I-131 I-132 I-133 I-134 I-135 1.1 0.41 1.8 0.26 1.0 SURE TERMS 11.1-9WATTS BARTable 11.1- Pressurier istorical Design Actiitiessotoeaor actiity

( Cicc)r-85 r-85m r-87 r-88 Xe-131m Xe-133 Xe-133m Xe-135 Xe-135m Xe-1385.1 10 11.0 10-11.8 10-21.2 10-1 4.73.6 10 2 1.8 6.5 10-15.0 10-42.2 10-3Liquid actiity

( Cigm)Rb-88Mo-99 I-131 I-132 I-1331.1 10-2 2.2 1.6 2.0 10-2 0.7 I-134 I-135 Cs-137 Cs-1385.5 10-3 0.14 1.3 5.5 10-3 11.1-10SURE TERMS WATTS BAR

• For two units, the actiities are doubled ** Represents the inentory o r-85 released to the reactor coolant during one year o ull power operation. The remaining isotopes are euilibrium alues.Table 11.1-5 istorical Design nentory n The aseous Waste Processing System Single UnitsotoeActiity*(Curies)r-85 r-85m r-87 r-88 Xe-131m Xe-133 Xe-133m Xe-135 Xe-135m Xe-1384.4 10 3**6.2 10 23.3 10 21.1 10 35.7 10 28.7 10 49.7 10 21.9 10 34.8 10 11.8 10 2 SURE TERMS 11.1-11WATTS BARTable 11.1- Parameters Used To Describe The Reactor Coolant System Realistic asisSymbolUnits ominal AS-1.1- 1 Assumtion WAnalysis AssumtionThermal powerPMWt 3400 3582Steam low rateFSlb/hr 1.5E+07 1.5E+07Weight o water in all reactor coolant systemWPlb 5.5E+05 5.4E+05Weight o water in all steamgeneratorsWSlb 4.50E+05 3.48E+05Reactor coolant letdown low rate(puriication)FDlb/hr 3.7E+04 3.7E+04Reactor coolant letdown low rate(yearly aerage or boron control)FBlb/hr 500 845Steam generator blowdown low(aerage total)FBDlb/hr 7.50E+04 3.00E+04Fraction o radioactiity inblowdown stream which is not returned to the secondary coolant systemNBD- 1.0 1.0Flow through the puriicationsystem cation demineralizerFAlb/hr 3.7E+03 3.7E+03Ratio o condensate demineralizerlow rate to the total steam low rateNC- 0.0 0.55Fraction o the noble gasactiity in the letdown stream

which is not returned to the reactor coolant system (not including the boron recoerysystem)Y- 0.0 0.0 11.1-12SURE TERMS WATTS BARTable 11.1- Secific Actiities n Princial Fluid StreamsRealistic asis (Cigm) (Page 1 of 2)ReactorSecondary Coolantsotoe CoolantWater Steam Class 1 oble ases r-85m r-85 r-87 r-88 Xe-131m Xe-133m Xe-133 Xe-135m Xe-135 Xe-137 Xe-138 1.71E-01 2.66E-01 1.61E-01 3.00E-01 6.54E-01 7.17E-02 2.53E+00 1.39E-01 9.04E-01 3.65E-02 1.29E-01 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 3.63E-08 5.51E-08 3.22E-08 6.31E-08 1.34E-07 1.54E-08 5.25E-07 2.90E-08 1.91E-07 7.62E-09 2.68E-08 Class 2 alogens Br-84 I-131 I-132 I-133 I-134 I-135 1.72E-02 4.77E-02 2.25E-01 1.49E-01 3.64E-01 2.78E-01 9.56E-08 1.41E-06 3.37E-06 4.03E-06 2.93E-06 6.19E-06 9.56E-10 1.41E-08 3.37E-08 4.03E-08 2.93E-08 6.19E-08 Class 3 Cs, Rb Rb-88 Cs-134 Cs-136 Cs-137 2.04E-01 7.39E-03 9.08E-04 9.79E-03 7.36E-07 4.58E-07 5.56E-08 6.11E-07 3.61E-09 2.36E-09 2.78E-10 3.05E-09 Class Water Actiation ProductsN-164.00E+011.29E-061.29E-07 Class 5 TritiumH-31.00E+001.00E-031.00E-03 SURE TERMS 11.1-13WATTS BARClass Other sotoes Na-24 Cr-51 Mn-54 Fe-55 Fe-59 Co-58 Co-60Zn-65 Sr-89 Sr-90 Sr-91Y-90 Y-91m Y-91Y-93 Zr-95 Nb-95Mo-99 Tc-99m Ru-103 Ru-106 Rh-103 Rh-106 Ag-110m Te-129mTe-129Te-131mTe-131 Te-132 Ba-137m Ba-140La-140 Ce-141 Ce-143 Ce-144 Pr-143 Pr-144W-187 Np-239 4.99E-02 3.26E-03 1.68E-03 1.26E-03 3.16E-04 4.84E-03 5.58E-04 5.37E-04 1.47E-04 1.26E-05 1.02E-03 1.26E-05 4.93E-04 5.47E-06 4.46E-03 4.10E-04 2.95E-04 6.75E-03 5.01E-03 7.89E-03 9.47E-02 7.89E-03 9.47E-02 1.37E-03 2.00E-04 2.57E-02 1.59E-03 8.26E-03 1.79E-03 9.79E-03 1.37E-02 2.64E-02 1.58E-04 2.96E-03

4.21E-03 2.96E-03 4.21E-03 2.65E-03 2.32E-03 1.86E-06 1.56E-07 7.80E-08 5.88E-08 1.44E-08 2.28E-07 2.64E-08 2.52E-08 6.84E-09 5.88E-10 3.52E-08 5.88E-10 4.34E-09 2.52E-10 1.50E-07 1.92E-08 1.32E-08 3.03E-07 1.40E-07 3.72E-07 4.44E-06 3.72E-07 4.44E-06 6.36E-08 9.36E-09 2.96E-07 6.60E-08 3.97E-08 7.98E-08 6.11E-07 6.25E-07 1.13E-06 7.32E-09 1.22E-07 1.92E-07 1.22E-07 1.92E-07 1.07E-07 1.02E-07 9.30E-09 7.56E-10 3.96E-10 3.00E-107.32E-11 1.13E-09 1.32E-10 1.20E-103.48E-11 3.00E-12 1.76E-10 3.00E-12 2.17E-11 1.32E-12 7.65E-10 9.48E-11 6.84E-11 1.45E-09 7.27E-10 1.92E-09 2.16E-08 1.92E-09 2.16E-08 3.24E-10 4.68E-11 1.48E-09 3.30E-10 2.05E-10 3.99E-10 3.05E-09 3.12E-09 5.60E-09 3.72E-11 6.23E-10 9.83E-10 6.23E-10 9.83E-10 5.40E-10 5.09E-10Table 11.1- Secific Actiities n Princial Fluid StreamsRealistic asis (Cigm) (Page 2 of 2) 11.1-14SURE TERMS WATTS BARTHIS PAGE INTENTIONALLY BLAN LIQUID WASTE SYSTEMS 11.2-1WATTS BAR11.2 LUD WAST SSTS11.2.1 DS OCTSThe Liuid Waste Processing System is designed to receie, segregate, process, and discharge liuid wastes. The system design considers potential personnel eposure and assures that uantities o radioactie releases to the enironment are as low as reasonably achieable. Under normal plant operation, the actiity rom radionuclides leaing the cooling tower blowdown (CTB) line is a raction o the limits in 10 CFR Parts 20 and 50.The plant is designed to stay within 10 CFR 20 radiological criteria during normal operation, een assuming euipment aults which could occur with moderate reuency, including uel cladding deects and ailures o up to two TPBARs (Unit 1 only) in combination with such occurrences as (1)Steam Generator tube leas (2)Malunction in Liuid Waste Processing System (3)Ecessie leaage in Reactor Coolant System Euipment (4)Ecessie leaage in Auiliary System EuipmentThe epected annual actiity releases (by isotope) are presented in Subsection 11.2.6, and the estimated doses are presented in Subsection 11.2.9. 11.2.2 SSTS DSCRPTOSThe Liuid Waste Processing System collects and processes potentially radioactie wastes or release to the rier. Proisions are made to sample and analyze luids beore they are discharged. Based on the laboratory analysis, these wastes are either released under controlled conditions ia the cooling tower blowdown or retained or urther processing. A permanent record o liuid releases is proided by analyses o nown olumes o waste. The system is shown on the Mechanical Flow Diagram (Figure 11.2-1.)The radioactie liuids discharged rom the Reactor Coolant System are processed by either the Chemical and Volume Control System (CVCS) holdup tans or Tritiated Drain Collector Tan (TDCT). Epected olumes to be processed by the Waste Processing System are gien in Table 11.2-1.The liuid Waste Processing System (WPS) consists o two main sub-systems processing tritiated and non-tritiated water. A system is proided or handling laboratory samples which may be tritiated and may contain chemicals. Much o the system is controlled or monitored rom a central panel in the Auiliary Building. Malunction o the system actuates an alarm in the Auiliary Building and a common alarm in the main control room (MCR). All liuid WPS euipment is located 11.2-2LIQUID WASTE SYSTEMS WATTS BARin or near the Auiliary Building, ecept or the reactor coolant drain tan and drain tan pumps containment pit sump and pumps Reactor Building loor and euipment drain sump and pumps Reactor Building loor and euipment drain pocet sump and pumps, which are located in the Reactor Building. A mobile demineralizer system is located and operated in the waste pacaging area.Fluid is sampled and analyzed to determine uantities o radioactiity, with an isotopic breadown, i necessary, be ore processing or disposal is attempted.At least two ales must be manually opened to permit discharge o liuid to the enironment. One o these ales is normally loced closed. A control ale trips closed on a high eluent radioactiity leel signal. Controls are proided to preent discharge without adeuate dilution.The liuid waste processing system is partly shared by the two units. Howeer, ecept or its containment isolation unction, the system seres no primary saety unction and the saety o either unit is not aected by such sharing. Liuid waste is processed, as necessary, through a mobile demineralizer.The Liuid Waste Processing System components that are not shared consist o one reactor coolant drain tan with two pumps, the containment pit sump with one pump, the Reactor Building loor and euipment drain pocet sump with two pumps, and the Reactor Building loor and euipment drain sump with two pumps. All o this euipment is located inside the containment o each unit.Shared ComonentsThe ollowing shared euipment is located inside the Auiliary Building one tritiated drain collector tan with two pumps and one ilter, one loor drain collector tan with two pumps and one ilter three waste condensate tans and two pumps a chemical drain tan and pump two laundry and hot shower tans and pump a spent resin storage tan a cas decontamination collector tan with two pumps and two ilters monitor tan with two pumps Auiliary Building loor and euipment drain sump and pumps one tritiated euipment drain sump with two pumps Auiliary Building passie sump a mobile demineralizer system, and the associated piping, ales and instrumentation. The ollowing shared components are located in the Turbine Building or receiing, processing, and transerring wastes rom the regeneration o condensate demineralizers high crud tans, pumps and ilter, a neutralization tan and pumps, and a non-reclaimable waste tan and pumps.The ollowing shared components are located in the waste pacaging area or receiing and processing liuid radwaste rom the loor drain and tritiated drain collector tans a mobile demineralizer system, including cation and anion ion echange resins, preilter, associated pumps, a endor supplied mobile demineralizer spent resin storage container, and associated piping and ales.

LIQUID WASTE SYSTEMS 11.2-3WATTS BARSearation of Tritiated and on-Tritiated LiquidsWaste liuids are normally separated into tritiated and non-tritiated liuids. Waste liuids which are high in tritium content (reactor coolant leao/leaage) are routed to the tritiated drain collector tan, while li uids low in tritium content (non-reactor coolant/raw water) are routed to the loor drain collector tan. The tritiated and non-tritiated liuids are processed or release to the rier.

Tritiated Water ProcessingTritiated water is processed or discharge to the rier. The water enters the liuid waste disposal system rom euipment leas and drains, ale leaos, pump seal leaos, tan oerlows, and other tritiated and aerated water sources.The euipment proided in this subsystem consists o a TDCT, pumps and ilter, reactor coolant drain tan and pumps the containment pit sump and pump the Reactor Building loor and euipment drain sump and pumps the Reactor Building loor and euipment drain pocet sump tritiated euipment drain sump, pumps and ilter. The primary unction o the tritiated drain collector tan is to proide suicient surge capacity or the waste processing euipment. The waste is primarily processed by the mobile demineralizer system.

on-Tritiated Water ProcessingNon-tritiated water is processed or discharge to the rier. The sources include loor drains, euipment drains containing non-tritiated water, certain sample room and radiochemical laboratory drains, laundry and hot shower drains and other non-tritiated sources. The euipment proided in this subsystem consists o pumps and ilter laundry and hot shower tans and pump laundry tan baset strainer waste condensate tans, pumps and ilter mobile demineralizer chemical drain tan and pump the Auiliary Building loor and euipment drain sump and pumps the Additional Euipment Building loor and euipment drain sump and pumps. Liuids entering the loor drain collector tan are normally rom low actiity sources and are normally processed through a mobile demineralizer system. The laundry and hot shower drains normally need no treatment or remoal o radioactiity. This water is collected in the laundry and hot shower drain tans. The inentory o these tans may be discharged directly to the cooling tower blowdown (ia the laundry tan strainer) or may be transerred to either the waste condensate tans or the cas decontamination collector tan or to the monitor tan or the FDCT (ia the laundry tan strainer) beore inal discharge to the cooling tower blowdown. Prior to discharge, a sample is taen and analyzed in accordance with plant procedures that implement the ODCM reuirements, and the water is discharged i the actiity leel is below ODCM limits.The blowdown rom the steam generators is routed to the CPDS or the hotwell (reer to Subsection 10.4.8) or discharged directly to the cooling tower blowdown line.Spent regenerant waste rom the CPDS is addressed below.

11.2-4LIQUID WASTE SYSTEMS WATTS BARobile Demineralier System Processing of Tritiated and on-Tritiated WasteFlow rom both the tritiated and nontritiated tans is routed to a Mobile Demineralizer System by use o the loor drain collector tan pumps, tritiated drain collector tan pumps, and gas stripper eed pumps.Processed water rom the system is routed to either the monitor tan or the CDCT. The contents o these tans are discharged as described in the two preious sections or processed urther, as necessary, to meet ODCM limits. The Mobile Demineralizer System remoes most soluble and suspended radioactie materials rom the waste stream ia ion echange and iltration. Once the resin and ilter media is epended, the spent resin is sluiced to either a liner or disposal or a Rad-Vault to accumulate enough resin or o-site disposa

l. The spent resin is dewa tered to meet the disposal site criteria.The ilters are stored in an appropriate container. Laboratory Samle Waste ProcessingThe chemical drain tan receies inputs rom the laboratory and the decontamination room. I the radioactiity leel is low and the chemical content is suitable or release, the tan contents can be discharged to the cooling tower blowdown line or release to the enironment. I analysis shows that there are no chemicals present which would be harmul to the demineralizer, the liuid is sent to the FDCT or processing. The tan contents may also be sent to the waste pacaging area or solidiication i reuired.Processing of Waste from Regeneration of Condensate Polishing Demineralier Wastes produced in the regeneration o the CPDS are processed or discharge or reuse. The high crud tans contain high crud, low conductiity waste (containing no regeneration chemicals) which are iltered and discharged when the radioactie leel does not eceed ODCM limits. When limits are eceeded, the high crud, low conductiity waste may be processed by the mobile demineralizer. The high crud tans may also contain regeneration chemicals i additional capacity is reuired. The tan would normally be processed by a endor i it conta ins regeneration chemicals . The neutralization and non-reclaimable waste tans contain low crud, high conductiity waste which is neutralized. I it contains radioactie material aboe ODCM limits, it is processed by a endor.Sent Resin ProcessingSpent resins are processed in accordance with Section 11.5.11.2.3 SST DS11.2.3.1 Comonent DesignA summary o principal design parameters are gien in Table 11.2-2. Design codes or the components o the Liuid Waste Processing System are gien in Chapter 3. Materials o the Liuid Waste Processing Syste m are selected to meet the material reuirements o the system and applicable codes. Parts o components in contact with borated water are normally abricated or clad with austenitic stainless steel. In addition pumps are normally proided with ent and drain connections. The mobile waste LIQUID WASTE SYSTEMS 11.2-5WATTS BARdemineralizer system is constructed to the applicable parts o Regulatory Guide 1.143, Reision 1, 1979.Reactor Coolant Drain Tan (RCDT) and PumsThe reactor coolant drain tan (one tan per unit) collects clean reactor coolant type water rom inside the reactor containment. Two pumps per unit are proided to transer the liuid rom the drain tan to the Chemical and Volume Control System holdup tans and to transer water rom the reueling canal to the reueling water storage tan or tritiated drain collector tan. The maimum load on the pumps occurs when the pressurizer relie tan drains and the ecess letdown low are imposed simultaneously or when the reueling canal is being drained. The normal load on the pumps is a small uantity, mainly rom leaos, although the ecess letdown low can be epected or relatiely long periods o time during plant heatup.Chemical Drain Tan and PumThe shared chemical drain tan receies radioactie wastes rom the radiochemical laboratory drains and rom the decontamination room. The pump is proided to transer the tan contents to the waste pacaging area or solidiication, CTB line, or the FDCT. Tritiated quiment Drain Sum and PumsTritiated Euipment Drain Sump and Pumps collect and transport tritiated liuid wastes rom euipment and lower eleation drains, which cannot drain by graity to the tritiated drain collector tan. Two pumps are urnished to transer the liuid collected to the tritiated drain collector tan. The sump ents to the building ehaust system.

Tritiated Drain Collector Tan (TDCT) and PumsThe shared tan collects radioactie liuids rom the primary plant which may contain tritiated water, boric acid and ission products. The primary unction o the tan is to proide suicient surge capacity or the waste processing system. Pump A is proided to transer the tan contents to the mobile waste demineralizer system or condensate demineralizer waste eaporator. Pump B is proided, as a spare, to also transer the tan contents.Floor Drain Collector Tan (FDCT) and PumsThe tan retains primarily non-reactor grade type luids and some non-recyclable reactor grade water rom certain drains in the Auiliary Building. The tan is euipped with three pumps. The tan contents may be sent through the FDCT discharge ilters. The liuids are processed through the mobile waste demineralizers and then collected in either the cas decontamination collector tan (CDCT) or the monitor tan. Ater the liuids are collected in one o these tans, the contents are recirculated, mied, sampled, and analyzed. I the radioactiity is within the discharge limits, the liuids are routed to the cooling tower blowdown or discharge.

11.2-6LIQUID WASTE SYSTEMS WATTS BAR Laundry and ot Shoer Tans and PumThe laundry and hot shower tans collect wastes rom th e radiologically controlled access area drains and hot shower drains. A pump is used to transer the liuid. A recirculation line is proided to permit miing the contents o the isolated tan beore taing samples or actiity analysis i the tan is to be discharged directly to the CTB. I the actiity leel is within discharge limits, the contents may be routed through the laundry baset strainer and discharged ia the CTB or the CDCT. I the actiity leel is aboe discharge limits, the contents are routed to the FDCT or routing to the mobile waste demineralizer or processing. Sent Resin Storage TanThis tan is supplied or the storage o used demineralizer resins. Resin is held in this tan to allow or decay o short-lied isotopes and to allow accumulation o enough resin or shipment. A layer o water is maintained oer the resins to preent degradation due to decay heat (see Section 11.5).

FiltersTable 11.2-2 lists the standard ilters reuired, their nominal ratings, and the material o the ilter media. The TDCT, FDCT, waste condensate tan, and CDCT ilters may be remoed and reinstalled as necessary to preent crud traps and particles rom building up in the piping.The methods employed to change ilters and screens are dependent on actiity leels. I the radiation leel o the ilter is low enough, it is changed manually. I actiity leels do not permit manual change, the spent cartridge is remoed remotely with temporary shielding to reduce personnel eposure.

The spent cartridge is placed in a shielded container or transport and storage prior to pacaging or shipment. onitor Tan and Cas Decontamination Collector Tan (CDCT)The Monitor Tan and the CDCT are used as release tans or liuid disposal. These tans receie processed liuid rom either the loor drain collector tan, the tritiated drain collector tan, or the CVCS hold up tans ia the mobile demineralizer. The CDCT may also receie liuid directly rom the laundry and hot shower tans. The CDCT may also receie water rom the spent uel shipping cas drain. The contents are pumped to the cooling tower discharge line ia the radwaste line i the actiity is suiciently low, and to the loor drain collector tan or returned to the mobile demineralizer or processing i the actiity is too high or discharge.onitor Tan Pum and Cas Decontamination PumTwo pumps are proided or each tan to recirculate and pump liuid. The CDCT processes the liuid through the cas decontamination ilter to the waste discharge line. Normally, only one pump is used.

LIQUID WASTE SYSTEMS 11.2-7WATTS BARWaste Condensate TansThe waste condensate tans are aailable or additional capacity to process eluent liuid rom the laundry and hot shower drain tans. Each o three tans are discharged to the waste condensate pumps. These tan are not normally used or Unit 1 or Unit 2 operation.Waste Condensate PumsTwo waste condensate pumps are aailable to receie liuid rom the waste condensate tans. This liuid may be processed to the CTB i it is below the ODCM limits. The discharge can be recirculated bac to the waste condensate tans, to the monitor tan, or to the cas decontamination collector tan.Condensate Polishing Demineralier Waste Processing quiment igh Crud (C) TansThese tans collect high crud, low conductiity waste produced during the bacwash phase o condensate polishing demineralizer regeneration. The high crud, low conductiity waste is iltered and is normally discharged to the cooling tower blowdown, processed to the Turbine Building sump or waste disposal, by the mobile demineralizer. The discharge (ater iltration) is ery near condensate uality and is discharged only i permissible discharge concentrations are not eceeded. The high crud tans may also contain regeneratie chemicals i additional capacity is reuired. The tan would normally then be processed by a endor.igh Crud PumsTwo pumps are proided to circulate the contents o the high crud tans or sampling, and to pump the tan contents through the high crud pre-ilter and high crud ilters.

Normally, only one pump is used.

igh Crud Pre-FiltersThree bag ilters are arranged in parallel upstream o the high crud ilter to ilter the discharge stream, thus reducing the loading and clogging o the high crud ilters. The essels are constructed o stainless steel with replaceable ilter elements. During normal operation two ilters are in serice. The third ilter which is on standby and isolated may be placed in serice while changing out the clogged ilters. Each essel has pressure gauges upstream and downstream o the ilters.eutraliation TanThis tan collects spent regenerant chemicals and rinses rom CPDS regeneration (low crud, high conductiity waste) miscellaneous waste rom the condensate polishing demineralizer sump and has the capability to receie and neutralize waste rom the cation and anion regeneration tans. Suluric acid or sodium hydroide is typically added to adust the pH. The tan contents are circulated during pH adustment. Ater neutralization to a desired pH alue, the tan contents are either processed to the non-reclaimable waste tan or discharged to the enironment.

11.2-8LIQUID WASTE SYSTEMS WATTS BAReutraliation Tan PumsTwo pumps are proided to circulate the contents o the neutralization tans and to transer the contents to the non-reclaimable waste tan or pump them to the enironment. Normally, only one pump is used.

on-Reclaimable Waste TanThis tan receies neutralized waste rom the neutralization tan. The tan contents are routed to discharge i the radioactiity content is suiciently low. I not, the contents are processed by a endor. on-Reclaimable Waste PumsTwo pumps are proided to pump contents o the non-reclaimable waste tan to discharge, to a endor or processing, or to the Turbine Building sump.Liquid Waste Processing System alesThe design code or the ales is ASME III Class 3 or ANS Saety Class 2b or 3 or Class 2 or ANS Saety Class 2a and ANSI B31.1, ANSI B16.5 or MSS-SP-66 or Non-Nuclear Saety (NNS) ales. The ales in the liuid waste processing system are stainless steel. The maority o the ales inoled are diaphragm ales. This type o ale proides positie control o stem leaage and is suitable or use as an isolation ale or in throttling serice. In seeral instances, globe ales are substituted or diaphragm ales because o their ability to control low oer a wider range.Vales are supplied or isolation o each maor euipment item or maintenance, to direct and control the low o waste through the system and or isolation o tans or

decay.For the purpose o containment isolation, trip ales are installed.Liquid Waste Disosal PiingThe piping design code is ASME III Class 3 or ANS Saety Class 2b or 3 or Class 2 or ANS Saety Class 2a and ANSI B31.1 or NNS. The piping is normally austenitic stainless steel and the piping oints are normally welded, ecept where langed connections are used at pump, ale and instrument connections to acilitate remoal or maintenance.Facilities for enting and DrainingNormally proisions hae been made or enting and draining euipment which may reuire maintenance during the plant lie. Vents and drains are normally proided either on the components themseles or in the pipe lines between the isolation ales. In general, each pipe line and component ent and drain is proided with a ale plus a bac-up leaage barrier o either a blan lange or a threaded screw cap.

LIQUID WASTE SYSTEMS 11.2-9WATTS BARobile Waste Demineraliation SystemThe mobile waste demineralization system (MWDS) consists o seeral essels with an associated pumping sid and leel control system. The MWDS normally processes liuids at a eed rate o approimately 40 gpm. Howeer, during pea low rates, the MWDS may process higher low rates (approimately 140 gpm). The essel headers hae inluent and eluent isolation ales and all piping is welded with long radius bends. Demineralizer essels are operated inside shielding in the waste pacaging area with a remote control panel to insure that the dose to personnel is within acceptable limits. The system is designed to the applicable portions o Regulatory Guide 1.143, Reision 1, 1979.The MWDS proides in-line processing o liuid radwaste through iltration and demineralization. The MWDS receies both tritiated liuid (the tritiated drain collector tan, high crud low conductiity waste, and CVCS holdup tan) and nontritiated liuids (the loor drain collector tan). Processed water rom the MWDS is sent to either the monitor tan or the CDCT or release to the rier.The liuid radwaste is processed through ion echange and iltration which remoe soluble and suspended radioactie materials rom the waste streams. The irst essel is normally loaded with a ilter media, such as actiated carbon, to proide initial iltration o the radwaste. This ilter medium remoes solids, cobalt isotopes, eisting in the orm o colloidal-sized suspended solids and cleaning agents, and other chemicals that can be remoed by absorption o the actiated carbon. A mechanical ilter loaded with ilter cartridges can be used or iltration. This conditions the radwaste or treatment in the subseuent tans.The subseuent demineralizer tans contain beds (anions and cations) o ion-echange resins, which remoe the soluble constituents o the waste stream. Once the resin and ilter media is epended, the resin is remoed rom the MWDS essels to either a liner or disposal or a RAD-Vault to accumulate enough resin or o-site disposal, and the ilters are placed in a shielded container or transport and storage prior to o-site disposal.Since the euipment or the MWDS is supplied by a endor and the selected endor may change rom time to time, a detailed description o the system is not possible. The speciic treatment steps and euipment used can also ary somewhat rom endor to endor.11.2.3.2 nstrumentation DesignThe Waste Disposal System panel, which is located in the Auillary Building, contains some o the controls and indications necessary to operate the system. Other controls and indicators are mounted near the euipment.

Alarms are shown separately on the WPS panel.

Most pumps are protected against loss o suction pressure by a control setpoint on the leel instrumentation or the respectie essels eeding the pumps.

11.2-10LIQUID WASTE SYSTEMS WATTS BARPressure indicators upstream and downstream o ilters proide local indications o pressure drops across each component. The radioactie eluent release monitoring instrumentation is described in Section 11.4.11.2. Oerating ProcedureThe euipment installed to reduce the actiity o radioactie e luents is maintained in good operating order and is operated to as low as reasonably achieable criteria, as stated in the ODCM. In order to assure that these conditions are met, administratie controls are eercised on oerall operation o the system preentie maintenance is utilized to ensure euipment is in optimum condition and applicable industry eperience and endor inormation aailable is used in planning or operation at Watts Bar Nuclear Plant.Administratie controls are eercised through the use o instructions coering such areas as ale alignment or arious operations, euipment operating instructions, and other instructions pertinent to the proper operation o the processing euipment. Discharge permits are utilized to assure proper procedures are ollowed in sampling and analyzing any radioactie liuid to be discharged and in assuring proper ale alignments and other operating conditions beore a release. These permits are signed and eriied by those personnel perorming the analysis and approing the release.Preentie maintenance is perormed in accordance with approed plan t maintenance program procedures deeloped, considerin g applicable operating and maintenance eperience as well as endor inormation.Operation o the Liuid Waste Processing System is essentially the same during all phases o normal reactor plant operation the only dierences are in the load on the system. The ollowing sections discuss the operation o the system in perorming its arious unctions. In this discussion, the term normal operation should be taen to mean all phases o operation ecept operation under emergency or accident conditions. The Liuid Waste Processing Systems only primary saety unction is containment isolation.Liquid Waste Processingormal OerationDuring normal plant operation the system processes liuid rom the ollowing sources (1)Euipment drains and leas (2)Radioactie chemical laboratory drains (3)Radioactie laundry and shower drains (4)Decontamination area drains (5)Demineralizer lushing, bacwashing and regeneration o resin LIQUID WASTE SYSTEMS 11.2-11WATTS BAR (6)Sampling systemThe system also collects and transers liuids rom the ollowing sources directly to the reactor coolant drain tan or processing in the CVCS.

(1)Reactor coolant loops (2)Pressurizer relie tan (3)Reactor coolant pump secondary seals (4)Ecess letdown during startup (5)Accumulators (6)Vale and reactor essel lange leaos

()Reueling canal drainsThe liuid lows to the reactor coolant drain tan and is discharged directly to the CVCS holdup tans by the reactor coolant drain pumps which are operated automatically by a leel controller in the tan. These pumps can also return water rom the reueling caity to the reueling water storage tan. Ther e is one reactor coolant drain tan with two reactor coolant drain pumps located inside containment.

Normally, the reactor coolant drain pumps are operated in the automatic mode, which allows pump operation and reactor coolant drain tan leel to be controlled. The pumps can also be operated manually to control the tan leel.Where possible, waste liuids drain to the waste disposal system and tritiated drain collector tans by graity low.Searation of Tritiated and on-tritiated LiquidsWaste liuids which are high in tritium content are routed to the tritiated drain collector tan, while liuids low in tritium content are routed to the loor drain collector tan. The tritiated and non-tritiated liuids are processed or release to the rier.

Tritiated WaterTritiated water enters the liuid waste disposal system ia euipment leas and drains, ale leaos, pump seal leaos, tan oerlows, and other tritiated and aerated water sources.The tritiated liuids rom euipment leas and drains, and ale lea-os which are below the tritiated drain collector tan, are drained to the sump and are pumped rom there to the tritiated drain collector tan. Normally, the sump pumps are operated in the automatic mode, which allows tan leel to be controlled. The pumps can also be

operated manually.

11.2-12LIQUID WASTE SYSTEMS WATTS BARThe liuid collected in the tritiated drain collector tan contains boric acid and ission product actiity. The liuid collected is normally demineralized by the mobile waste demineralizer and is then analyzed and discharged to the rier.

on-Tritiated WaterNon-tritiated water sources include loor drains, euipment drains containing non-tritiated water, certain sample room and radiochemical laboratory drains, laundry and hot shower drains and other non-tritiated sources.The liuids entering the loor drain collector tan are primarily rom low actiity sources. The liuid collected is normally demineralized by the mobile waste demineralizer and is then analyzed and discharged to the rier. Laundry and ot Shoer DrainsOne o the two laundry and hot shower tans is aled to receie waste at all times. When one tan is illed, it is aled out and the other tan is aled in. The ull tan is then aligned with the laundry pump to mi the waste by recirculation. A sample is taen (i reuired) rom a local sample connection to determine what subseuent handling o the waste liuid is reuired. Normally no treatment is reuired or remoal o radioactiity. This water is transerred to either CTB or FDCT or to CDCT or to the waste condensate tans or to the monitor tan (all ia the laundry tans strainer). A sample is taen and, ater analysis, the water is discharged in accordance with the ODCM limits. Laboratory SamlesLaboratory samples which contain chemicals used in analysis are normally discarded in a ume hood sin which drains to the chemical drain tan.The operation o the chemical drain tan pump and control o the tan leel is manual, with the eception that the pump is shut o automatically on low tan leel.Low actiity drains rom the laboratory, such as lush water, are normally routed to the loor drain collector tan. Ecess tritiated samples not contaminated by chemicals during analysis are normally directed to the tritiated drain collector tan.Shiing Cas DrainsLiuid in this area is drained to the CDCT. The liuid is epected to be low enough in radioactiity content that it can be discharged without processing. Following analysis, the liuid is discharged. In the unliely eent that the radioactiity leel is such that urther processing is reuired, the liuid may be transerred to the loor drain collector tan or returned to the Mobile Waste Demineralizer System or urther processing.Condensate Polishing Demineralier WasteThe condensate polishing demineralizer system (CPDS) is described in Section 10.4.6. Section 10.4.6 includes a discussion o the regeneration process. Treatment o regeneration wastes is describ ed in this section.

LIQUID WASTE SYSTEMS 11.2-13WATTS BARThe CPDS regeneration subsystem is designed to separate wastes into two ractions - one, a high-crud, low-conductiity liuid and the other, a low-crud, high-conductiity liuid. These ractions are collected in separate tans. The irst raction results rom bacwash which precedes chemical regeneration and rom rinses which ollow chemical regeneration. The second raction consists o neutralized chemical regenerants plus displacement water. At each regeneration, the olume o the irst raction is about 23,000 gallons, and that o the second raction is about 10,000 gallons.Treatment of igh-Crud, Lo Conductiity (CLC) Waste The high-crud waste is normally low in conductiity. This waste is processed in euipment located in the Turbine Building. The slurry is iltered in the HC pre-ilter or HC ilter. The iltrate radioactiity is low enough to achiee adeuate dilution in the cooling tower blowdown, in accordance with the ODCM, and is normally discharged.

I the waste can not be properly diluted, it can be routed to the mobile demineralizers or urther processing. Following a ilter run in the HC ilter, the ilter is bacwashed and the liuid is routed to the HC tan.Treatment of Lo-Crud, igh-Conductiity (LCC) WasteThe LCHC wastes, consisting o the spent regeneration chemicals is neutralized in a neutralizer tan and may be transerred to a non-reclaimable waste tan. The liuid is normally processed by a endor i the radioactiity is aboe the ODCM limit. Howeer, the liuid is circulated and sampled prior to processing. I the radioactiity leel is below permissible discharge leels, it may be discharged directly without urther treatment.

Discharge of Regeneration WastesWaste liuids rom the CPDS regeneration that are to be discharged are sampled and analyzed as reuired per the ODCM to ensure that the actiity leel complies with reuirements stated in the ODCM. The discharge line rom the Turbine Building etends to the cooling tower blowdown line, and includes a loced-closed ale, a radiation monitor, and a radiation-controlled ale. The latter is arranged to close on a high radiation signal rom the monitor. It is closed also by a signal rom the low meter in the cooling tower blowdown line on low low, indicating inadeuate dilution low.Sent Resin andlingThis portion o the system sluices resin rom the demineralizers and transports resin rom the spent resin storage tan to the railroad access bay to be dewatered or solidiied by an osite contractor.CCS Resin SluicingSpent resins are initially luidized by baclushing with primary water. The baclush water is routed to the tritiated drain collector tan.The resin is then drained and lushed to the spent resin storage tan. Fresh resin is then added and the demineralizer is illed with water, as a coer, oer the resin. The 11.2-14LIQUID WASTE SYSTEMS WATTS BARales are then realigned or normal process operation. A negligible amount, i any, o resin is epected to remain in a demineralizer ater lushing, as the demineralizers are completely lushable.

RefuelingOperation o the Liuid Waste Processing System is the same during reueling as during normal operation. When reueling is complete, the water remaining in the reueling canal ollowing normal drain-down by the Residual Heat Remoal System is drained to the reactor coolant drain tan and pumped bac to the reueling water storage tan with the reactor coolant drain tan pumps. The pumps normally operate in the automatic mode during this operation. Since there is oygen in the reueling water, the drain tan is isolated rom the ent header during this transer and the tan is ented to the containment atmosphere. It is necessary to purge the tan with nitrogen beore connecting it bac to the ent header.Faults of oderate FrequencyThe system is designed to handle the occurrence o euipment aults o moderate reuency such as (1)Malunction in the Liuid Waste Processing SystemMalunction in this system could include such things as pump or ale ailures. Because o pump standardization throughout the system, a spare pump can be used to replace most pumps in the system. There is suicient surge capacity in the system to accommodate waste until the ailures can be ied and normal plant operation resumed.

(2)Ecessie Leaage in Reactor Coolant System EuipmentThe system is designed to handle a one gpm reactor coolant lea in addition to the epected leaage during normal operation. Operation o the system is almost the same as or normal operation ecept the load on the system is increased. A one gpm lea into the reactor coolant drain tan is handled automatically but will increase the load actor o the CVCS. I the one gpm lea enters the tritiated drain collector tan, operation is the same as normal ecept or the increased load on the system. Abnormal liuid olumes o reactor coolant resulting rom ecessie reactor coolant or auiliary building euipment leaage (1 gpm) can also be accommodated by the loor drain collector tan and processed by the non-tritiated system. Vale and pump leaos are all processed through the tritiated drain collector tan and non-reusable reactor coolant entering the loor drain collector tan is processed or release to the rier.

(3)Ecessie Leaage in Auiliary System EuipmentLeaage o this type could include water rom steam side leas inside the containment which are collected in the Reactor Building loor and euipment drain sump. Although the sump pump discharge is normally routed to the LIQUID WASTE SYSTEMS 11.2-15WATTS BARtritiated drain collector tan, the low can be dierted to the loor drain collector tan upon discoery o a lea. Other sources could be component cooling water leas, essential raw cooling water leas, and secondary side leas. This water enters the loor drain collector tan and will be processed

and discharged as during normal operation.

(4)Steam Generator Tube LeasDuring periods o operation with uel deects, coincident with steam generator tube leas, radioactie liuid is discharged ia the steam generator blowdown system. The releases rom the secondary side will be within the ODCM limits.Releases of WasteRelease o radioactie liuid out o the Liuid Waste Processing System is rom the waste condensate tans, cas decontamination collector tan, monitor tan, chemical drain tan, and laundry and hot shower tan to the blowdown line rom the cooling towers. The cooling tower blowdown line discharges into the rier through the diuser pipes. Liuid wastes rom the condensate polishing demineralizer system are released rom the high-crud tans, the non-reclaimable waste tan, and the neutralization tan.The condenser circulating water system operates in the closed cycle mode. Water is recirculated between the cooling towers and the condenser. The cooling towers blowdown lows to the diuser in order to maintain the solids in the water at an acceptable leel.Release o the radioactie liuids rom the liuid waste system is made only ater laboratory analysis o the tan contents. I the actiity is not below ODCM limits, the liuid waste streams are returned to waste disposal system or urther processing by the mobile demineralizer. Once the luids are sampled, they are pumped to the discharge pipe through a normally loced closed manual ale and a remotely operated control ale, interloced with a radiation monitor and a low element in the cooling tower blowdown line. This assures that suicient dilution low is aailable or the discharge o radioactie liuids. The minimum dilution low reuired or discharge o radioactiity into the cooling tower blowdown lines (CTBL) is 20,000 gpm.A similar arrangement is proided or wastes discharged ro m the condensate polishing demineralizer system. A radiation monitor on this system and a low element on the cooling tower blowdown are interloced with a low control ale in the system discharge line. Release o wastes is automatically stopped by either a high radiation signal or a signal which indicates that inadeuate dilution low is aailable. The CPDS and SGB may be released with the CTB low less than 20,000 gpm proided the sum o the Eluent Concentration Limit (ECL) ractions (release concentrations/10 CFR 20 ECLs) or all isotopes released is less than or eual to 10 as reuired by the Technical Speciications and ODCM, and proided such releases are controlled and limited such that the 10 CFR 50, Appendi I limits are not eceeded.

11.2-16LIQUID WASTE SYSTEMS WATTS BARThe steam generator blowdown system also may discharge radioactie liuid. Liuid waste rom this system is not collected in tans or treatment, but is continuously monitored or radioactiity and may discharge to the cooling tower blowdown, or recirculated to the condensate system upstream o the condensate demineralizers. Reer to Section 10.4.8 or a description o the steam generator blowdown system operation.The turbine building sump collects liuid entering the turbine building loor drain system. When the sump is nearly ull (approimate usable capacity o 30,000 gallons), the liuid is pumped to either the low olume waste treatment (LVWT) pond or the yard holding pond. Water in the ponds drains by graity to the rier ia the cooling tower blowdown line to the diusers. I high concentrations o chemicals are present, it may be pumped to the lined or unlined chemical holdup ponds or treatment beore release per the NPDES Permit.Station lacoutThe Liuid Waste Processing System (ecept or containment isolation) does not normally operate during a blacout. I necessary, euipment with diesel bacup power can be manually connected to the emergency power sources when they become aailable.Loss-of-Coolant AccidentThe Liuid Waste Processing System (ecept or containment isolation) is not reuired to operate during, or immediately ollowing, a loss-o-coolant accident. Euipment may be started manually as reuired.Oerating erienceDemineraliersOperational data on CPDS decontamination actors (DF) is deried rom NUREG0017, Reision 1 Re. 1. The DF or MWDS was supplied by a endor.11.2.5 PRFORAC TSTSInitial perormance tests were perormed to eriy the operability o the components, instrumentation and control euipment and applicable alarms and control setpoints.The speciic obecties were to demonstrate the ollowing (1)Pumps are capable o producing low rate and head as reuired.

(2)Waste ilters are capable o passing reuired low rate.

(3)Instrumentation, controllers, and alarms operate satisactorily to maintain leels, pressures, and low rates and indicates, records, and alarms, as reuired.

LIQUID WASTE SYSTEMS 11.2-17WATTS BAR (4)Sampling points are aailable or sampling.

During reactor operation, the system is used at all times and hence is under sureillance. Data is taen periodically (i applicable) or use in determining decontamination actors o demineralizers.11.2. STATD RLASS11.2..1 RC RequirementsThe ollowing documents hae been issued to proide regulations and guidelines or release o radioactie liuids (1)10 CFR 20, Standards or Protection Against Radiation.

(2)10 CFR 50, Licensing o Production and Utilization Facilities.11.2..2 Westinghouse PWR Release erienceThe liuid releases are highly dependent upon administratie actiities which control the use o water or decontamination, euipment and loor rinsing and other uses in the controlled areas.Operating plants hae reported liuid discharges as shown in Table 11.2-3.11.2..3 ected Liquid Waste Processing System ReleasesThe uantities and isotopic concentration in liuids assumed discharged to the liuid waste processing system, and hence the releases to the enironment, are highly dependent upon the operation o the plant. The radionuclide concentrations and calculated doses are the principal ocus o treatment actiities. Volume released is a secondary ocus. The analysis or Watts Bar is based on engineering udgement, with respect to the operation o the plant and the liuid waste processing system, and realistic estimation o the potential input sources. Hence, the results are representatie o typical releases rom the Watts Bar liuid waste processing system.The input sources, the computational data and assumptions are summarized in Table 11.2-1. The isotopic composition o reactor coolant (RC) is based on ANSI/ANS-18.1-1984 and includes the proected tritium permeation rom 2,304 TPBARs (Unit 1 only). The associated releases in curies per year per nuclide are gien in Table 11.2-5.The liuid waste processing system is assumed to operate as described in Subsection 11.2.4.11.2.. Turbine uilding (T) Drains11.2...1 PuroseThe TB drainage system is designed to remoe liuid drainage in the Turbine Building.

11.2-18LIQUID WASTE SYSTEMS WATTS BAR11.2...2 DescritionThe TB drains are not normally radioactie.The Turbine Building drainage consists o the ollowing categories

()Condensate Polishing Demineralizer System Drains

()Other TB drainage

()Oil and oily water drainage.11.2...2.1 Condensate Polishing Demineralier System DrainsThe Condensate Polishing Demineralizer System (CPDS) area is sericed by separate loor and euipment drains. The drains or CPDS are routed to the Condensate Demineralizer sump where they are pumped to the Neutralization Tan (NT). These drains hae a potential to be low-leel radioactie during periods o primary to secondary leaage. The NT is proided with the capability o adusting pH, and i the inentory is not radioactie or less th an the dischargeable limit , it is normally discharged with a batch release to the CTB line. The NT is normally processed by a endor i the inentory is aboe dischargeable limits. Any radioactie discharge rom this release point is handled in accordance with the ODCM. Section 10.4.6 discusses the CPDS, and this chapter discusses the wastes rom the system and their disposal under radioactie and non-radioactie conditions.11.2...2.2 Other Turbine uilding DrainageDrainage rom the Turbine Building areas other than the CPDS area is directed to the yard holding pond, normally, ia the low olume waste treatment (LVWT) pond. Floor and euipment drainage in Turbine Building is irst collected in the Turbine Building Station sump and is then pumped to the yard holding pond, normally, ia the LVWT pond. Roo drainage lows by graity directly to the yard holding pond.11.2...2.3 Oil and Oily Water Drainage Oil is drained directly to drums or tan trucs or reuse or remoal rom the plant. Oily water drains are urnished in the Turbine Building and are routed to the oil sump which is located in the low point o the Turbine Building. Oil may be accumulated in the sump until a suicient amount is collected to be pumped into tan trucs or osite disposal.11.2..5 stimated Total Liquid Releases10 CFR 50 Appendi I and 10 CFR 20 prescribe the allowable limits o radionuclide liuid releases rom Watts Bar. The Osite Dose Calculation Manual is the process document that describes how releas es are measured, monitored, controlled and reported. The liuid waste management system at Watts Bar can be operated in a ariety o conigurations depending on plant conditions and the amount and composition o radionuclides in the waste stream. Irrespectie o the speciic modes described, the annual releases are reuired to be eual to or less than the limits proided in the ODCM, Appendi I and 10CFR 20.

LIQUID WASTE SYSTEMS 11.2-19WATTS BARTable 11.2-5 proides the total annual discharge rom the liuid waste processing system or our dierent leels o processing prior to discharge.

The annual discharge or Unit 2 is epected to be similar to Unit 1 with the eception that tritium production is not currently planned. A alue o 0.16 Ci/yr is included as an unplanned release in each o the plant alignment to proide additional conseratism as discussed in NUREG-0017. The discussions to ollow are based on the luid uantities and actiities speciied in Table 11.2-1.11.2..5.1 ected ormal Plant OerationThe epected plant alignment and the resultant our release paths are as ollowsCVCS letdown waste processed by the CVCS demineralizers and then by the mobile demineralizer. The reactor coolant drain tan, the tritiated drain collector tan, and the loor drain collector tan discharges and processed using the mobile demineralizer.Liuid releases rom the Laundry and Hot Shower Drain Tan and the Turbine Building drains can be released without processing by mobile demineralizer.The combination o the aboe three paths is called liuid radwaste.Steam Generator Blowdown released without processing.The results or this alignment are shown in Column 8 o Table 11.2-5. Column 8 is the combined source term rom Column 6 and 7. Column 6 proides the liuid radwaste source term. Column 7 proides the source term or steam generator blowdown assuming an annual untreated SG Blowdown concentration o 3.65 E-5 uCI/cc. Concentrations aboe this alue cannot be released continuously on an annual basis without additional processing. Unit 1 currently operates without the condensate demineralizers in serice. The condensate demineralizers will not be utilized unless signiicant primary to secondary leaage occurs. Operating eperience has shown that annual releases are below the alues shown in Column 8 and thus that processing o SG Blowdown is not epected to be reuired. There is no condensate demineralizer blowdown or bacwashing when the plant is operating under this set o conditions. SG Blowdown concentrations aboe 3.65E-5 uCi/cc can be released without processing by the condensate demineralizers or short periods o time and are acceptable as long as total releases rom the site are below the ODCM and 10 CFR limits.The epected liuid releases rom Watts Bar based on the alues in Column 8 are below the limit o 5 Curies per year as prescribed in 10 CFR 50, Appendi I. Table 11.2- 5d shows releases remain within the 10CFR 20 limits i the steam generator blow down concentration is restricted to a maimum concentration o 3.65E-5 uCi/cc gross gamma during the release.11.2..5.2 Other Plant Alignment aluationsThe alues in Table 11.2-5 Column 4 assume the ollowing 11.2-20LIQUID WASTE SYSTEMS WATTS BARCVCS letdown waste processed by the CVCS demineralizers and then by the mobile demineralizer. The reactor coolant drain tan, the tritiated drain collector tan, and the loor drain collector tan discharges and processed using the mobile demineralizer.Condenstate Demineralizer Flow including SG Blowdown processed by the condensate demineralizer.Liuid releases rom the Laundry and Hot Shower Drain Tan and the Turbine Building drains can be released without processing by mobile demineralizer.The alues in Table 11.2-5 Column 5 assume the ollowingCVCS letdown waste processed by the CVCS demineralizers and then by the mobile demineralizer. The reactor coolant drain tan, the tritiated drain collector tan, and the loor drain collector tan discharges and processed using the mobile demineralizer.Condensate Demineralizer Flow including SG Blowdown processed by the condensate demineralizer with additional processing by the mobile demineralizer.Liuid releases rom the Laundry and Hot Shower Drain Tan and the Turbine Building drains can be released without processing by mobile demineralizer.The epected liuid releases rom Watts Bar based on the alues in columns 4 and 5 are well below the limit o 5 Curies per year as prescribed in 10 CFR 50, Appendi I.

Tables 11.2-5a and 11.2-5b describe liuid releases or 1 ailed uel or both treated and untreated waste relatie to the reuirements o 10 CFR 20.1302(b). The sum oer all isotopes o the concentrations/ECL (C/ECL) alue rom the Table 11.2-5a is greater than unity or the case where all isotopes are at design alues and the released liuid is not processed by the Mobile Demineralizers. In order to preent eceeding the 10 CFR 20.1302(b) limits, the condensate regeneration waste is rerouted through the Mobile Demineralizers i the long term releases rom the condensate regeneration waste is greater than the 10 CFR 20 concentration limits. With Mobile Demineralizer processing o condensate regeneration waste, the release co ncentrations are shown in Table 11.2-5b and are less than the limits speciied in 10 CFR 20.1302(b). Based on the aboe, the releases rom the plant are in accordance with the design obecties as outlined in Section 11.2.1 and the Osite Dose Calculation Manual.11.2. RLAS POTSAll radioactie liuid wastes are released rom the plant through the cooling tower blowdown line. The discharge points rom the waste disposal system are shown in Figure 11.2-1 and 11.2-2. The connection to the cooling tower blowdown line is shown in Figure 10.4-5.

LIQUID WASTE SYSTEMS 11.2-21WATTS BAR11.2. DLUTO FACTORSThe dosimetry calculations or drining water are based on the assumption that the liuid eluent will be mied with 10 o the rier low between the point o discharge and Tennessee Rier Mile (TRM) 510.0, where 100 dilution is assumed to occur. Further discussion o these calculations and dilution lows used is presented in section 11.2.9.1. 11.2. STATD DOSS FRO RADOUCLDS LUD FFLUTSDoses rom the ingestion o water, rom the consumption o ish, and rom shoreline recreation are calculated or eposures to radionuclides routinely released in liuid eluents.11.2..1 Assumtions and Calculational ethodsInternal doses are calculated using methods outlined in NRC Regulatory Guide 1.109, Reision 1, October 1977. This model is used or estimating the doses to bone, gastro-intestinal (G.I.) tract, thyroid, lier, idney, lung, sin, and total body o man rom ingestion o water, consumption o ish, and rom eternal eposures due to recreational actiities. Population doses are estimated or the year 2040 based on the populations gien in Table 2.1-12.

(1)Doses to Man rom the Ingestion o WaterData listed in Table 11.2-6 or public water supplies is used to calculate dose commitments rom the consumption o Tennessee Rier water. The 2040 populations or the water supplies are estimated by multiplying the 2000 public water supply populations by a population growth actor o 1.42. This actor is the ratio o the 2040 population (Table 2.1-12) to the 2000 population (Table 2.1-8). It is assumed that the plant eluent is mied with one-tenth o the rier low in the 18-mile reach between the nuclear plant site and TRM 510.0. Although natural water turbulence will continue to increase the dispersion downstream, it is assumed that one-tenth dilution is maintained as ar as TRM 510.0, where ull-dilution is assumed.Dilution is calculated using aerage annual low data or the Tennessee Rier as measured during the 69-year period 1899-1968. The aerage low past the site is approimately 28,000 t 3/sec.Radioactie decay between the time o intae in a water system and the time o consumption is handled in accordance with Regulatory Guide 1.109. Maimum and aerage consumption rates are those recommended by Regulatory Guide 1.109.Due to a lac o deinitie data, no credit is taen or remoal o actiity rom the water through absorption on solids and sedimentation, by deposition in the biomass, or by processing within water tre atment systems.

11.2-22LIQUID WASTE SYSTEMS WATTS BARInternal doses, D, or an organ or a single radionuclide are calculated using the relationD = DCF I(1) where DCF = the dose commitment actor or the organ rom the radionuclide (mrem/pCi). Values used are rom Regulatory Guide 1.109.I = the actiity o the radionuclide taen into the body annually ia ingestion, (pCi).

(2)Dose to Man rom the Consumption o FishCurrent estimates o the Tennessee Rier ish harest are 3.04 lb/acre/year. It is assumed that the rates will increase with the population epansion, so the dose calculations are based on harests o 3.77 lb/acre o ish in the year 2040. This is determined by multiplying the 1990 harest by the population growth actor. The Tennessee Rier, within 50 miles downstream o WBN, is segmented into 4 regions (Table 11.2-6) in order to acilitate the calculations o ish harests and radioactiity concentrations. The radioactiity leels in the ish rom each region are estimated by the product o an aerage actiity concentration in the reach and a concentration actor or each radionuclide. The population dose is calculated using the assumption that all o the 3.77 lb/acre o ish caught is edible weight, and that the total harest rom each portion o the rier is consumed by humans.Dose commitments are calculated with Euation 1, which is discussed or water ingestion in the preious section.Calculations indicate that there would be no signiicant radiological impact rom human utilization o shellish. Shellish are not currently being harested commercially in the Tennessee Rier and consumption o shellish by

humans is assumed to be negligible.

(3)Doses to Man due to Shoreline RecreationEstimates o the doses rom shoreline recreation along the Tennessee Rier are calculated or each radionuclide using the ollowing euationD = RDCF C T (mrem),

where RDCF = The shoreline recreation dose commitment actor, mrem/hour per pCi/m 2, rom Regulatory Guide 1.109, Table E-6.T = eposure time, hours.

LIQUID WASTE SYSTEMS 11.2-23WATTS BARC = Concentration o the radionuclide in the sediment, pCi/m 2 calculated using NRC Regulatory Guide 1.109 methodology. A shoreline width actor o 0.2 is used.

Doses to the population are calculated using estimates or shoreline isits (1990 alues) multiplied by the population growth actor. 11.2..2 Summary of Dose from Radionuclides in Liquid ffluentsRadiation doses calculated or releases o radionuclides in liuid eluents during normal operation o the Watts Bar Nuclear Plant are summarized in Table 11.2-7. Lier tissues are epected to receie the greatest doses or the maimum indiidual howeer, the thyroid tissues are epected to receie the greatest dose or the Tennessee Valley population.REFERENCES (1)NUREG-0017, R1, Calculation o Releases o Radioactie Materials in Gaseous and Liuid Eluents rom Pressurized Water Reactors, a PWR-GALE Code, Published April, 1985.

11.2-24LIQUID WASTE SYSTEMS WATTS BARTable 11.2-1 Liquid Waste Processing SystemCalculation asis(Page 1 of 2)1.nuts (2 Units)1.1Reactor Coolant Drain TanTan Volume 350 gal/unit Input 40 gpd14,600 gal/yrActiity 0.1 PCA Collection Time 24 hrs Processing Time neglected1.2Tritiated Drain Collector TanTan Volume 24,700 gal Input 2,980 gpd 1,087,000 gal/yrActiity See Section 3.0Collection Time 24 hrsProcessing Time 6 hrs1.3Floor Drain Collector TanTan Volume 23,000 galInput 3,200 gpd 1,168,000 gal/yrActiity See Section 3.0 Collection Time 24 hrs Processing Time 6 hrs1.CCS LetdonInput4,863 gpd 1,775,107 gal/yrActiity 1.0 PCACollection Time24 hrsProcessing Time6 hrs1.5Chemical Drain Tan Laundry and ot Shoer TanInput 1080 gal/day (NUREG-0017 Table 1-3) 394,200 gal/yrActiity NUREG-0017 Table 2-27 Released without processing or decay1.Condensate Polisher Regeneration WasteInput 6,800 gpd o waste (NUREG-0017 Table 1-3) 2,482,000 gal/yr Actiity See Section 3.01.Steam enerator lodonInput 60,000 lb/hr (365 days)Actiity See Section 3.0 LIQUID WASTE SYSTEMS 11.2-25WATTS BAR1.aseous ActiityAll noble gases ent to gaseous waste processing system. All halogens remain in liuid.2.Processing2.1Decontamination Factors ecept mobile demineralizer system based on NUREG-0017 Re 1 Table 1-42.2CVCS letdown irst processed through CVCS mied bed and cation demineralizersDF = 20 or Cs RbDF = 100 or all others2.3 All processing through mob ile demineralizer systemDF = 1000 or all isotopes ecept Cobalt 58 based on ie (5) beds. The irst is loaded with ion speciic iltration media/actiated carbon, ollowed by another ion speciic media, a cation bed, and then two (2) mied beds in series.Flow rate 40 gpm DF = 100 or Co583.Leaage 1 a)b) c)

d) e)

f) g)

h)i)))l)1.2.

3..Reactor coolant pump seal leaage, 20 gal/day 0.1 PCAReactor containment cooling system, 500 gal/day 0.001 PCA 2Other leas and drains, 10 gal/day 1.67 PCA 2Primary coolant euipment drains, 80 gal/day 1.0 PCA 2Reactor coolant sampling, 200 gal/day 0.05 PCA 2Spent uel pit liner drains, 700 gal/day 0.001 PCA 2Auiliary Building loor drains, 200 gal/day 0.1 PCA 3Secondary system sampling, 1400 gal/day 1 PCA(o SSC)(Note NUREG-0017 uses 1E-4 PCA (RC), this calculation uses actual SSC actiities, thereore PCA = 1 SSC) 3CVCS letdown (ia holdup tans), 845 lb/hr (2431.654 gal/day) 1 PCAInput into the condensate resin regeneration waste (with resin DF=2 or Cs, Rb, and DF=10 or others) collected oer a 6-day time period consisting o1)SGBD blowdown = 3E4 lb/hr (86330.93 gal/day) 1 PCA (o SSC)2)Condensate low = 1.5E7 lb/hr (steam low)*0.55(low split)=8.25E6 lb/hr 1 PCA (o SSS)Turbine Building loor drains, 7200 gal/day 1 PCA (o SSC) (Note no reactor coolant in Turbine Building).

LHST release taen directly rom NUREG-0017 Table 2-27.The leaage alues are or 1 Unit.Normally processed to TDCT.Normally processed to FDCT. Tabulated inputs are based on dual unit system use unless otherwise noted.Table 11.2-1 Liquid Waste Processing SystemCalculation asis(Page 2 of 2) 11.2-26LIQUID WASTE SYSTEMS WATTS BARTable 11.2-2 Comonent Design Parameters*(Page 1 of )Reactor Coolant Drain Tan Number per unitType Volume, gal Design pressure, internal, psigDesign pressure, eternal, psig

Design temperature, FNormal operating pressure, range, psig Normal operating temperature range, FMaterial o construction 1Horizontal 350 25 60267 0.5-2.0 50-200 Austenitic SS Reactor Coolant Drain Tan Pums

Number per unitTypeDesign low rate, gpm Pump A Pump BDesign head, t Design pressure, psig

Design temperature, FReuired NPSH at design low, t Pump A Pump BMaterial, wetted suraces 2open ace horizontal, centriugal 50150 175 150300 6 6 Austenitic SS Chemical Drain Tan

Number (shared)Type Volume, gal Design pressure

Design temperature, FNormal operating pressure

Normal operating temperature, FMaterial o construction 1Vertical600 Atmospheric 180 Atmospheric 50-140 Austenitic SS

• For design codes and sa ety classes see Section 3.2 LIQUID WASTE SYSTEMS 11.2-27WATTS BARChemical Drain Pum Number (shared)TypeDesign low rate, gpmDesign head, t Design pressure, psig Design temperature, FReuired NPSH at design low, t

Material 1Horizontal, centriugal, mechanical seal

20 100150180 5

Austenitic SS Tritiated Drain Collector Tan Number (shared)Type Volume, gal Design pressure, psig

Design temperature, FNormal operating pressure

Normal operating temperature, FMaterial o construction 1Horizontal 24,700 Atmospheric 180 Atmospheric 50-140 Austenitic SS Tritiated Drain Collector Tan Pums Number (shared)Type 2Horizontal, centriugal, mechanical sealPum APum Design lowrate, gpmDesign head, t Design pressure, psig

Design temperature, FReuired NPSH at design low, t Material 100 100 150 180 20Austenitic SS 20 100 150 180 5Floor Drain Collector Tan Number (shared)Type Volume, galDesign pressure

Design temperature, FNormal operating pressure Normal operating temperature, FMaterial o construction 1Horizontal 23,000 Atmospheric 180 Atmospheric50-140Austenitic SS

• For design codes and saety classes see Section 3.2Table 11.2-2 Comonent Design Parameters*(Page 2 of )

11.2-28LIQUID WASTE SYSTEMS WATTS BARFloor Drain Collector Tan Pums Number (shared)Type 2Horizontal, centriugal, mechanical sealPum APum Design low rate, gpmDesign head, t Design pressure, psig

Design temperature, FReuired NPSH at design low, t

Material 100 110 150 180 15 Austenitic SS 20 100 150 180 5Waste Condensate Tans Number (shared)TypeVolume, each, galDesign pressure

Design temperature, FNormal operating pressure

Material 3Vertical 1500 Atmospheric 180 Atmospheric Austenitic SSWaste Condensate Pums

Number (shared)Type Design low rate, gpmDesign head, tDesign pressure, psig

Design temperature, FMaterial, wetted suraces 2Horizontal, centriugal

20 100 150 180 Austenitic SSLaundry and ot Shoer Tans Number (shared)Type Design temperature, FDesign pressureVolume, gal Material 2Vertical 180 Atmospheric600Stainless steel Laundry and ot Shoer Pum

Number (shared)

Design temperature, FDesign pressure, psig 1180150* For design codes and saety classes see Section 3.2Table 11.2-2 Comonent Design Parameters*(Page 3 of )

LIQUID WASTE SYSTEMS 11.2-29WATTS BARLaundry ot Shoer Pum (Contd)Design head, tDesign low, gpm Material contacting luid Type100 20 Stainless steel Horizontal, centri- ugal, mechanical sealonitor Tan (shared)

NumberCapacity, gal.

Design pressure Design Temperature, F

Material 120,462 Atmospheric 200 Austenitic stainless steelonitor Tan Pums (shared)

NumberDesign pressure, psig Design Temperature, F Design low, gpm Design head, t

Material 2150200150 200 Austenitic stainless steelCas Decontamination Collector Tan

Number (shared)Volume, gal Design pressure

Design temperature, F Material 115,000 Atmospheric 180 Carbon steel Cas Decontamination Collector Tan Pums

Number (shared)Flow rate, gpmDesign pressure, psig

Design temperature, F Material 2100150 180 Stainless steel Cas Decontamination Collector Tan Filters Number (shared)Flow rate, gpm Design pressure, psig

Design temperature, F Material 240 200 250 304 stainless steel

• For design codes and saety classes see Section 3.2Table 11.2-2 Comonent Design Parameters*(Page of )

11.2-30LIQUID WASTE SYSTEMS WATTS BARSent Resin Storage Tan Number (shared)Type Volume, each, t 3Design pressure, psig

Design temperature, FNormal operating pressure, psig Normal operating temperatureMaterial o construction 1Vertical 300 100 180 0.5 - 15 Ambient Austenitic SS TDCT and FDCT Discharge Filters, Waste Condensate Tan Filter, and Waste Condenser Filter**

Number (shared)TypeDesign pressure, psig 1Disposable synthetic cartridge 200 Design temperature, FFlow rate, gpm Pressure drop at 20 gpm, clean ilter, psiMaimum dierential pressure, 100 ouled, psiRetention or 25-micron particles, Materials Housing Filter element250 35 5 20 98 Stainless steel Nylon Laundry Tan aset Strainer

Number (shared)TypeDesign low rate, gpmDesign pressure, psig

Design temperature, FDiameter o peroration, in.

Pressure drop at design low when clean, psiRadiation leels outside Material, wetted suraces 1Perorated stainless steel sheet20 150 180 1/16 0.5 Negligible Austenitic SS

• For design codes and saety classes see Section 3.2**Other ilter media are allowed per endor technical manual i they are eual or iner.Table 11.2-2 Comonent Design Parameters*(Page 5 of )

LIQUID WASTE SYSTEMS 11.2-31WATTS BARFDCT Discharge Pums Strainer NumberDesign low rate, gpm Design pressure, psig

Design temperature, FDiameter o peroration, in.

Pressure drop at design low whenclean, psi Material 1100 150 180 3/16 2Stainless steeligh-Crud, Lo-Conductiity Tans Number (shared)Volume o each tan, gal.

Design pressure

Design temperature, F Material 219,000 Atmospheric 140 Rubber lined carbon

steeligh-Crud, Lo-Conductiity Pums Number (shared)Flow rate, gpmDesign pressure, psig

Design temperature, F Material Head, t. water 2150 150 140 Stainless steel 330 *For design codes and saety classes see Section 3.2 Table 11.2-2 Comonent Design Parameters*(Page of )

11.2-32LIQUID WASTE SYSTEMS WATTS BARigh-Crud Pre-Filters NumberType Design pressure, psig Design Temperature, FFlow rate, gpm

Material 3Bag Filter 220 140 150 304 Stainless steeligh-Crud, Lo-Conductiity Filter Number (shared)TypeDesign pressure, psig Design temperature, FFlow rate, gpm Maimum dierential pressure, 100 ouled, psi

Materials 1Etched Disc-type 375 140 100 (dirty)

75 Stainless steel eutraliation Tan Number (shared)Volume, gal Design pressure Design temperature, F Material Neutralization Pumps

Number (shared)

Flow rate, gpmDesign pressure, psig Design temperature, F Material Head, t. water 120,000 Atmospheric140Rubber lined carbon steel 2100 150 140 Stainless steel 135 on-Reclaimable Waste Tan Number (shared)Volume, gal

Design pressure

Design temperature, F Material 110,000 Atmospheric 140 Rubber lined carbon steel

• For design codes and saety classes see Section 3.2on-Reclaimable Waste Pums Number (shared)Flow rate, gpmDesign pressure, psig

Design temperature, F Material Head, t. water 2115 150 140 Nicel Alloy 300

• For design codes and saety classes see Section 3.2Table 11.2-2 Comonent Design Parameters*(Page of )

LIQUID WASTE SYSTEMS 11.2-33WATTS BARTable 11.2-3 Radioactie Liquid Releases From Westinghouse Designed PWR Plants istorical nformationPlantearCladdingAerage 2Fuel DefectsTotal ReleasedCuriesAg. Discharge Concentration Ci ml Fraction1 CFR 2ConcentrationYanee Rowe197019711972Stainless Steel Neg.0.001 0.036 0.0034 0.00131.5 10-101.25 10-124.7 10-121.5 10-31.25 10-54.71 10-5Connecticut1970Stainless Steel0.0129.54.02 10

-84.02 10-1Yanee19711972 0.035.85 12.267.75 10-91.61 10-87.75 10-21.61 10-1San Onore197019711972Stainless Steel 0.007 0.015 3.41 9.21 28.56.1 10-91.34 10-84.11 10-86.1 10-21.34 10-14.1 10-1R. E. Ginna197019711972 Zircaloy 0.4 0.26 9.35 0.96 0.381.43 10-81.45 10-95.69 10-101.43 10-11.45 10-25.7 10-3H. B. Robinson 219701971 1972 Zircaloy 0.0010.74 0.391.01 10-95.57 10-101.01 10-25.6 10-3Point Beach 19701971 1972 Zircaloy 0.010.14 1.532.48 10-102.68 10-92.48 10-32.7 10-2 11.2-34LIQUID WASTE SYSTEMS WATTS BAR* Per unit in accordance with 10CFR20, Appendi I. Table 11.2- Total Annual Discharge Liquid Waste Processing System* Prior to Treatment Combined Tans(Au. ldg)CCSLST(Ciyr)Con. Demin.T Br-84 I-131 I-132 I-133 I-134 I-135 Rb-88 Cs-134 Cs-136 Cs-137 Na-24 Cr-51 Mn-54 Fe-55 Fe-59 Co-58 Co-60Zn-65 Sr-89 Sr-90 Sr-91 Y-91mY-91 Y-93 Zr-95 Nb-95Mo-99 Tc-99m Ru-103 Ru-106 Te-129m Te-129 Te-131m Te-131 Te-132 Ba-140 La-140 Ce-141 Ce-143 Ce-144 Np-239 Total 0.09825 8.21 5.778 18.39 3.439 18.21 0.6522 1.325 0.1586 1.756 5.408 0.5775 0.301 0.2259 0.05624 0.8639 0.1001 0.09618 0.02619 0.00226 0.08633 0.05313 0.001647 0.3921 0.07314 0.05311 1.071 0.9414 1.403 16.97 0.03551 0.3423 0.2189 0.07575 0.2891 2.392 4.315 0.02804 0.417 0.7542 0.3604 95.94 1.84 153.7 108.2 344.4 64.41 340.9 12.22 24.8 2.969 32.87 101.2 10.81 5.634 4.229 1.053 16.17 1.873 1.8 0.4902 0.0423 1.616 0.9947 0.03083 7.341 1.369 0.9941 20.04 17.62 26.26 317.7 0.6646 6.411 4.098 1.418 5.412 44.78 80.78 0.5249 7.806 14.12 6.746

1796.34 0.0016 0.011 0.00037 0.016 0.0047 0.0038 0.0072 0.0022 0.0079 0.014 0.000088 0.000013 0.000084 0.0011 0.0019 0.00006 0.00029 0.0089 0.00091 0.00023 0.0039 0.0862.043E-044.449E-01 4.232E-023.352E-011.036E-02 1.650E-01 3.065E-046.586E-02 6.740E-03 8.647E-027.115E-023.626E-02 1.992E-02 1.513E-02 3.538E-03 5.616E-02 6.721E-03 6.193E-03 1.691E-03 1.516E-04 8.539E-04 5.010E-041.172E-043.913E-03 4.704E-033.509E-033.889E-023.534E-02 9.169E-021.108E+002.244E-032.288E-034.875E-03 9.200E-04 1.147E-02 1.359E-011.946E-011.768E-03 9.902E-03 4.925E-02 1.217E-023.093.028E-051.346E-02 5.213E-032.758E-02 1.535E-03 2.248E-02 1.305E-04 4.551E-03 5.382E-04 6.074E-031.117E-021.532E-03 7.746E-04 5.843E-04 1.421E-04 2.256E-03 2.624E-04 2.502E-04 6.753E-05 5.845E-06 1.652E-04 9.537E-05 3.705E-067.310E-041.898E-041.318E-042.664E-03 2.056E-03 3.666E-03 4.410E-02 9.210E-05 2.597E-04 5.036E-04 9.882E-05 7.144E-04 6.048E-03 1.031E-02 7.200E-05 9.526E-04 1.906E-03 8.781E-040.17 LIQUID WASTE SYSTEMS 11.2-35WATTS BARTable 11.2-5 Total Annual Discharge Liquid Waste Processing SystemAnnual Discharge (Ci) After ProcessingTotal Releases Per Unit (TPC Unit 1 Only)*** (Page 1 of 3)Column 1Column 2Column 3Column 4Column 5Column 6Column 7Column 8CD = Condensate Polishing Demineralizer, MD = Mobile DemineralizerOTHER OPERATIONAL MODESEXPECTED OPERATIONMD DFCVCS DFSGB processed by CDSGB processed by CD and MDLRWNo SGBSGB with no CD process Column 6 and Column 7Br-841000500.00036960.0001655341.65E-045.23E-046.88E-04I-1311000500.4712440.02678892.63E-021.14E+001.16E+00I-1321000500.0554750.013197321.32E-021.08E-011.21E-01I-1331000500.3880580.05319325.29E-028.57E-019.10E-01I-1341000500.01662220.006272566.26E-032.65E-023.28E-02I-1351000500.2125080.0476734.75E-024.22E-014.70E-01Rb-88100020.00719920.0068930076.89E-037.84E-047.68E-03Cs-134100020.0951360.029341862.93E-021.68E-011.98E-01Cs-136100020.00929130.002558042.55E-031.72E-021.98E-02Cs-137100020.1267350.040351474.03E-022.21E-012.61E-01Na-241000500.0897520.018673151.86E-020.00E+001.86E-02Cr-511000500.04328570.007061967.03E-039.27E-029.98E-02Mn-541000500.02490830.00500824.99E-035.10E-025.59E-02Fe-551000500.02322480.008109918.09E-030.00E+008.09E-03Fe-591000500.00595740.0024229382.42E-039.05E-031.15E-02Co-58100500.0781890.02259062.20E-021.44E-011.66E-01Co-601000500.0211210.0144066811.44E-021.72E-023.16E-02Zn-651000500.00657540.0003885733.82E-040.0E+003.82E-04 11.2-36LIQUID WASTE SYSTEMS WATTS BARSr-891000500.00188250.0001932151.92E-044.33E-034.52E-03Sr-901000500.00017362.21026E-052.20E-053.88E-044.10E-04Sr-911000500.00113780.0002847042.84E-042.18E-032.47E-03Y-91m1000500.00066940.0001688951.68E-040.00E+001.68E-04 Y-911000500.00020729.00858E-059.00E-053.00E-043.90E-04Y-931000500.00518290.0012738331.27E-030.00E+001.27E-03Zr-951000500.00609430.0013950241.39E-031.20E-021.34E-02Nb-951000500.00561380.0021083012.10E-038.98E-031.11E-02Mo-991000500.04308580.004234694.20E-039.95E-021.04E-01Tc-99m1000500.03868980.003385143.35E-030.00E+003.35E-03Ru-1031000500.09757420.005975895.88E-030.00E+005.88E-03Ru-1061000501.1843240.0774327.63E-020.00E+007.63E-02Te-129m1000500.00238490.0001431461.41E-040.00E+001.41E-04 Te-1291000500.00301820.0007325087.30E-040.00E+007.30E-04 Te-131m1000500.00567950.0008093358.05E-040.00E+008.05E-04 Te-1311000500.00112290.000203852.03E-040.00E+002.03E-04Te-1321000500.01258170.001123211.11E-032.93E-023.05E-02Ba-1401000500.14614560.01038151.02E-023.48E-013.58E-01Table 11.2-5 Total Annual Discharge Liquid Waste Processing SystemAnnual Discharge (Ci) After ProcessingTotal Releases Per Unit (TPC Unit 1 Only)*** (Page 2 of 3)Column 1Column 2Column 3Column 4Column 5Column 6Column 7Column 8CD = Condensate Polishing Demineralizer, MD = Mobile DemineralizerOTHER OPERATIONAL MODESEXPECTED OPERATIONMD DFCVCS DFSGB processed by CDSGB processed by CD and MDLRWNo SGBSGB with no CD process Column 6 and Column 7 LIQUID WASTE SYSTEMS 11.2-37WATTS BARLa-1401000500.21084060.01643521.62E-024.98E-015.14E-01Ce-1411000500.00210850.0003423063.41E-040.00E+003.41E-04 Ce-1431000500.01142770.001536221.53E-030.00E+001.53E-03 Ce-1441000500.05609260.006891856.84E-031.26E-011.33E-01Np-2391000500.01354340.001385591.37E-030.00E+001.37E-03 H-3 (TPC)111252.80 (3326.4)1252.80 (3326.4)1257.64 (3326.4)Unplanned0.160.160.160.16total (w/o H3) w/unplanned3.52523283.6850.4416449 0.6020.4380.5984.4024.84 5.000total (w/H3) w/unplanned1256.33 (3329.93)1256.49 (3330.09)1253.24 (3326.84)1253.40 (3327.00)1257.64 (3331.24)1257.80 (3331.40)Table 11.2-5 Total Annual Discharge Liquid Waste Processing SystemAnnual Discharge (Ci) After ProcessingTotal Releases Per Unit (TPC Unit 1 Only)*** (Page 3 of 3)Column 1Column 2Column 3Column 4Column 5Column 6Column 7Column 8CD = Condensate Polishing Demineralizer, MD = Mobile DemineralizerOTHER OPERATIONAL MODESEXPECTED OPERATIONMD DFCVCS DFSGB processed by CDSGB processed by CD and MDLRWNo SGBSGB with no CD process Column 6 and Column 7 11.2-38LIQUID WASTE SYSTEMS WATTS BAR Table 11.2-5 Total Annual Discharge Liquid Waste Processing System*Annual Discharge (Ci) After ProcessingTotal Releases Per Unit (TPC Unit 1 Only)***

Notes(TPC) The alues within the parentheses () represent the tritium alues due to the Trtium Production Core.***Total Release = Tan + CVCS /MD DF + LHST + TB + cond. demin/MD DF CVCS DFMD = Mobile Demineralizer (Processes Tans, CVCS)DF = Decontamination FactorCVCS DF = Decontamination Factor o CVCS prior to treatment with MD.Cond. demin. = condensate demineralizer regeneration waste0.16 Ci/yr is the unplanned release rom NUREG-0017Column 1Source term isotopesColumn 2Decontamination actors or the Mobile DemineralizerColumn 3CVCS Demineralizer decontamination actorsColumn 4((A+B/C)/D) + E + F/H + G Column 5((A+B/C)/D) + E + F/H/D + GColumn 6((A+B/C)/D) + E + F + GColumn 7 Column 8((A+B/C)/D) + E + G + (See below deinition or items A thru A (Ci/yr) =Reactor Coolant Drain Tan + Tritiated Drain Collector Tan + Floor Drain Collector TanB (Ci/yr) =Chemical Volume Control System (CVCS) Letdown C=CVCS Demineralizer decontamination actorD=Mobile Demineralizer decontamination actorE(Ci/yr) =Laundry and Hot Shower Drain Tan F (Ci/yr) =Condensate Demineralizer low = (Condensate low + Steam Generator Blow Down si day collection olume)G(Ci/yr) =Turbine Building drains H=CondensateDemineralizer decontamination actors (2 or Rb-88, Cs-134,-136,-137, 10 or all other isotopes-re. 1) (Ci/yr) =Steam Generator Blow down at ma allowable untreated concentration o 3.65E-5 uCi/cc. This calculated alue is based on an aerage o 365 days but does not represent a constraint on the plant since the actual alue or indiidual releases may be greater. Howeer, the total o all yearly releases must remain 5 Ci LIQUID WASTE SYSTEMS 11.2-39WATTS BAR Table 11.2-5a DS (FOR 1 FALD FUL) LUD RLASS COCTRATO(FFLUTCOCTRATOLT)ASL DATA WT O PROCSS (Sheet 1 of 1). Rel. Ciyr DesRatioDesign CiyrDesign uCicc1CFR2 CLCCLBr-843.696E-042.500E+009.241E-042.320E-114.000E-045.806E-08I-1314.712E-015.241E+012.470E+016.210E-071.000E-066.207E-01I-1325.548E-024.000E+002.219E-015.580E-091.000E-045.577E-05I-1333.881E-012.685E+011.042E+012.620E-077.000E-063.740E-02I-1341.662E-021.650E+002.740E-026.890E-104.000E-041.722E-06I-1352.125E-017.910E+001.682E+004.230E-083.000E-051.409E-03Rb-887.199E-031.814E+011.306E-013.280E-094.000E-048.204E-06Cs-1349.514E-024.060E+013.862E+009.710E-089.000E-071.079E-01Cs-1369.291E-031.652E+021.535E+003.860E-056.000E-066.429E-03Cs-1371.267E-011.532E+021.942E+014.880E-071.000E-064.880E-01Cr-514.329E-022.900E-011.261E-023.170E-105.000E-046.340E-07Mn-542.491E-024.700E-011.171E-022.940E-103.000E-059.813E-06Fe-595.957E-033.480E+002.074E-025.210E-101.000E-055.212E-05Co-587.819E-025.370E+004.200E-011.060E-082.000E-055.278E-04Co-602.112E-021.380E+002.915E-027.330E-103.000E-062.442E-04Sr-891.883E-032.245E+014.226E-021.060E-098.000E-061.328E-04Sr-901.736E-041.349E+012.342E-035.890E-115.000E-071.177E-04Sr-911.138E-031.860E+002.119E-035.330E-112.000E-052.663E-06Y-900.000E+001.567E+010.000E+000.000E+007.000E-060.000E+00Y-912.072E-041.115E+032.310E-015.810E-098.000E-067.258E-04Zr-956.094E-031.710E+001.040E-022.620E-102.000E-051.308E-05Nb-955.614E-032.340E+001.313E-023.300E-103.000E-051.100E-05Mo-994.309E-027.852E+023.383E+018.500E-072.000E-054.251E-02Te-1321.258E-021.453E+021.828E+004.590E-089.000E-065.103E-03Ba-1401.461E-013.100E-014.587E-021.150E-098.000E-061.441E-04La-1402.108E-016.000E-021.198E-023.010E-109.000E-063.345E-05Ce-1445.609E-028.000E-024.530E-031.140E-103.000E-063.795E-05Pr-1440.000E+008.000E-020.000E+000.000E+006.000E-040.000E+00H-31.253E+031.000E+001.253E+033.150E-051.000E-033.149E-02H-3 (TPC)3.326E+031.000E+003.326E+038.360E-051.000E-038.360E-02Total1.3430832Total (TPC)1.3957987Note The aboe numbers ar e based on one unit operation.This Table is based on column 4 o Table 11.2-5 ratioed up to 1 ailed uel.

11.2-40LIQUID WASTE SYSTEMS WATTS BAR Table 11.2-5b DS (FOR 1 FALD FUL) LUD RLASS COCTRATO(FFLUTCOCTRATOLT)WAST PROCSSD OL DRALRS (Sheet 1 of 1). Rel. Ciyr Des RatioDesign Ciyr DesignuCicc1CFR2 CLCCLBr-841.655E-042.500E+004.138E-041.040E-114.000E-042.600E-08I-1312.679E-025.241E+011.404E+003.530E-081.000E-063.529E-02I-1321.320E-024.000E+005.279E-021.330E-091.000E-041.327E-05I-1335.319E-022.685E+011.428E+003.590E-087.000E-065.127E-03I-1346.273E-031.650E+001.034E-022.600E-104.000E-046.496E-07I-1354.767E-027.910E+003.773E-019.480E-093.000E-053.161E-04Rb-886.893E-031.814E+011.250E-013.140E-094.000E-047.855E-06Cs-1342.934E-024.060E+011.191E+002.990E-089.000E-073.326E-02Cs-1362.558E-031.652E+024.226E-011.060E-086.000E-061.770E-03Cs-1374.035E-021.532E+026.183E+001.550E-071.000E-061.554E-01Cr-517.062E-032.900E-012.058E-035.170E-115.000E-041.034E-07Mn-545.008E-034.700E-012.355E-035.920E-113.000E-051.973E-06Fe-592.423E-033.480E+008.434E-032.120E-101.000E-052.120E-05Co-582.259E-025.370E+001.214E-013.050E-092.000E-051.525E-04Co-601.441E-021.380E+001.988E-025.000E-103.000E-061.665E-04Sr-891.932E-042.245E+014.337E-031.090E-108.000E-061.363E-05Sr-902.210E-051.349E+012.982E-047.490E-125.000E-071.499E-05Sr-912.847E-041.860E+005.303E-041.330E-112.000E-056.664E-07Y-900.000E+001.587E+010.000E+000.000E+007.000E-060.000E+00Y-919.009E-051.115E+031.005E-012.520E-098.000E-063.156E-04Zr-951.395E-031.710E+002.382E-035.990E-112.000E-052.993E-06Nb-952.108E-032.340E+004.931E-031.240E-103.000E-054.131E-06Mo-994.235E-037.852E+023.325E+008.360E-082.000E-054.178E-03Te-1321.123E-031.453E+021.631E-014.100E-099.000E-064.556E-04Ba-1401.038E-023.100E-013.258E-038.190E-118.000E-061.024E-05La-1401.644E-026.000E-029.338E-042.350E-119.000E-062.608E-06Ce-1446.892E-038.000E-025.566E-041.400E-113.000E-064.663E-06Pr-1440.000E+008.000E-020.000E+000.000E+006.000E-040.000E+00H-31.253E+031.000E+001.253E+033.150E-051.000E-033.149E-02H-3 (TPC)3.326E+031.000E+003.326E+038.360E-051.000E-038.360E-02Total2.680E-01Total (TPC)3.201E-01Note The aboe calculations are or 1 unit operation.This Table is based on column 5 o Table 11.2-5 ratioed up to 1 ailed uel.

LIQUID WASTE SYSTEMS 11.2-41WATTS BAR Table 11.2-5c Deleted by Amendment 11.2-42LIQUID WASTE SYSTEMS WATTS BARTable 11.2-5d no CD rocess SD at ma Alloable Concentration ith 2 gm dilution ASCiyrCiyr scaled to.2 Cidesansi desCiyrliquiddesuCicc liquid1CFR2CCLBr-840.000165330.0005225322.50 0.000935862.35E-11 4.0E-04 5.88E-08 I-1310.0263441.13790818852.41 2.518620986.33E-08 1.0E-06 0.0633001I-1320.013155 0.1082406714.00 0.160860674.04E-09 1.0E-04 4.043E-05I-1330.0528580.85733159126.85 2.27633835.72E-08 7.0E-06 0.008173I-1340.00626220.026497481.65 0.036819799.25E-10 4.0E-04 2.313E-06I-1350.0475080.4220158497.91 0.797978442.01E-08 3.0E-05 0.0006685Rb-880.00689270.00078392618.14 0.125798583.16E-09 4.0E-04 7.904E-06Cs-1340.0292760.16844826540.60 1.356919173.41E-08 9.0E-07 0.0378925 Cs-1360.00255130.017238708165.20 0.438708971.10E-08 6.0E-06 0.0018377Cs-1370.0402650.221161881153.22 6.39046731.61E-07 1.0E-06 0.1606107Cr-510.00702570.092741180.29 0.094788552.38E-09 5.0E-04 4.765E-06 Mn-540.004988280.0509488220.47 0.05329451.34E-09 3.0E-05 4.465E-05Fe-590.00241940.0090490433.48 0.0174714.39E-10 1.0E-05 4.391E-05Co-580.0220290.1436388495.37 0.261976456.58E-09 2.0E-05 0.0003292Co-600.014399960.0171901121.38 0.037061029.31E-10 3.0E-06 0.0003105Sr-890.0001915240.00432502322.45 0.008624542.17E-10 8.0E-06 2.709E-05Sr-900.0000219510.00038774313.49 0.000683911.72E-11 5.0E-07 3.438E-05Sr-910.000283850.0021839961.86 0.002712746.82E-11 2.0E-05 3.409E-06Y-900015.87 00.00E+00 7.0E-06 0Y-918.99686E-050.0002997591115.17 0.100630372.53E-09 8.0E-06 0.0003161Zr-950.001390320.0120312881.71 0.014405013.62E-10 2.0E-05 1.81E-05 Nb-950.0021047920.008974872.34 0.013897943.49E-10 3.0E-05 1.164E-05Mo-990.00419580.099467857785.19 3.393947868.53E-08 2.0E-05 0.004265Te-1320.001111740.029336496145.25 0.190818284.80E-09 9.0E-06 0.0005329Ba-1400.01024560.3475875990.31 0.350803378.82E-09 8.0E-06 0.0011021La-1400.01624060.4977229340.06 0.49864571.25E-08 9.0E-06 0.0013925 Ce-1440.00684260.1259653370.08 0.126517953.18E-09 3.0E-06 0.0010599Pr-144000.08 00.00E+00 6.0E-04 0H-31252.8011252.803.15E-05 1.0E-03 0.0314864 H-3 (TPC)3326.4013326.408.36E-051.0E-030.0836019Total0.3135157Total (TPC)0.3656312Note This Table is based on column 8 o Table 11.2-5, ratioed up to 1 ailed uel with SGBD at maimum allowable concentration o 3.65E-5 uCi/cc gross gamma) (TPC Unit 1 only).

LIQUID WASTE SYSTEMS 11.2-43WATTS BARTRM - Tennessee Rier Mile 1100 Miing PointTable 11.2- Tennessee Rier Reaches Within 5 ile Radius Donstream of W ameeginning TR nding TRSie(acres)Recreation isitsyChicamauga Lae below WBN528.0510.0 14799120,986Chicamauga Lae aboe Seuoyah Nuclear Plant510.0 1484.0221011,297,880Chicamauga Lae below Seuoyah Nuclear Plant484.0471.098897,421,905Nicaac Lae (Part 1)471.0460.01799284,000Public Water Sulies Within 5 ile Radius Donstream of WameTRstimated 2 PoulationDayton, TN50419,170East Side Utility, TN473.049,700 Chattanooga, TN465237,048 Soddy-Daisy/Falling Water Utility District, TN48711,452 11.2-44LIQUID WASTE SYSTEMS WATTS BARTable 11.2- Watts ar uclear PlantDoses From Liquid ffluents For ear 2ndiidual Dose (mrem)

AdultTotal Body0.72 Bone 0.56GI Tract 0.132Thyroid0.88Lier 0.96 idney 0.352Lung 0.136Sin 0.031TeenTotal Body0.44 Bone 0.60GI Tract0.104Thyroid0.80Lier 1.00 idney 0.356Lung 0.152Sin 0.031 ChildTotal Body0.188 Bone 0.76GI Tract 0.06Thyroid0.92Lier 0.88 idney 0.312Lung 0.128Sin 0.031nfantTotal Body0.032 Bone 0.036GI Tract0.033Thyroid 0.264Lier 0.036 idney 0.034Lung 0.032Sin 0.031Poulation Dose (Person-rem)Total ody1.619 Bone 1.761GI Tract1.420Thyroid15.336Lier 2.130 idney 1.392Lung 1.037Sin 0.315 ASEUS WASTE SYSTEMS 11.3-1WATTS BAR11.3 ASOUS WAST SSTS11.3.1 Design asesThe Gaseous Waste Processing System (GWPS) is designed to remoe ission product gases rom the Nuclear Steam Supply System and to permit operation with periodic discharges o small uantities o ission gases through the monitored plant ent. This is accomplished by internal recirculation o radioactie gases and holdup in the nine waste gas decay tans to reduce the concentration o radioisotopes in the released gases.The plant gaseous eluent releases during normal operation o the plant are limited at the site boundary not to eceed 10 CFR 50 Appendi I and 40 CFR 190 limits as speciied in the Osite Dose Calculation Manual (ODCM).Although plant operating procedures, euipment inspection, and preentie maintenance are perormed during plant operations to minimize euipment malunction, oerall radioactie release limits hae been established as a basis or controlling plant discharges durin g operation with the occurrence o a combination o euipment aults. A combination o euipment aults which include operation with uel deects and ailure o up to two TPBARs (Unit 1 only) in combination with such occurrences as (1)Steam generator tube leas.

(2)Leaage in Liuid Waste Processing System.

(3)Leaage o Gaseous Waste Processing System.

(4)Leaage in Reactor Coolant System euipment.

(5)Leaage in auiliary system euipment.The radioactie releases rom the plant resulting rom euipment aults o moderate reuency are within 10 CFR 50 Appendi I and 40 CFR 190 limits as speciied in the ODCM.11.3.2 SST DSCRPTOSThe GWPS consists o two waste gas compressor pacages, nine waste gas decay tans, auiliary serices, and the associated piping, ales and instrumentation. The euipment seres both units. The system is shown on the Process Flow and Electrical Control Diagrams, Figure 11.3-1 and Figure 11.3-2.Table 11.3-4 gies process parameters and system actiities or ey locations in the system.Table 11.3-5 gies the epected annual gaseous releases rom the GWPS.

11.3-2ASEUS WASTE SYSTEMS WATTS BARThe bases used or estimating the system actiities and gaseous releases are gien in Table 11.3-3.Gaseous wastes are receied rom the ollowing degassing o the reactor coolant and purging o the olume control tan prior to a cold shutdown, displacing o coer gases caused by liuid accumulation in the tans connected to the ent header, purging o some euipment, sampling and gas analyzer operation.Auiliary SericesThe auiliary serices portion o the GWPS consists o two automatic gas analyzers and its instrumentation, ales, and tubing, a nitrogen and a hydrogen supply maniold and the necessary instrumentation, ales, and piping.One automatic seuential gas analyzer determines the uantity o oygen in the gas space o the olume control tan, pressurizer relie tan, holdup tans, gas decay tans, reactor coolant drain tan, and spent resin storage tan and proides a local and main control room (MCR) alarm on 2 oygen concentration (hi-alarm), and 4 concentration (hi-hi alarm). Hydrogen (H

2) concentration may be monitored by the seuential analyzer. Howeer, the H 2 concentration is assumed to eceed the lower lammability limit. Thereore, operator action or the seuential analyzer is based primarily on the O 2 concentration. I the H 2 concentration is low (i.e, less than or eual to 4), this may be considered a mitigating actor when determining contingency actions or high or high-high O 2 concentration. A second oygen monitor is installed to continuously sample the discharge o the operating gas compressor. This monitor sounds an alarm at 2 oygen (hi-alarm) and 4 oygen (hi-hi alarm) in the MCR. Operator action is relied upon to preent the ormation o a combustible gas miture in the GWPS. This is accomplished by reducing oygen concentrations on a hi-alarm and suspending additions to the Waste Gas System and reducing oygen concentrations on a hi-hi alarm. For the seuential analyzer on a hi-alarm, the operator determines the source o the high oygen and reduces the oygen concentration. For a seuential analyzer hi-hi alarm, the operator minimizes an increase in ent header pressure, suspends additions to the waste gas system, and reduces oyge n concentration.As protection against an uncontrolled release o radioactie materials rom the GWPS, grab sampling and analysis are per ormed when either the waste disposal system waste gas seuential or continuous oygen analyzer is inoperable. Grab sampling and analysis are perormed or the continuous analyzer only during periods o compressor operation or batch transers.The nitrogen and hydrogen supply pacages are designed to proide a supply o gas to the Nuclear Steam Supply System. Two headers are proided or each pacage one or operation and one or bacup. The pressure regulator (nitrogen only) in the bacup header is set slightly lower than that in the operating header. When the operating header is ehausted, its discharge pressure alls below the set pressure o the bacup header, which comes into serice automatically to ensure a continuous supply o nitrogen gas. An alarm alerts the operator that one header (nitrogen or hydrogen) is ehausted. A two header (low and high pressure) liuid nitrogen (N 2)supply is proided to supplement the N 2 pacage.

ASEUS WASTE SYSTEMS 11.3-3WATTS BARNitrogen is supplied or the ollowing spent resin storage tan, reactor coolant drain tan, pressurizer relie tan, olume control tan, waste gas decay tans, and Chemical and Volume System (CVCS) holdup tans. In addition, there is a truc ill connection in the nitrogen supply header or the direct illing o the saety inection system accumulators. Maeup nitrogen or the accumulators is supplied rom the pacage. Hydrogen is supplied or the olume control tan.The design and material o ales and maniolds are the same as or the main GWPS.11.3.3 SST DS11.3.3.1 Comonent DesignThe GWPS euipment parameters are gien in Table 11.3-1. For urther inormation on design codes and saety classes see Section 3.2.Waste as ComressorsThe two waste gas compressors are proided or remoal o gases discharging to the ent header. One unit is supplied or normal operation and is capable o handling the gas rom a holdup tan which is receiing letdown low at the maimum rate. The second unit is proided or bacup during pea load conditions, such as when degassing the reactor coolant or or serice when the irst unit is down or maintenance. Operation o the bacup unit can be controlled manually or automatically by ent header pressure. The compressors are o the water sealed centriugal type and are proided with mechanical seals to minimize leaage.

Construction is o cast iron eternal and bronze internals with a stainless steel shat.as Decay TansNine tans are proided to hold radioactie waste gases or decay or contain nitrogen gas as and inert. This arrangement is adeuate or a plant operating with one percent uel deects. Nine tans are proided so that during normal operation, a minimum o 60 days are aailable or decay. The 60 days deine the design characteristics, not an operational parameter.alesThe ales handling gases are selected to minimize leaage.PiingThe piping or gaseous waste is typically carbon steel. All piping oints are welded ecept where langed connections are necessary or maintenance.11.3.3.2 nstrumentation DesignThe system instrumentation is shown on Flow Diagrams and Electrical Control Diagrams, Figures 11.3-1 and 11.3-2. Adeuate instrumentation is proided to monitor appropriate system parameters.

11.3-4ASEUS WASTE SYSTEMS WATTS BARThe instrumentation re adout is located mainly on the Waste Processing System panel in the Auiliary Building. Some instruments hae local readout at the euipment location.Most alarms are shown separately on the WPS panel and urther relayed to one common WPS annunciator on the waste disposal panel (0-L-2). An oygen analyzer alarm on the waste gas compressor discharge is in the main control room. The continuous oygen analyzer on the waste gas compressor is proided to alert the operator that oygen is prese nt, and to stop processing and manually switch to the standby gas decay tan. An automatic seuential gas analyzer is proided to monitor oygen concentrations. The analyzer records the oygen concentrations and alarms at high oygen leel. The instrumentation diagram and sample collection points are shown in Figure 11.3-2.

Hydrogen (H

2) concentration may be monitored by the seuential analyzer. Howeer, the H 2 concentration is assumed to eceed the lower lammability limit so that only O 2concentration is used to determine the need or operation action.11.3. Oerating ProcedureEuipment installed to reduce radioactie eluents to the minimum practicable leel will be maintained in good operating order and will be operated to the maimum etent practicable. In order to assure that these conditions are met, administratie controls are eercised on oerall operation o the system preentie maintenance is utilized to maintain euipment in optimum condition and eperience aailable rom similar plants is used in planning or operatio n at Watts Bar Nuclear Plant.Administratie controls are eercised through the use o instructions coering such areas as ale alignment or arious operations, euipment operating instructions, and other instructions pertinent to the proper operation o the processing euipment. Discharge permit orms are utilized to assure proper procedures are ollowed and in assuring proper ale alignments and other operating conditions beore a release.

These orms are signed and eriied by those personnel perorming the analysis and approing the release.Preentie maintenance is carried out on all euipment as described in the plants maintenance program.Gaseous wastes are receied rom degassing o the reactor coolant, purging o VCT, and nitrogen rom the closed coer gas system. The components connected to the ent header are limited to those which normally contain no air or aerated liuids to preent ormation o a combustible miture o hydrogen and oygen.Waste gases discharged to the ent header are pumped to a waste gas decay tan by one o the two waste gas compressors.The standby compressor is started automatically when high pressure occurs in the ent header. The standby compressor can be started manually. The compressors may also be used to transer gas between gas decay tans.

ASEUS WASTE SYSTEMS 11.3-5WATTS BARTo compress gas into the gas decay tans, the operator selects two tans at the auiliary control panel, one to receie gas, and one or standby. When the tan in serice is pressurized to 100 psig, low is automatically switched to the standby tan and an alarm alerts the operator to select a new standby tan.The discharge o the running waste ga s compressor is sampled automatically by the continuous gas analyzer as it is being transerred to the tan being illed and an alarm alerts the operator to a high oygen content. On high oygen signal, the tan must be isolated and operator action is reuired to direct low to the standby tan and to select a new standby tan. I it should become necessary to transer gas rom one decay tan to another, the tan to be emptied is discharged to the holdup tan return line. The tan to receie gas is opened to the inlet header and the return line pressure regulator setpoint is increased aboe setpoint. The return line isolation ale is closed and the crossoer between the return line and the compressor suction is opened. With this arrangement, gas is transerred by the compressor which is in serice.As the Chemical and Volume Control System holdup tans liuid is withdrawn, gas rom the gas decay tans is returned to the holdup tans. The gas decay tan selected to supply the returning coer gas is attached to the return header rom the auiliary control board by manually opening the appropriate ale.To maimize residence time or decay in the decay tans, the last tan illed should be the irst tan attached to the header. A bacup supply o gas or the holdup tans is proided by the nitrogen header.Beore a gas decay tan is discharged to the atmosphere ia the plant ent, a gas sample is taen to determine actiity concentration o the gas and total actiity inentory in the tan. Total tan actiity inentory is determined rom the actiity concentration and pressure in the tan.To release the gas, the appropriate local manual stop ale is opened to the plant ent and the gas discharge modulating ale is opened at the auiliary control panel. The plant ent actiity leel is also indicated on the panel to aid in setting the ale properly. I there should be a high actiity leel in the ent during release, the modulating ale closes.RefuelingWhen preparing the plant or a cold shutdown prior to re-ueling, it is necessary to degas the reactor coolant to reduce the hydrogen concentration to a desired leel o 5cc/g and a desired actiity concentration o Xe-133 to 1 Ci/cc. At the start o the de-gassing operation, the olume control tan gas space contains H 2 and traces o ission gases. This atmosphere is replaced with nitrogen by raising and lowering the tan liuid leel while enting and introducing nitrogen, until the aboe hydrogen and Xe-133 desired limits aboe are met.

11.3-6ASEUS WASTE SYSTEMS WATTS BARGas eoled rom the olume control tan during this operation is pumped by the waste-gas compressors to the gas-decay tans.Operation o the gaseous side o the GWPS is the same during the actual reueling operation as during normal operation.Auiliary Serices During normal operation the GWPS supplies nitrogen and hydrogen rom standard cylinders to primary plant components. Two headers are proided, one or operation and one or bacup. The pressure regulato r in the nitrogen operating header is set aboe the bacup header pressure and an alarm alerts the operator when this pressure alls below setpoint. The standby header or nitrogen comes into serice automatically to ensure a continuous supply o gas. Ater the ehausted header has been replaced, the operator manually sets the operating pressure and the bacup pressure to their respectie set points. When the supply header pressure or the hydrogen alls below the setpoint, an alarm alerts the operator to manually select the bacup. A two header (low and high) liuid nitrogen (N

2) supply is proided to supplement the N 2 cylinders and headers. This liuid N 2 supply is normally used to maintain a charge on both the cylinders and headers. I the liuid supply is depleted, then the cylinders supply the N 2 or the headers.11.3.5 Performance TestsInitial perormance tests are perormed to eriy the operability o the components, instrumentation and control euipment.During reactor operation the system is used at all times and hence is monitored.11.3. Deleted by Amendment 11.3. Radioactie Releases 11.3..1 RC RequirementsThe ollowing documents hae been issued by the NRC to proide regulations and guidelines or radioactie releases (1)10 CFR 20, Standards or Protection Against Radiation (2)10 CFR 50, Licensing o Production and Utilization Facilities The total plant gaseous releases meet these regulations by proiding assurance that the eposures to indiiduals in unrestricted areas are as low as reasonably achieable during normal plant operation and during anticipated operational occurrences. 11.3..2 Westinghouse PWR erience ReleasesA surey has been perormed o gaseous discharges rom dierent Westinghouse PWR plants or one calendar year. The results are presented in Table 11.3-2.

ASEUS WASTE SYSTEMS 11.3-7WATTS BAR11.3..3 ected aseous Waste Processing System ReleasesGaseous wastes consist o nitrogen and hydrogen gases purged rom the Chemical Volume and Control System olume control tan when degassing the reactor coolant, and rom the closed gas blaneting system. The gas decay tan capacity permits at least 60 days decay or waste gases beore discharge during normal operation.The uantities and isotopic concentration o gases discharged rom the GWPS hae been estimated. The analysis is based on input sources to the GWPS per NUREG0017, modiied to relect WBN plant-speciic parameters.The epected gaseous releases in curies per year per reactor unit are gien in Table 11.3-5. 11.3.. Releases from entilation SystemsA detailed reiew o the entire plant has been made to ascertain those items that could possibly contribute to airborne radioactie releases.During normal plant operations, airborne noble gases and/or iodines can originate rom reactor coolant leaage, euipment drains, enting and sampling, secondary side leaage, condenser air eector and gland seal condenser ehausts, and GWPS leaage.The assumptions used to estimate the annual uantity o radioactie gaseous eluents are gien in Table 11.3-6. These assumptions are in accordance with NUREG-0017. The noble gases and iodines discharged rom the arious sources are entered in Table 11.3-7.11.3..5 stimated Total ReleasesThe estimated releases listed in Table 11.3-7c hae been used in calculating the site boundary doses as shown in Table 11.3-10. Table 11.3-7a is the epected gases released or 1 ailed uel with containment purge. Table 11.3-7 is the annual releases with purge air ilters. Table 11.3-7b is the epected gases released or 1 ailed uel with continuous iltered containment ent, and Table 11.3-7c based on ANSI 18.1-1984 with continuous iltered containment ent.

The dose calculations, based on the estimated total plant releases, show that the releases are in accordance with the design obecties in Section 11.3.1 and meet the regulations as outlined in Section 11.3.7.1. Further, the total plant releases are within the ODCM limits.11.3. Release Points Gaseous radioactie wastes are released to the atmosphere through ents located on the Shield Building, Auiliary Building, Turbine Building, and Serice Building. A brie description, including unction and location o each type ent, is presented below.

11.3-8ASEUS WASTE SYSTEMS WATTS BARShield uilding entWaste gases rom containment purge and the waste gas decay tans are discharged to the enironment through a Shield Building ent. Each Shield Building has one ent. The ent is o rectangular cross section (dimension - 2 eet by 7 eet 6 inches) and discharges approimately 130 eet aboe ground leel. The location o the Reactor Building ents is shown in the euipment layout drawings, Figure 1.2-1. The location o the Shield Building in relation to the site is shown on the main plant general plan, Figure 2.1-5. All releases rom the Shield Building ent ecept containment purge air ehaust monitor discharges are passed through HEPA ilters and charcoal adsorbers prior to release. The eluent discharge rate through the ent is ariable occasionally, during containment purge, the rate may approach the alue which is listed in Figure 9.4-28. The low path or waste gases ehausted through the ent rom the waste gas decay tans is shown in Figure 11.3-1.Auiliary uilding entWaste gases in the Auiliary Building are discharged through the Auiliary Building ehaust ent. In addition, containment atmosphere is continuously ented, during normal operation or pressure control, into the annulus ater it is iltered through HEPA and charcoal ilters, and subseuently, discharged into the Auiliary Building ehaust ent. The ent is o the chimney type haing a rectangular cross section o 10 by 30 eet. The top o the ent is located atop the Auiliary Building and discharges approimately 106 eet aboe grade. Under normal operating conditions, gases are continuously discharged through the ent. Eluent low rates can be near 224,000 cm when two Auiliary Building general ehaust ans and one uel-handling area ehaust an are operating at ull capacity. Under accident conditions, the Auiliary Building is isolated, and the Auiliary Building gas treatment system (ABGTS) is used to treat gaseous eluents. When in serice, the ABGTS discharges to the Shield Building ehaust ent. The location o the Auiliary Building ehaust ent is shown in the euipment layout diagram, Figure 1.2-1. The Auiliary Building is shown on the main plant general plan, Figure 2.1-5.Turbine uilding entsGaseous wastes rom the condenser are discharged through the condenser acuum ehaust ent. The ent, which is a 12-inch diameter pipe, discharges at approimately the 760-oot leel. Under normal operating conditions the discharge low rate will typically be less than 45 cm.Non-radioactie entilation air is ehausted rom the Turbine Building through the Turbine Building ents. There are eighteen ents at the 755-oot leel and twenty ents at the 824-oot leel (roo leel). The eluent low rates ary or each type o ent. Generally, the normal low rates through a typical ent at the 755-oot leel is 22,888 cm and the low rates through typical ent at the 824-oot leel is 28,500 cm. The general arrangement o ents on the Turbine Building is shown on Figure 1.2-1. The turbine building is shown on the main plant general plan, Figure 2.1-5.

ASEUS WASTE SYSTEMS 11.3-9WATTS BARCondenser acuum haust entGaseous wastes rom the condenser are discharged through the condenser acuum ehaust ent. The ent, which is a 12-inch diameter pipe, discharges at approimately the 760-oot leel. Under normal operating conditions the discharge low rate will typically be less than 45 cm. Serice uilding ent Radiologically monitored potentially radioactie waste gases rom the radiochemical laboratory and the titration room are ehausted through HEPA ilters ia a common duct which discharges to the common Serice Building roo ehaust plenum. Ehaust air rom the general area discharges to the common Serice Building roo ehaust plenum. Separate ents rom the common roo ehaust plenum discharge to atmosphere approimately 24 eet aboe grade. The Serice Building is shown on the site plot plan, Figure 2.1-5.11.3. Atmosheric DilutionCalculations o atmospheric transpo rt, dispersion, and ground deposition are based on the straight-line airlow model discussed in NRC Regulatory Guide 1.111 (Reision 1, uly 1977). Releases are assumed to be continuous. Releases nown to be periodic, e.g., those during containment purging and waste gas decay tan enting, are treated as batch releases.Releases rom the Shield Building, Turbine Building (TB), and Auiliary Building (AB) ents are treated as ground leel. The computer code titled Gaseous Eluent Licensing Code (GELC) was used to perorm routine dose assessments or WBN.

During Unit 1 licensing, terrain adustment actors (TAF) were deeloped to account or recirculation eects due to the rier alley location o the plant. The ground leel oint reuency distribution (FD) is gien in Section 2.3. Air concentrations and deposition rates were calculated considering radioactie deca y and buildup during transit. Plume depletion was calculated using the igures proided in Regulat ory Guide 1.111.Table 11.3-8 proides the receptor locations or perorming the dose assessments in this chapter. The data was based on the 2007 land use surey. The TAF, X/, and D/ or each receptor were calculated or the locations based on this surey. The TAF alues presented in Table 11.3-8 were deeloped on the same basis that was used or the Unit 1 licensing. Meteorology data rom the 1986 to 2005 time period was used in the deelopment o the X/s and D/s. Estimates o normalized concentrations (X/) and normalized deposition rates (D/) or gaseous releases at points where potential dose pathways eist are listed in Table11.3-8.11.3.1 stimated Doses from Radionuclides in aseous ffluentsIndiiduals are eposed to gaseous eluents ia the ollowing pathways (1) eternal radiation rom radioactiity in the air and on the ground (2) inhalation and (3) ingestion o bee, egetables, and mil. No other additional eposure pathway has been identiied which would contribute 10 or more to either indiidual or population doses.

11.3-10ASEUS WASTE SYSTEMS WATTS BAR11.3.1.1 Assumtions and Calculational ethodsEternal air eposures are ealuated at points o potential maimum eposure (i.e., points at the unrestricted area boundary). Eternal sin and total body eposures are ealuated at nearby residences. The dose to the critical organ rom radioiodines, tritium and particulates is calculated or real pathways eisting at the site during a land use surey conducted in 2007.To ealuate the potential critical organ dose, mil animals and nearest gardens were identiied by a detailed surey within ie miles o the plant (Table 11.3-8). Inormation on grazing seasons and eeding regimes are relected in the eeding actor. The eeding actor is the raction o the year an animal grazes on pasture. The calculation assumes eeding actor o 0.65 or all cow receptors in the 2007 LUS. The alue is taen rom Figure 2.2 in NUREG/CR-4653 GASPAR II - Technical Reerence and User Guide, 1987 that proides the growing season across the US. The alue chosen is on the high end or the middle Tennessee Valley. The LUS and publicly aailable inormation support that this is a conseratie eeding actor. Supplemental eed is assumed to be grown in the icinity o Watts Bar and hae the same nuclide source as

the pasture. Doses are calculated using the dose actors and methodology contained in NRC Regulatory Guide 1.109 with certain eceptions as ollows (1)Inhalation doses are based on the aerage indiiduals inhalation rates ound in ICRP Publication 23 o 1,400 5,500 8,000 and 8,100 m 3/year or inant, child, teen, and adult, respectiely.

(2)The mil ingestion pathway has been modeled to include speciic inormation on grazing periods or mil animals obtained rom a detailed arm surey. A eeding actor (FF) has been deined as that raction o total eed intae a dairy animal consumes that is rom resh orage. The remaining portion o eed (1-FF) is assumed to be rom stored eed. Doses calculated rom mil produced by animals consuming resh orage are multiplied by these actors. Concentrations o radioactiity in stored eed are adusted to relect radioactie decay during the maimum assumed storage period o 180 days by the actor 1 180---------expi t-t d 0 1801i 180-ep-180i--------------

---

=

ASEUS WASTE SYSTEMS 11.3-11WATTS BARThis actor replaces the actor ep (-i t h) in euation C-10 o Regulatory Guide 1.109.

(3)The stored egetable and bee ingestion pathways hae been modeled to relect more accurately the actual dietary characteristics o indiiduals. For stored egetables the assumption is made that home grown stored egetables are consumed when resh egetables are not aailable, i.e., during the 9 months o all, winter, and spring. Rather than use a constant storage period o 60 days, radioactie decay is accounted or eplicitly during the 275-day consumption period. The radioactie decay correction is calculated byThis replaces the term ep (-i t h) in Euation C-5 o Regulatory Guide 1.109.

(4)The bee consumption pathways can be diided into either commercial sales or home use pathways. Dose calculations are made or indiiduals consuming meat produced or home use. The normal processing route is or an indiidual to slaughter the bee animal, pacage and reeze the meat, and then consume the meat during the net 3-month period. Radioactie decay is calculated during the 3-month period byThe term is multiplied into Euation C-12 in Regulatory Guide 1.109. I the bee animals are sold commercially, then indiiduals would not be eposed 1 275----------i t-ept d 0 2751i 275-ep-275i------------------------------------------

-=1 90------i t-ept 1i 90-ep-90i---------------------------------------

=d 0 90 11.3-12ASEUS WASTE SYSTEMS WATTS BARcontinuously to meat containing radioactiity rom the same arm. It is epected that this pathway will not cause signiicant indiidual eposures.Population doses were based on U.S. Population distribution o* e.g., someone who is 1 year, 11 months is an inant, while someone who is eactly two years old is a child.Tables 11.3-11 and 11.3-12 proide the doses estimated or indiiduals and the population within 50 miles o the plant site.TVA assumes that enough resh egetables are produced at each residence to supply annual consumption by all memebers o that household. TVA assumes that enough meat is produced in each sector annulus to supply the needs o that region. The Watts Bar proected poplulation distribution or the year 2040 is gien in Table 11.3-9. Vegetable inestion is the critical pathway.11.3.1.2 Summary of Annual Poulation DosesTVA has estimated the radiological impact to regi onal population groups in the year 2040 rom the normal operation o the Watts Bar Nuclear Plant. Table 11.3-11 summarizes these population doses. The total body dose rom bacground to indiiduals within the United States ranges rom approimately 100 mrem to 250 mrem per year. The annual total body dose due to bacground or a population o about 1,500,000 persons epected to lie within a 50 mile radius o the Watts Bar Nuclear Plant in the year 2040 is calculated to be approimately 210,000 man-rem assuming 140 mrem/year/indiidual. By comparison, th e same population (ecluding onsite radiation worers) will receie a total body dose o approimately 6.66 man-rem rom eluents. Based on these results, TVA concludes that the normal operation o the Watts Bar Nuclear Plant will present minimal ris to the health and saety o the public.RFRCS NoneCategory Ages (A)* FractionInant A2 0.015Child 2 A13 0.167Teen 13A19 0.153Adult 19A 0.665 ASEUS WASTE SYSTEMS 11.3-13WATTS BAR1.For design codes and saety classes, see Section 3.2. 2.Hydrogen is uantiied to determine i it eceeds lower lammability limit.Table 11.3-1 aseous Waste Processing System Comonent Data 1Waste as Comressors NumberType Design low rate, N2

(at 140F, 2 psig) cmDesign pressure, psig

Design temperature, FNormal operating pressure, psig

Suction Discharge Normal operating temperature, F 2Water Sealed Centriugal 401501802.0 - 3.50 - 10070 - 130as Decay Tans NumberVolume, each, t 3Design pressure, psig Design temperature, FNormal operating pressure, psig

Normal operating temperatures, FMaterial o construction Type 9600 150 1800 - 11050 - 140 Carbon steelVertical CylindricalSequential Automatic as AnalyerOygen Hydrogen 2 Automatic stepping switch Recorded ReadoutTemperature, F Number (Shared)

Electrochemical Sensor o the Polargraphic Type, 0 - 20 O 2By Thermal Conductiity,0 - 100 H28 steps8 points120 1 11.3-14ASEUS WASTE SYSTEMS WATTS BARTable 11.3-2 D Airborne Radioactie oble as Releases For 13 From Westinghouse Designed Oerating ReactorsPlantTotal Released Curies1.Yanee Rowe3.5 10 12.Connecticut Yanee (Haddam Nec)3.2 10 13.San Onore1.1 10 44.R. E. Ginna5.76 10 25.H. B. Robinson3.1 10 36.Point Beach Units 1 and 25.75 10 3

ASEUS WASTE SYSTEMS 11.3-15WATTS BARTable 11.3-3 ases Used n Calculating ected System Actiities and Releases From The WPSA.PCTD SST ACTT1.The maor inputs to the gas system during normal operation are ents on the CVCS Holdup Tans (HUT) and Reactor Coolant Drain Tans (RCDT). Inputs rom the gas analyzer sampling system and CVCS olume control tan are assumed to be negligible.2.Reactor coolant gaseous actiities are based on NUREG-0017 as modiied to relect Watts Bar plant parameters.3.Twenty-ie percent o dissoled radiogases in the reactor coolant entering the RCDTs and HUTs leae solution and enter the apor space.4.Radioactie decay was assumed while the CVCS HUT, RCDTs and gas decay tans were illing. No additional decay was assumed in the eaporator.5.The CVCS HUT is assumed to be illed to 80 capacity beore processing by the waste disposal system. The RCDTs are assumed to be illed to 300 gallons beore draining.6.Values or liuid low rates to the tans were based on estimates o annual aerage lows.CVCS HUT low 4 gpm(2 gpm per unit)

RCDT low 300 gpd(per each unit)7.Plant capacity actor 0.88.Iodine partition coeicient in the RCDTs and CVCS HUT was 7.5 10-3Ci/cc in apor (Based on NUREG-0017) Ci/cc in liuid 9.Hydrogen conce ntration in the primary coolant was assumed 35 cc/g..AUAL RLASSPer NUREG-0017, the ollowing assumptions were used in calculating epected annual releases1.173 t 3/day (at STP) o reactor coolant ogas is input into the waste gas disposal system.2.WGDT inentory is assumed to be at RCS coolant concentrations, ater correcting or standard temperature and pressure (273.2 and 14.7 psia)3.RCS coolant is at 588.2F and 2250 psia.4.GWPS releases are based on a 60 day hold-up time.5.Particulate releases are taen rom Table 2-17 o NUREG-0017.

11.3-16ASEUS WASTE SYSTEMS WATTS BAR.Table 11.3- Process Parameters And ected Actiities n aseous Waste System (Concentrations n Cim) (Sheet 1 of 2)

Pressu re(PS)FloTem. (F)Rate(ccday) R3 R5 R5 R R R131133 133135 1. Unit 1 RCDT Vent1.5170 ma.1.14(+6)0.0E+061.5E-033.2E-021.4E-021.3E-020.0E+007.3E-023.9E-042.9E-017.5E-04 2. Unit 2 RCDT Vent1.5170 ma.1.14(+6)0.0E+061.5E-033.2E-021.4E-021.3E-020.0E+007.3E-023.9E-042.9E-017.5E-04 3. Sampling System VCT Vent Unit 11.5115 00.0E+000.0E+000.0E+000.0E+000.0E+000.0E+000.0E+000.0E+000.0E+000.0E+00 4. Sampling System VCT Vent Unit 21.5115 00.0E+000.0E+000.0E+000.0E+000.0E+000.0E+000.0E+000.0E+000.0E+000.0E+00 5. CVCS HUT Vent - -2.18(+7)0.0E+009.0E-052.9E-022.3E-031.0E-030.0E+005.6E-022.4E-051.7E-014.6E-05 6. Gas Analyzer - - 00.0E+000.0E+000.0E+000.0E+000.0E+000.0E+000.0E+000.0E+000.0E+000.0E+00

7. Waste Disposal System SRST Vent - - 00.0E+000.0E+000.0E+000.0E+000.0E+000.0E+000.0E+000.0E+000.0E+000.0E+00

8. CVCS VCT Vent Unit 11.5115 00.0E+004.1E-013.5E+001.4E-015.3E-010.0E+005.3E-004.8E-012.0E+012.5E-029. CVCS VCT Vent Unit 21.5115 00.0E+004.1E-013.5E+001.4E-015.3E-010.0E+005.3E-004.8E-012.0E+012.5E-0210. Combination o Normal 1/p to WPS(G)1.5VAR2.48(+7)0.0E+003.9E-042.0E-018.5E-034.2E-030.0E+003.3E-011.0E-048.8E-012.0E-0411. Compressor Recirculation Line1.5140 00.0E+003.9E-042.0E-018.5E-034.2E-030.0E+003.3E-011.0E-048.8E-012.0E-0412. Compressor Inlet3.5VAR2.48(+7)0.0E+003.9E-042.0E-018.5E-034.2E-030.0E+003.3E-011.0E-048.8E-012.0E-0413. Compressor Inlet2.0VAR2.48(+7)0.0E+003.9E-042.0E-018.5E-034.2E-030.0E+003.3E-011.0E-048.8E-012.0E-0414. Downstream o Compressor1001402.48(+7)0.0E+001.8E-039.6E-014.0E-022.0E-020.0E+001.6E+004.8E-044.1E+001.0E-0315. Compressor Outlet to GDTs - - 00.0E+001.8E-039.6E-014.0E-022.0E-020.0E-021.6E+004.8E-044.1E+001.0E-0316. Inlets to Filling GDTs1001402.48(+7)0.0E+001.8E-039.6E-014.0E-022.0E-020.0E-021.6E+004.8E-044.1E+001.0E-0317. Line to GDT Header100AMB VAR0.0E+001.0E-059.6E-016.0E-06.5E-040.0E+001.4E+001.5E-063.1E+003.0E-0618. Discharge Line 20AMB VAR0.0E+000.0E+004.6E-010.0E+000.0E+000.0E+002.1E-020.0E+005.6E-040.0E+0019. Discharge Line 1AMB VAR0.0E+000.0E+004.6E-010.0E+000.0E+000.0E+002.1E-020.0E+005.6E-040.0E+00

20. Gas Analyzer 2AMB 00.0E+000.0E+000.0E+000.0E+000.0E+000.0E+000.0E+000.0E+000.0E+000.0E+0021. From GDTs to Compressor Inlet100AMB2.48(+7)0.0E+001.0E-059.6E-016.0E-036.5E-040.0E+001.4E+001.5E-063.1E+003.0E-0622. From GDTs to BRS HTs 3AMB2.48(+7)0.0E+001.0E-059.6E-016.0E-036.5E-040.0E+001.4E+001.5E-063.1E+003.0E-06 ASEUS WASTE SYSTEMS 11.3-17WATTS BARTable 11.3- PROCSS PARATRS AD PCTD ACTTS ASOUS WAST SST (COCTRATOS Cigm) (Sheet 2 of 2)

Pressur e(PS)Tem.(F)Flo Rate(ccday) 135 13 13 13 131 132 133 13135 1. Unit 1 RCDT Vent1.5170 ma.1.14(+6)7.0E-025.0E-057.5E-040.0E+003.4E-043.8E-048.9E-042.7E-041.0E-03

2. Unit 2 RCDT Vent1.5170 ma.1.14(+6)7.0E-025.0E-057.5E-040.0E+003.4E-043.8E-048.9E-042.7E-041.0E-03 3. Sampling System VCT Vent Unit 11.5115 00.0E+000.0E+000.0E+000.0E+000.0E+000.0E+000.0E+000.0E+000.0E+00 4. Sampling System VCT Vent Unit 21.5115 00.0E+000.0E+000.0E+000.0E+000.0E+000.0E+000.0E+000.0E+000.0E+00 5. CVCS HUT Vent - -2.18(+7)9.7E-033.0E-064.7E-050.0E+002.4E-052.8E-061.7E-051.8E-061.0E-05 6. Gas Analyzer - - 00.0E+000.0E+000.0E+000.0E+000.0E+000.0E+000.0E+000.0E+000.0E+00 7. Waste Disposal System SRST Vent - - 00.0E+000.0E+000.0E+000.0E+000.0E+000.0E+000.0E+000.0E+000.0E+00

8. CVCS VCT Vent Unit 11.5115 03.2E+001.7E-032.5E-020.0E+000.0E+000.0E+000.0E+000.0E+000.0E+00

9. CVCS VCT Vent Unit 21.5115 03.2E+001.7E-032.5E-020.0E+000.0E+000.0E+00 0.0E+000.0E+000.0E+0010. Combination o Normal 1/p to WPS(G)1.5VAR2.48(+7)3.9E-021.3E-052.0E-040.0E+005.3E-053.8E-054.6E-052.5E-051.0E-0411. Compressor Recirculation Line1.5140 03.5E-021.3E-052.0E-040.0E+005.3E-053.8E-059.6E-052.5E-051.0E-0412. Compressor Inlet3.5VAR2.48(+7)3.5E-021.3E-052.0E-040.0E+005.3E-053.8E-059.6E-052.5E-051.0E-0413. Compressor Inlet2.0VAR2.48(+7)3.5E-021.3E-052.0E-040.0E+005.3E-053.8E-059.6E-052.5E-051.0E-0414. Downstream o Compressor1001402.48(+7)1.7E-016.1E-059.6E-040.0E+002.6E-041.8E-044.4E-041.2E-044.9E-04

15. Compressor Outlet to GDTs - - 01.7E-016.1E-059.6E-040.0E+002.6E-041.8E-044.4E-041.2E-044.9E-0416. Inlet to Filling GDTs1001402.48(+7)1.7E-016.1E-059.6E-040.0E+002.6E-041.8E-044.4E-041.2E-044.9E-0417. Line to GDT Header100AMBVAR1.8E-023.1E-083.1E-060.0E+002.0E-044.8E-061.1E-041.3E-063.9E-05

18. Discharge Line 20AMBVAR0.0E+000.0E+000.0E+000.0E+006.0E-070.0E+000.0E+000.0E+000.0E+0019. Discharge Line 1AMBVAR0.0E+000.0E+000.0E+000.0E+006.0E-070.0E+000.0E+000.0E+000.0E+0020. Gas Analyzer 2AMB 00.0E+000.0E+000.0E+000.0E+000.0E+000.0E+000.0E+000.0E+000.0E+0021. From GDTs to Compressor Inlet100AMB2.48(+7)1.8E-033.1E-083.1E-060.0E+002.0E-044.8E-061.1E-041.3E-063.9E-0522. From GDTs to BRS HTs 3AMB2.48(+7)1.8E-023.1E-083.1E-060.0E+062.0E-044.8E-061.1E-041.3E-063.9E-05 11.3-18ASEUS WASTE SYSTEMS WATTS BARTable 11.3-5 ected Annual aseous Releases From The WPS - Per Reactor Unit GWPS Gas release (Ci/Yr) r-85m r-85 r-87 r-88 Xe-131M Xe-133M Xe-133 Xe-135M Xe-135 Xe-137 Xe-138 Ar-41 Br-84 I-131 I-132 I-133 I-134 I-135 H-3 Cr-51 Mn-54 Co-57 Co-58 Co-60Fe-59 Sr-89 Sr-90 Zr-95 Nb-95 Ru-103 Ru-106 Sb-125 Cs-134 Cs-136 Cs-137 Ba-140 Ce-141 C-14 0.00E+00 4.63E+00 0.00E+00 0.00E+00 3.52E-01 1.14E-08 1.72E-02 0.00E+00 6.01E-47 0.00E+00 0.00E+00 0.00E+00 0.00E+00 1.44E-03 0.00E+00 1.16E-21 0.00E+00 4.08E-66 0.00E+00 1.40E-07 2.10E-08 0.00E+00 8.70E-08 1.40E-07 1.80E-08 4.40E-07 1.70E-07 4.80E-08 3.70E-08 3.20E-08 2.70E-08 0.00E+00 3.30E-07 5.30E-08 7.70E-07 2.30E-07 2.20E-08 1.20E+00 ASEUS WASTE SYSTEMS 11.3-19WATTS BARTable 11.3- Radioactie aseous ffluent Parameters (Page 1 of 2)1.Thermal Power Rating is 3582 MWt. (For Unit 1 only, Tritium releases based on 3425 MWt. Tritium isotope determination or the Non-Tritium Production Cor e based on 3480 MWt)2.Primary and secondary side coolant and steam actiities are based on ANSI N18.1 and hae been plant adusted or WBN speciic parameters.3.RCS water parametersVolume = 11,375 t 3Press. = 2250 psiaTemp. = 588.2 F Spec. Vol. = 0.02265 t 3/lb4.Containment releases are iltered through a HEPA and charcoal ilter with minimum iltration eiciencies o 99 and 70, respectiely.5.Containment gaseous source terms are based on a 3/day (noble gas) and 8.0E-4/day (iodines) release o RCS coolant into the containment air borne atmosphere.6.WGDT releases are based on a 173 t 3/day ( STP) input o RCS coolant ogas to the waste gas disposal system and a WGDT holdup time o 60 days.7.Auiliary Building (AB) entilation noble gas source terms are based on a 160 lb/day release o RCS coolant actiity into the AB atmosphere.8.AB entilation iodine releases are based on 1.85 Ci/yr per Ci/gm o RCS or 300 days and 6.8 Ci/yr per Ci/gm or 65 days.9.Reueling Area iodine releases are based on 0.16 Ci/yr per Ci/gm o RCS or 300 days and 0.3Ci/yr per Ci/gm or 65 days.10.Turbine Building (TB) entilation noble gas sour ce terms are based on a 1700 lb/hr release o secondary steam into the TB atmosphere.11.TB entilation iodine source terms are based on 8500 Ci/yr per Ci/gm o secondary steam or 300days and 1400 Ci/yr per Ci/gm or 65 days. 12.Condenser acuum ehaust noble gas source terms are based on a steam lowrate to the condenser o 8.5E6 lb/hr at secondary steam actiities.13.Condenser acuum ehaust iodine source terms are based on a 3500 Ci/yr per Ci/gm o secondary steam released to the condenser acuum ehaust.14.Steam generator blowdown lash tan source terms are based on a maimum steam generator blowdown low o 12.5 gpm/steam generator. Iodines are urther reduced in the ogases by applying a 0.05 partition actor. There are no noble gas releases rom this path as there are no noble gas source terms in th e secondary coolant. 15.Ar-41 releases are 34 Ci/yr.

16.Total tritium releases are based on 0.4 Ci/yr per MWt, with 10 o that aailable or release ia gaseous pathways.17.Total particulate releases are taen directly rom Table 2-17 o NUREG-0017. Since these alues are prior to treatment, the releases rom the Containm ent Building either through the purge air, or containment ent ilters, are reduced by applying a HEPA iltration actor o 0.01 (99 eiciency).

11.3-20ASEUS WASTE SYSTEMS WATTS BAR18.C-14 releases are 1.6 Ci/yr rom containment, 4.5 Ci/yr rom the AB, and 1.2 Ci/yr rom the GWPS or a total o 7.3 Ci/yr.19.The WGS discharge is iltered with a HEPA (eiciency o 99) and charcoal (eiciency 70) ilter prior to release.20.A continuous iltered containment ent o 100 cm is the epected normal release and is ealuated. A separate ealuation assuming one purge eery two wees will be perormed. NUREG-0017 suggests 22 containment purges a year during power operation, and 2 purges during reueling.Table 11.3- Radioactie aseous ffluent Parameters (Page 2 of 2)

ASEUS WASTE SYSTEMS 11.3-21WATTS BAR (1) Includes release rom GWPS (2) 4.28E+02 = 4.28 X 10 2 (3)Tritium alues or a Tritim Production CoreTable 11.3- Annual Radioactie Releases With Purge Air Filters (CuriesearReactor)Table based on operation o one unit.

NuclideContain.(1)BuildingAu.BuildingTurbine BuildingTotal r-85m r-85 r-87 r-88 Xe-131m Xe-133m Xe-133 Xe-135m Xe-135 Xe-137 Xe-138 Ar-41 Br-84 I-131 I-132 I-133 I-134 I-135 H-3 H-3 (TPC)(3)Unit 1 Only

Cr-51 Mn-54 Co-57 Co-58 Co-60 Fe-59 Sr-89 Sr-90Zr-95 Nb-95 Ru-103 Ru-106 Sb-125 Cs-134 Cs-136 Cs-137 Ba-140 Ce-141 C-142.00E+016.90E+02 1.09E+012.84E+01 1.17E+03 4.63E+013.12E+03 3.86E+001.55E+02 3.18E-01 3.33E+003.40E+01 6.00E-05 7.29E-03 1.61E-033.55E-031.66E-033.16E-03 1.39E+023.70E+029.21E-05 5.30E-058.20E-06 2.50E-04 2.61E-052.70E-051.30E-04 5.22E-05 4.80E-08 1.80E-051.60E-05 2.70E-08 0.00E+00 2.53E-05 3.21E-05 5.58E-05 2.30E-07 1.30E-05 2.80E+00 4.53E+00 7.05E+00 4.27E+00 7.95E+00 1.73E+01 1.90E+00 6.70E+01 3.68E+00 2.40E+01 9.67E-01 3.42E+00 0.00E+00 5.02E-02 1.39E-01 6.56E-01 4.35E-01 1.06E+00 8.10E-01 0.00E+00 0.00E+00 5.00E-04 3.78E-04 0.00E+00 2.29E-02 8.71E-03 5.00E-05 2.85E-03 1.09E-03 1.00E-03 2.43E-03 6.10E-05 7.50E-05 6.09E-05 2.24E-03 4.80E-05 3.42E-03 4.00E-04 2.64E-05 4.50E+00 1.23E+00 1.86E+00 1.09E+00 2.13E+00 4.53E+00 5.21E-01 1.77E+01 9.80E-01 6.46E+00 2.58E-01 9.06E-01 0.00E+00 4.81E-04 7.08E-03 1.70E-02 2.03E-02 1.47E-02 3.13E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 2.58E+01 6.99E+02 1.62E+01 3.85E+01 1.19E+03 4.88E+01 3.20E+03 8.52E+00 1.85E+02 1.54E+00 7.66E+00 3.40E+01 5.07E-02 1.53E-01 6.75E-01 4.58E-01 1.08E+00 8.45E-01 1.39E+02 3.70E+02 5.92E-04 4.31E-04 8.20E-06 2.32E-02 8.74E-03 7.70E-05 2.98E-03 1.14E-03 1.00E-03 2.45E-03 7.70E-05 7.50E-05 6.09E-05 2.27E-03 8.01E-05 3.48E-03 4.00E-04 3.95E-05 7.30E+00 11.3-22ASEUS WASTE SYSTEMS WATTS BARTable 11.3-a Design (For 1 Failed Fuel) ected as Release Concentration(ffluent Concentration Limit) With Containment Purge (Sheet 1 of 2)Ep. Rel.(Ci/yr)Des/Ep Design(Ci/yr)Design (Ci/cc)10CFR20 (ECL)Single Unit Oeration C/ECL Dual Unit Oeration C/ECL r-85m r-85 r-87 r-88 Xe-131m Xe-133m Xe-133 Xe-135m Xe-135 Xe-138 Br-84 I-131 I-132 I-133 I-134 I-135 Cs-134 Cs-136 Cs-137 Cr-51 Mn-54 Fe-59 Co-58 Co-60 Sr-89 Sr-90Zr-95 Nb-95 Ba-140 H-3 H-3 (TPC) 1 rod 2 rod C-14 Ar-41TotalTotal (TPC) 1 rod 2 rod2.58E+016.99E+02 1.62E+01 3.85E+01 1.19E+03 4.88E+01 3.20E+03 8.52E+00 1.85E+02 7.66E+00 5.07E-02 1.53E-01 6.75E-014.58E-011.08E+00 8.45E-01 2.27E-03 8.01E-053.48E-035.92E-04 4.31E-04 7.70E-05 2.32E-028.74E-032.98E-03 1.14E-03 1.00E-03 2.45E-034.00E-041.39E+02 3.70E+02 1.53E+03 2.69E+03 7.30E+00 3.40E+0112.2833.087.4512.332.9143.24111.075.04 6.97 5.43 2.5052.414.0026.851.65 7.9140.60165.20 153.220.29 0.473.485.37 1.3822.45 13.491.71 2.340.31 1 1 1 1 1

13.17E+022.31E+04 1.21E+02 4.75E+02 3.45E+03 2.11E+03 3.55E+05 4.29E+011.29E+034.16E+01 1.27E-01 8.03E+00 2.70E+00 1.23E+01 1.78E+00 6.69E+00 9.20E-02 1.32E-025.33E-01 1.73E-042.03E-04 2.68E-04 1.24E-01 1.21E-026.69E-021.54E-02 1.71E-03 5.73E-03 1.26E-041.39E+02 3.70E+02 1.53E+03 2.69E+03 7.30E+00 3.40E+011.10E-107.99E-09 4.18E-11 1.64E-10 1.19E-09 7.29E-10 1.23E-07 1.48E-11 4.46E-10 1.44E-11 4.38E-142.77E-129.33E-13 4.25E-12 6.14E-13 2.31E-12 3.18E-14 4.57E-15 1.84E-13 5.96E-17 7.01E-17 9.27E-17 4.30E-14 4.17E-15 2.31E-14 5.33E-155.92E-161.98E-15 4.34E-17 4.80E-11 1.28E-105.29E-10 9.30E-10 2.52E-12 1.18E-11 1.0E-07 7.0E-07 2.0E-08 9.0E-09 2.0E-06 6.0E-07 5.0E-07 4.0E-08 7.0E-08 2.0E-08 8.0E-08 2.0E-10 2.0E-08 1.0E-09 6.0E-08 6.0E-09 2.0E-10 9.0E-10 2.0E-10 3.0E-08 1.0E-09 5.0E-10 1.0E-09 5.0E-11 1.0E-09 6.0E-12 4.0E-10 2.0E-09 2.0E-09 1.0E-07 1.0E-07 1.0E-07 1.0E-07 3.0E-09 1.0E-08 0.00109510.0114124 0.0020906 0.0182306 0.0005971

0.0 012142

0.2456675 0.0003710

0.0 06375

0.0007188 5.478E-07

0.0 13875

4.67E-05

0.0 042535

1.023E-05

0.0 003851

0.0001589 5.079E-06

0.0 009203

1.988E-09 7.005E-08 1.853E-07 4.298E-05 8.333E-05 2.313E-05

0.0 008877

1.481E-06 9.895E-07 2.171E-08

0.0 004811

0.0012775 0.0052869 0.0092962 0.000841

0.0 011752

0.3109694 0.3117657 0.3157751 0.31978450.00219020.0228248

0.0 041812

0.0364612

0.0 011942

0.0024284 0.49133500.0007420

0.0 12750

0.0014376 1.096E-06 0.027750

0.0 000934

0.0085070 2.046E-050.00077020.0003178 1.016E-05

0.0 018406

3.976E-09 1.401E-07 3.706E-07 8.596E-05 1.667E-04 4.626E-050.0017754 2.962E-06 1.979E-06 4.342E-08 0.00096220.0012775

0.0 052869

0.0092962 0.001682 0.00235040.62193880.62273520.6267446 0.6307539 ASEUS WASTE SYSTEMS 11.3-23WATTS BARTable 11.3-a Design (For 1 Failed Fuel) ected as Release Concentration(ffluent Concentration Limit) With Containment Purge (Sheet 2 of 2)Note The Dual Unit Operation column in the aboe calculation considers dual unit operation. Based on the ealuation done or Reision 7, the per unit concentrations are the same or both units. Thereore, the last column is twice the preceeding column ecept in the case o TPC.Note Dual unit operation considers only Unit 1 with TPC.

11.3-24ASEUS WASTE SYSTEMS WATTS BARTable 11.3-b Design (For 1 Failed Fuel) ected as Release Concentration(ffluent Concentration Limit) With Continuous Filtered Containment ent (Sheet 1 of 2)Ep. Rel.(Ci/yr)Des/Ep Design (Ci/yr)Design (Ci/cc)10CFR20(ECL)Single Unit Oeration C/ECL Dual Unit Oeration C/ECL r-85m r-85 r-87 r-88 Xe-131m Xe-133m Xe-133 Xe-135m Xe-135 Xe-138 Br-84 I-131 I-132 I-133 I-134 I-135 Cs-134 Cs-136 Cs-137 Cr-51 Mn-54 Fe-59 Co-58 Co-60 Sr-89 Sr-90Zr-95 Nb-95 Ba-140 H-3 H-3 (TPC) 1 rod2 rod C-14 Ar-41TotalTotal (TPC) 1 rod 2 rod 9.48E+00 6.78E+02 5.81E+00 1.32E+01 1.09E+03 4.31E+01 2.90E+03 4.68E+00 8.88E+01 4.34E+00 5.07E-02 1.53E-01 6.73E-01 4.57E-01 1.07E+00 8.42E-01 2.27E-03 8.01E-05 3.48E-03 5.92E-04 4.31E-04 7.70E-05 2.32E-02 8.74E-03 2.98E-03 1.14E-03 1.00E-03 2.45E-03 4.00E-04 1.39E+02 3.70E+02 1.53E+03 2.69E+03 7.30E+00 3.40E+01 12.28 33.08 7.45 12.33 2.91 43.24111.07 5.04 6.97 5.43 2.50 52.41 4.00 26.85 1.65 7.91 40.60 165.20 153.22 0.29 0.47 3.48 5.37 1.38 22.45 13.49 1.71 2.34 0.31 1 1 1 1 1

1 1.16E+02 2.24E+04 4.33E+01 1.63E+02 3.18E+03 1.86E+03 3.22E+05 2.36E+01 6.19E+02 2.36E+01 1.27E-01 8.00E+00 2.69E+00 1.23E+01 1.77E+00 6.66E+00 9.20E-021.32E-02 5.33E-01 1.73E-042.03E-042.68E-04 1.24E-01 1.21E-02 6.69E-021.54E-021.71E-03 5.73E-03 1.26E-04 1.39E+02 3.70E+02 1.53E+03 2.69E+03 7.30E+00 3.40E+014.02E-11 7.75E-09 1.50E-11 5.63E-11 1.10E-09 6.44E-10 1.11E-07 8.15E-12 2.14E-10 8.15E-12 4.38E-14 2.77E-12 9.30E-13 4.24E-12 6.10E-13 2.30E-12 3.18E-14 4.57E-15 1.84E-13 5.96E-17 7.01E-17 9.27E-17 4.30E-14 4.17E-15 2.31E-14 5.33E-15 5.92E-16 1.98E-15 4.34E-17 4.80E-11 1.28E-10 5.29E-10 9.30E-10 2.52E-121.18E-111.0E-077.0E-07 2.0E-08 9.0E-092.0E-06 6.0E-07 5.0E-07 4.0E-08 7.0E-08 2.0E-08 8.0E-082.0E-10 2.0E-081.0E-09 6.0E-08 6.0E-092.0E-10 9.0E-102.0E-10 3.0E-08 1.0E-095.0E-101.0E-09 5.0E-11 1.0E-09 6.0E-124.0E-102.0E-09 2.0E-09 1.0E-07 1.0E-071.0E-071.0E-07 3.0E-09 1.0E-080.00040240.0110743

0.0 007480

0.0062505

0.0 005489

0.0010735 0.2227110

0.0 002038

0.0030561

0.0 004073

0.0000005

0.0 138277

0.0000465

0.0 042433

0.0000102

0.0 003837

0.0001589

0.0 000051

0.0009203

0.0 000000

0.0000001

0.0 000002

0.0000430

0.0 000833

0.0000231

0.0 008877

0.0000015

0.0 000010

0.0000000

0.0 004811

0.0012775

0.0 052869

0.0092962

0.0 008410

0.0011752 0.2696131 0.2704095 0.2744189 0.27842830.00080480.02214860.00149600.0125010

0.0 010978

0.0021470 0.44542200.0004076

0.0 061122

0.0008146

0.0 000010

0.0276554

0.0 000930

0.0084866

0.0 000204

0.0007674

0.0 003178

0.00001020.0018406

0.0 000000

0.0000002 0.00000040.00008600.0001666

0.0 000462

0.0017754

0.0 000030

0.0000020

0.0 000000

0.0009622

0.0 012775

0.00528690.00929620.0016820

0.0 023504

0.5392262 0.5400226 0.5440320 0.5480413 ASEUS WASTE SYSTEMS 11.3-25WATTS BARTable 11.3-b Design (For 1 Failed Fuel) ected as Release Concentration(ffluent Concentration Limit) With Conti nuous Filtered Containment ent (Sheet 2 of 2)Note The Dual Unit Operation column in the aboe calculation considers dual unit operation. Based on the ealuation done or Reision 7, the per unit concentrations are the same or both units. Thereore, the last column is twice the preceeding column ecept in the case o TPC.Note Dual unit operation considers only Unit 1 with TPC.

11.3-26ASEUS WASTE SYSTEMS WATTS BARTable 11.3-c Total Releases (based on AS 1.1-1 inCiyr), ith Continuous Filtered Containment ent (Sheet1of 1)Table based on operation o one unit NuclideContain.(1)BuildingAu.BuildingTurbine BuildingTotal r-85m r-85 r-87 r-88 Xe-131m Xe-133m Xe-133 Xe-135m Xe-135 Xe-137 Xe-138 Ar-41 Br-84 I-131 I-132 I-133 I-134 I-135 H-3 Cr-51 Mn-54 Co-57 Co-58 Co-60Fe-59 Sr-89 Sr-90 Zr-95 Nb-95 Ru-103 Ru-106 Sb-125 Cs-134 Cs-136 Cs-137 Ba-140 Ce-141 C-14 3.72E+00 6.69E+02 4.48E-01 3.10E+00 1.07E+03 4.07E+01 2.82E+03 2.26E-02 5.83E+01 3.76E-04 1.69E-02 3.40E+01 8.16E-07 6.74E-03 1.36E-04 2.36E-03 4.26E-05 8.80E-04 1.39E+02 9.21E-05 5.30E-05 8.20E-06 2.50E-04 2.61E-052.70E-051.30E-04 5.22E-05 4.80E-081.80E-05 1.60E-05 2.70E-08 0.00E+00 2.53E-05 3.21E-05 5.58E-05 2.30E-07 1.30E-05 2.80E+00 4.53E+00 7.05E+00 4.27E+00 7.95E+00 1.73E+01 1.90E+00 6.70E+01 3.68E+00 2.40E+01 9.67E-01 3.42E+00 0.00E+00 5.02E-02 1.39E-01 6.56E-01 4.35E-01 1.06E+00 8.10E-01 0.00E+00 5.00E-04 3.78E-04 0.00E+00 2.29E-02 8.71E-03 5.00E-05 2.85E-03 1.09E-03 1.00E-03 2.43E-03 6.10E-05 7.50E-05 6.09E-05 2.24E-03 4.80E-05 3.42E-03 4.00E-04 2.64E-05 4.50E+001.23E+001.86E+00 1.09E+00 2.13E+00 4.53E+00 5.21E-01 1.77E+01 9.80E-01 6.46E+01 2.58E-01 9.06E-01 0.00E+00 4.81E-04 7.08E-03 1.70E-022.03E-021.47E-02 3.13E-02 0.00E+00

.00E+000.00E+000.00E+00 0.00E+00 0.00E+000.00E+000.00E+00 0.00E+00 0.00E+000.00E+00 0.00E+000.00E+00 0.00E+00 0.00E+00 0.00E+000.00E+000.00E+00 0.00E+00 0.00E+00 9.48E+00 6.78E+02 5.81E+00 1.32E+01 1.09E+03 4.31E+01 2.90E+03 4.68E+00 8.88E+01 1.23E+00 4.34E+00 3.40E+01 5.07E-02 1.53E-01 6.73E-01 4.57E-01 1.07E+00 8.42E-01 1.39E+02 5.92E-04 4.31E-04 8.20E-06 2.32E-02 8.74E-03 7.70E-05 2.98E-03 1.14E-03 1.00E-03 2.45E-03 7.70E-05 7.50E-05 6.09E-05 2.27E-03 8.01E-05 3.48E-03 4.00E-04 3.95E-05 7.30E+00 ASEUS WASTE SYSTEMS 11.3-27WATTS BARTable 11.3- Data On Points Of nterest ear Watts ar uclear Plant (Page 1 of 2)

SectorDistance(eters)Chi-oer-(sm3)D-oer-(1m2)TerrainAdustmentFactor il FeedingFactorUnrestricted Area Boundary Unrestricted Area BoundaryUnrestricted Area Boundary Unrestricted Area BoundaryUnrestricted Area Boundary Unrestricted Area BoundaryUnrestricted Area Boundary Unrestricted Area BoundaryUnrestricted Area Boundary Unrestricted Area BoundaryUnrestricted Area Boundary Unrestricted Area BoundaryUnrestricted Area Boundary Unrestricted Area BoundaryUnrestricted Area Boundary Unrestricted Area Boundary NNNE NE ENE EESE SESSE SSSW SWWSW W WNW NWNNW155019801580 137012801250125012501340 155016701430 146014001400 14605.12e-066.35e-061.05e-05 1.23e-051.37e-051.43e-051.11e-056.04e-065.33e-06 4.14e-064.46e-065.47e-062.11e-062.49e-062.05e-06 2.68e-068.13e-091.23e-081.10e-08 8.77e-099.66e-091.16e-08 9.49e-098.21e-091.17e-08 1.05e-087.34e-096.37e-09 2.07e-092.38e-092.13e-09 3.08e-09 1.70 1.80 2.10 1.70 1.60 1.80 1.50 1.50 1.90 2.00 2.10 1.80 1.20 2.50 1.70 1.60 Nearest Resident Nearest Resident Nearest Resident

Nearest Resident Nearest Resident Nearest Resident

Nearest Resident

Nearest Resident Nearest Resident Nearest Resident

Nearest Resident Nearest Resident Nearest Resident Nearest Resident Nearest Resident Nearest Resident Nearest GardenNearest GardenNearest Garden Nearest GardenNearest GardenNearest Garden Nearest GardenNearest GardenNearest Garden NNNE NE ENE EESE SESSE SSSW SWWSW W WNW NWNNW NNNE NE ENE EESE SESSE S213436003353 2414326844161372 152415851979 423018292896 164620614389766461733353 492763724758 4633745422542.84e-062.69e-063.84e-06 6.26e-063.97e-062.64e-06 9.66e-06 4.18e-063.91e-062.76e-061.15e-063.61e-067.30e-07 2.26e-061.03e-063.50e-07 3.13e-071.06e-063.84e-06 2.01e-061.35e-062.26e-06 1.58e-063.73e-072.50e-064.21e-094.41e-093.22e-09 3.83e-092.14e-091.46e-09 8.16e-09 5.56e-098.42e-096.64e-09 1.43e-094.03e-096.01e-102.12e-099.95e-102.97e-103.00e-101.42e-093.22e-09 9.39e-105.42e-101.21e-09 8.97e-102.80e-104.94e-09 1.50 1.80 2.20 1.90 1.70 1.90 1.50 1.40 1.80 1.90 2.00 1.70 1.10 2.90 1.50 1.00 1.00 1.50 2.20 1.60 1.40 1.80 1.30 1.10 1.90 11.3-28ASEUS WASTE SYSTEMS WATTS BARNearest GardenNearest GardenNearest GardenNearest Garden Nearest GardenNearest GardenNearest GardenMil CowMil CowMil CowSSW SWWSW W WNW NWNNWESESSWSSW1979810046675120590931704602 6706228633532.76e-064.28e-078.70e-073.03e-07 1.72e-074.13e-063.28e-071.35e-062.24e-061.36e-066.64e-094.03e-107.11e-102.03e-10 1.05e-103.50e-102.74e-10 6.18e-105.20e-092.84e-09 1.90 1.80 1.50 1.00 1.30 1.10 1.00 1.70 1.90 2.00 0.65 0.65 0.65Table 11.3- Data On Points Of nterest ear Watts ar uclear Plant (Page 2 of 2)

SectorDistance(eters)Chi-oer-(sm3)D-oer-(1m2)TerrainAdustmentFactor il FeedingFactor ASEUS WASTE SYSTEMS 11.3-29WATTS BARTable 11.3- Proected 2 Poulation Distribution Within 5 iles Of Watts ar uclear Plant Poulation Within ach Sector lement Distance From Site (iles)Direction-11-22-33--5TotalN2,6191,8852,7784,7686,17218,222NNW2,15011,76218,76614,5022,54749,727NE1,4413,78316,73429,83878,334130,130ENE1,1103,55329,53963,798253,831351,832E1,91511,35218,6473,06344,013105,990ESE1356,2302,1205,0683,28034,833SE20319,8521,1853,9504,82244,012SSE7828,9511,9072,91848,59374,151S5,8234,58642,88356,43017,985127,707SSW5675,72542,51746,281106,392201,482SW1,05112,97814,44962,307111,795202,630WSW93812,7912,8372,8403,37222,778W9373,4065,5552,9445,47418,316WNW7172,0914,3725,65420,51133,345NW3,9982,88918,63410,46215,95651,940NNW3,4131,53633,84311,6095,89056,290 Total27,799113,368299,818353,432728,9681,523,385 11.3-30ASEUS WASTE SYSTEMS WATTS BARTable 11.3-1 Watts ar uclear Plant- ndiidual Doses From aseous ffluents (For1Unit ithout TPC)EluentPathway Guideline*LocationDose Noble Gases Air dose 10 mradMaimum Eposed Indiidual 1 0.801 mrad/yr Air dose 20 mradMaimum Eposed Indiidual 1 2.710 mrad/yrTotal body 5 mremMaimum Residence 2,30.571 mrem/yr Iodines/ParticulatesSin Bone(critical organ) 15 mrem 15 mremMaimum Residence 2,3Maimum Real Pathway 41.540 mrem/yr 9.15 mrem/yrreadon of odineParticulate Doses (mremyr)Total Vegetable Ingestion6.57Inhalation0.0704Ground Contamination0.0947 Submersion Bee Ingestion 5Total 0.130 2.28 9.145 mrem/yr

• Guidelines are deined in Appendi I to 10 CFR Part 50.

1Maimum eposure point is at 1250 meters in the ESE sector.

2Dose rom air submersion.

3Maimum eposed residence is at 1372 meters in the SE sector.

4Maimum eposed indiidual is a child at 1979 meters in the SSW sector.

5Maimum dose location or all receptors is 1250 meters in the ESE sector.

ASEUS WASTE SYSTEMS 11.3-31WATTS BARTable 11.3-11 Summary Of Poulation DosesTROD Submersion Ground Inhalation Cow Mil Ingestion Bee IngestionVegetable Ingestion Total man-remInant1.26e-02 2.31e-03 6.62e-02 3.22e-01 0.00e+00 0.00e+004.04e-01 Child1.41e-01 2.59e-02 1.24e+00 1.57e+00 3.17e-011.04e+004.34e+00Teen1.28e-01 2.36e-026.64e-016.63e-01 1.59e-014.16e-012.05e+00 Adult 5.57e-01 1.03e-01 2.36e+00 1.25e+00 8.04e-01 1.09e-01 6.17e+00 Total 8.38e-01 1.54e-01 4.33e-00 3.81e+00 1.28e+00 2.55e+00 1.30e+01TOTAL OD Submersion Ground InhalationCow Mil Ingestion Bee IngestionVegetable Ingestion Total man-remInant1.26e-022.31e-033.93e-03 1.04e-01 0.00e+00 0.00e+001.23e-01 Child1.41e-01 2.59e-021.05e-01 5.73e-01 3.06e-011.06e-002.20e+00Teen1.28e-01 2.36e-02 6.65e-022.17e-011.53e-014.40e-011.03e+00 Adult 5.57e-01 1.03e-01 2.76e-01 3.85e-01 7.74e-01 1.21e+00 3.31e+00 Total 8.38e-01 1.54e-01 4.52e-01 1.28e+00 1.23e+00 2.70e+00 6.66e+00 11.3-32ASEUS WASTE SYSTEMS WATTS BARTHIS PAGE INTENTIONALLY BLAN , Attachment 4 Response to FSAR Chapter 11 and FSEIS, Chapter 3 Request For Additional Information Proposed Markups for FSEIS, Chapter 3 Completion and Operation o Watts Bar Nuclear Plant Unit 2 Final Supplemental Enironmental Impact Statement 86Table 3-1. Recetors from Actual Land Use Surey Results Used for Potential aseous Releases From W Unit 2 Recetor umber Recetor Tye SectorDistance(meters) 1 Nearest Residence N 2134 2 Nearest Residence NNE 3600 3 Nearest Residence NE 3353 4 Nearest Residence ENE 2414 5 Nearest Residence E 3139 6 Nearest Residence ESE 4416 7 Nearest Residence SE 1372 8 Nearest Residence SSE 1524 9 Nearest Residence S 1585 10 Nearest Residence SSW 1979 11 Nearest Residence SW 4230 12 Nearest Residence WSW 1829 13 Nearest Residence W 2896 14 Nearest Residence WNW 1646 15 Nearest Residence NW 3048 16 Nearest Residence NNW 4389 17 Nearest Garden N 7644 18 Nearest Garden NNE 6173 19 Nearest Garden NE 3829 20 Nearest Garden ENE 4831 21 Nearest Garden E 8005 22 Nearest Garden ESE 4758 23 Nearest Garden SE 4633 24 Nearest Garden SSE 2043 25 Nearest Garden S 4973 26 Nearest Garden SSW 2286 27 Nearest Garden SW 8100 28 Nearest Garden WSW 4667 29 Nearest Garden W 5150 30 Nearest Garden WNW 5793 31 Nearest Garden NW 3170 32 Nearest Garden NNW 4698 33 Mil Cow ESE 6096 34 Mil Cow ESE 6706 35 Mil Cow SSW 2286 36 Mil Cow SSW 3353 37 Mil Cow NW 8100 Replacethistablewithinformation providedonthe nextpage.

Completion and Operation o Watts Bar Nuclear Plant Unit 2 Table 3-1 Recetors from Actual Land Use Surey Results Used for Potential aseous Releases From W Unit 2Recetor umberRecetorTye Sector Distance (meters)1.Nearest Resident N21342.Nearest Resident NNE36003.Nearest Resident NE33534.Nearest Resident ENE24145.Nearest Resident E32686.Nearest Resident ESE44167.Nearest Resident SE13728.Nearest Resident SSE15249.Nearest Resident S158510.Nearest Resident SSW 197911.Nearest Resident SW423012.Nearest Resident WSW182913.Nearest Resident W289614.Nearest Resident WNW164615.Nearest Resident NW206116.Nearest Resident NNW 438917.Nearest Garden N766418.Nearest Garden NNE617319.Nearest Garden NE335320.Nearest Garden ENE492721.Nearest Garden E637222.Nearest Garden ESE475823.Nearest Garden SE463324.Nearest Garden SSE745425.Nearest Garden S225426.Nearest Garden SSW 197927.Nearest Garden SW810028.Nearest Garden WSW466729.Nearest Garden W512030.Nearest Garden WNW590931.Nearest Garden NW317032.Nearest Garden NNW 460233.Mil Cow ESE670634.Mil Cow SSW 228635.Mil Cow SSW 335386Final Supplemental Enironmental Impact Statement Placethe information providedin thistableinto thetableon thepreceding

page.

Chapter 3 Final Supplemental Enironmental Impact Statement 87Table 3-2. W Total Annual aseous Discharge Per Oerating Unit (curiesyearreactor) uclide Containment uildingAuiliary uilding Turbine uilding Total er Unitr-85m 1.99E+01 4.53E+00 1.23E+00 2.57E+01 r-85 6.90E+02 7.05E+00 1.86E+00 6.99E+02 r-87 1.09E+01 4.27E+00 1.09E+00 1.63E+01 r-88 2.83E+01 7.95E+00 2.13E+00 3.84E+01 Xe-131m 1.17E+03 1.73E+01 4.53E+00 1.19E+03 Xe-133m 4.63E+01 1.90E+00 5.21E-01 4.87E+01 Xe-133 3.12E+03 6.70E+01 1.77E+01 3.20E+03 Xe-135m 3.85E+00 3.68E+00 9.80E-01 8.51E+00 Xe-135 1.55E+02 2.40E+01 6.46E+00 1.85E+02 Xe-137 3.18E-01 9.67E-01 2.58E-01 1.54E+00 Xe-138 3.32E+00 3.42E+00 9.06E-01 7.65E+00 Ar-41 3.40E+01 0.00E+00 0.00E+00 3.40E+01 Br-84 6.00E-05 5.01E-02 4.81E-04 5.06E-02 I-131 7.29E-03 1.39E-01 7.08E-03 1.53E-01 I-132 1.60E-03 6.56E-01 1.70E-02 6.75E-01 I-133 3.55E-03 4.35E-01 2.03E-02 4.59E-01 I-134 1.66E-03 1.06E+00 1.47E-02 1.08E+00 I-135 3.16E-03 8.10E-01 3.13E-02 8.44E-01 H-3 1.37E+02 0.00E+00 0.00E+00 1.37E+02 H-3 (TPC) 3.70E+02 0.00E+00 0.00E+00 3.70E+02 Cr-51 9.21E-05 5.00E-04 0.00E+00 5.92E-04 Mn-54 5.30E-05 3.78E-04 0.00E+00 4.31E-04 Co-57 8.20E-06 0.00E+00 0.00E+00 8.20E-06 Co-58 2.50E-04 2.29E-02 0.00E+00 2.32E-02 Co-60 2.61E-05 8.71E-03 0.00E+00 8.74E-03 Fe-59 2.70E-05 5.00E-05 0.00E+00 7.70E-05 Sr-89 1.30E-04 2.85E-03 0.00E+00 2.98E-03 Sr-90 5.22E-05 1.09E-03 0.00E+00 1.14E-03 Zr-95 4.80E-08 1.00E-03 0.00E+00 1.00E-03 Nb-95 1.80E-05 2.43E-03 0.00E+00 2.45E-03 Ru103 1.60E-05 6.10E-05 0.00E+00 7.70E-05 Ru-106 2.70E-08 7.50E-05 0.00E+00 7.50E-05 Sb-125 0.00E+00 6.09E-05 0.00E+00 6.09E-05 Cs-134 2.53E-05 2.24E-03 0.00E+00 2.27E-03 Cs-136 3.21E-05 4.80E-05 0.00E+00 8.01E-05 Cs-137 5.58E-05 3.42E-03 0.00E+00 3.48E-03 Ba-140 2.30E-07 4.00E-04 0.00E+00 4.00E-04 Ce-141 1.30E-05 2.64E-05 0.00E+00 3.94E-05 C-14 2.80E+00 4.50E+00 0.00E+00 7.30E+00 A companion igure, illustrating the release points or radioactie gaseous eluents rom WBN is

presented in Figure 3-9.Replacethistablewithinformationprovidedinthetableonthenextpage.

Chapter 3 Table 3-2 W Total annual aseous discharge Per Oerating Unit (curiesyearreactor) uclide Containment uildingAuiliary uilding Turbine uilding Totalr-85m 3.72E+00 4.53E+00 1.23E+00 9.48E+00 r-856.69E+02 7.05E+001.86E+00 6.78E+02 r-874.48E-01 4.27E+001.09E+00 5.81E+00 r-883.10E+00 7.95E+002.13E+00 1.32E+01 Xe-131m 1.07E+03 1.73E+01 4.53E+00 1.09E+03 Xe-133m 4.07E+01 1.90E+00 5.21E-01 4.31E+01 Xe-133 2.82E+03 6.70E+01 1.77E+01 2.90E+03 Xe-135m 2.26E-02 3.68E+00 9.80E-01 4.68E+00 Xe-135 5.83E+01 2.40E+01 6.46E+01 8.88E+01 Xe-137 3.76E-04 9.67E-01 2.58E-01 1.23E+00 Xe-138 1.69E-02 3.42E+00 9.06E-01 4.34E+00 Ar-413.40E+01 0.00E+000.00E+00 3.40E+01 Br-848.16E-07 5.02E-024.81E-04 5.07E-02 I-1316.74E-03 1.39E-017.08E-03 1.53E-01 I-1321.36E-04 6.56E-011.70E-02 6.73E-01 I-1332.36E-03 4.35E-012.03E-02 4.57E-01 I-1344.26E-05 1.06E+001.47E-02 1.07E+00 I-1358.80E-04 8.10E-013.13E-02 8.42E-01 H-31.39E+02 0.00E+000.00E+00 1.39E+02 H-3 (TPC)3.70E+02 0.00E+00 0.00E+00 3.70E+02 Cr-519.21E-05 5.00E-040.00E+00 5.92E-04 Mn-54 5.30E-05 3.78E-040.00E+00 4.31E-04 Co-578.20E-06 0.00E+000.00E+00 8.20E-06 Co-582.50E-04 2.29E-020.00E+00 2.32E-02 Co-602.61E-05 8.71E-030.00E+00 8.74E-03 Fe-59 2.70E-05 5.00E-050.00E+00 7.70E-05 Sr-891.30E-04 2.85E-030.00E+00 2.98E-03 Sr-905.22E-05 1.09E-030.00E+00 1.14E-03 Zr-954.80E-08 1.00E-030.00E+00 1.00E-03 Nb-951.80E-05 2.43E-030.00E+00 2.45E-03 Ru-1031.60E-05 6.10E-050.00E+00 7.70E-05 Ru-1062.70E-08 7.50E-050.00E+00 7.50E-05 Sb-125 0.00E+00 6.09E-05 0.00E+00 6.09E-05 Cs-134 2.53E-05 2.24E-03 0.00E+00 2.27E-03 Cs-136 3.21E-05 4.80E-05 0.00E+00 8.01E-05 Cs-137 5.58E-05 3.42E-03 0.00E+00 3.48E-03 Ba-140 2.30E-07 4.00E-04 0.00E+00 4.00E-04 Ce-1411.30E-05 2.64E-050.00E+00 3.95E-05 C-14 2.80E+00 4.50E+000.00E+00 7.30E+00 A companion igure illustrating the release points or radioactie gaseous eluents rom WBN is presented in Figure 3-9. Final Supplemental Enironmental Impact Statement 87Placetheinformationprovidedinthistableintothetableontheprecedingpage.

Chapter 3 Final Supplemental Enironmental Impact Statement 89A tabulation o the resulting calculated gaseous doses to indiiduals per operational unit is gien in Table 3-21.Table 3-21. W Doses From aseous ffluent For Unit 2 Without Tritium Production for ear 2 ffluent Pathay uideline 1 Location Dose Noble Gases Air dose 10 mrad Maimum Eposed Indiidual 2 0.801 mrad/year Air dose 20 mrad Maimum Eposed Indiidual 2 2.710 mrad/year Total body 5 mrem Maimum Residence 3,4 0.571 mrem/year Iodines/ Particulate Sin10 mrem Maimum Residence 3,4 1.540 mrem/year Thyroid(critical organ) 15 mrem Maimum Real Pathway 5 2.715 mrem/yearreadon of odineParticulate Doses (mremyr) Cow Mil with Feeding Factor o 0.65 2.44 Inhalation 0.174 Ground Contamination0.0405 Submersion 0.0603Bee Ingestion 2 0.00 Total 2.7148 1Guidelines are deined in Appendi I to 10 CFR Part 50.

2Maimum eposure point is at 1250 meters in the ESE sector.

3Dose rom air submersion.

4Maimum eposed residence is at 1372 meters in the SE sector.

5Maimum eposed indiidual is an inant at 3353 meters in the SSW sector.

The estimated annual airborne releases and resulting doses as presented by the 1972 FES, the WBN Unit 1 FSAR, Unit 2, Unit 1 and 2 totals, and recent historical data rom WBN Unit 1 (as submitted in the Annual Radioactie Eluent Reports to the NRC) with NRC guidelines gien in 10 CFR 50 Appendi I are compared in Table 3-22. These guidelines are designed to assure that releases o radioactie material rom nuclear power reactors to unrestricted areas during normal conditions, including epected occurrences, are ept as low as practicable. Replacewith"Bone" Replace with"9.15"Replacewith TotalVegetable IngestionReplacewith 5 Replace with 6.57 0.0704 0.0947 0.130 2.28 9.145Replacewith

1979Replacewith

child Insert 5Maximumdoselocationforallreceptorsis1250metersin theESEsector.

Replace with*1 2

3 4Replacewith 2,3 Replace with 4Replacewith

1 Completion and Operation o Watts Bar Nuclear Plant Unit 2 Final Supplemental Enironmental Impact Statement 90Table 3-22. Comarison of stimated Annual Airborne Releases and Resulting Doses 12 FS(Table 2.-2)

Unit 1 FSAR Unit 2 aluation Units 1 2 Combined Unit 1 1-year Oerational Aerage 1 CFR 5 Aendi uidelines er Unit Particulate Actiity (Ci 1)3.0E-01 7.6E+00 4.70E-02 7.6E+00 9.29E-05 10 oble as Actiity (Ci 1)7.0E+03 1.4E+04 4.84E+03 4.84E+03 2.7E-03 N/A 2 ternal Dose (mrad 3)6.6E+006.2E+003.5E+009.7E+003.69E-01 10 Organ Dose (mrem 4)3.5E+00(inhalation and mil only)1.1E+01 (all pathways)2.82E+00 (all pathways)1.38E+01 (all pathways)8.3E-02 (all pathways)15 1 Ci = Curies 2 N/A = Not Applicable 3 mrad = millirad 4 mrem = millirem Two conclusions can be drawn rom the data in Table 3-20 The Unit 2 FSAR estimates, een though based on ery conseratie (worst-case) assumptions, indicate that estimated doses continue to meet the per unit dose guidelines gien in 10 CFR Part 50, Appendi I. Historical WBN operational data or airborne eluents indicate that actual releases and resulting dose estimates (eternal and organ) to the public are a small raction o the Appendi I guideline (aeraging about 1 percent or less). Based on these conclusions, the analyses o radiological impact rom airborne release in the 1972 FES continue to be alid, and operation o WBN Unit 2 would not materially change the

results.Population DosesTVA has estimated the radiological impact rom the normal operation o WBN Unit 2 using a 50-mile regional population proection or the year 2040 o 1,523,385. The estimated population doses as presented by the 1972 FES, the WBN Unit 1 FSAR, Unit 2, Unit 1 and Unit 2 totals, and recent historical data rom WBN (as submitted in the Annual Radioactie Eluent Reports to the

NRC) are presented in Table 3-23. Table 3-23. stimated Poulation Doses From Oeration of Watts ar uclear Plant 12 FS(Table 2.-)

Unit 1 FSAR Unit 2 aluation Units 1 2 Combined Unit 1 1-year Oerational Aerage 1 CFR 5 Aendi uidelines3.1E+01 12.8E+00 2.362E+01 3.64E+01 3.38E-01 N/A Replacewithdataonthenextpage ForFSEISTable3-22ForFSEISTable 3-23 9.42E-01 9.68E+03 Completion and Operation o Watts Bar Nuclear Plant Unit 2 Final Supplemental Enironmental Impact Statement 88Figure 3-. Watts ar uclear Plant aseous ffluent Release Points Revisetoread AuxiliaryBuildingVent(Common)and ContinuousVents , Attachment 5 Response to FSAR Chapter 11 and FSEIS, Chapter 3 Request For Additional Information Proposed Clean Copy of FSEIS, Chapter 3 Chapter 3 Final Supplemental Enironmental Impact Statement 33CAPTR 3 3. CAS T AFFCTD ROT AD ROTAL COSUCS The enironmental conseuences o constructing and operating WBN were addressed comprehensiely in the 1972 FES or WBN Units 1 and 2. Subseuent enironmental reiews updated that analysis, as described in Section 1.3 o this FSEIS. By 1996, when the construction o WBN Unit 1 was complete, most o the construction eects had already occurred. As described in Section 2.1, WBN Unit 2 would use structures that already eist and most o the wor reuired to complete Unit 2 would occur inside those buildings. As shown in Figure 1-2, any disturbance proposed or the construction o new support acilities would be within the current plant ootprint. Although the acility locations in this tentatie site plan are not irm, any relocation would occur within the mared area to be disturbed. TVA would use standard construction BMPs to control minor construction impacts to air and water rom dust, sedimentation, and noise. The reiews by TVA and NRC in 1993 and 1995 ocused primarily on the completion o WBN Unit 1. Some modiications to plant design and operations hae occurred since that time.

Chapter 3 summarizes the enironmental eects assessed in past WBN-related enironmental reiews, identiies any new or additional eects that could result rom the completion and operation o WBN Unit 2, and assesses the potential or impacts. The current reiew ocused

on the entire proposed area to be disturbed. Cumulatie ffects cumulatie eects o constructing and operating WBN Units 1 and 2 were considered in the 1972 FES and the 1995 NRC FES, which TVA adopted, The potential or cumulatie eects to surace water and auatic resources are addressed by the plants NPDES permit and its monitoring reuirements. Concerns oer potential cumulatie eects to air were tied to emissions rom WBF plant, which had not operated since 1983 and has since been retired. Cumulatie eects are also considered in many o the documents incorporated by reerence and/or tiered rom or this supplement. Most notably, cumulatie eects o spent uel storage and transportation were addressed in the CLWR FEIS cumulatie eects o transportation o radioactie materials were addressed in NUREG-75/038 (NRC 1975) and cumulatie eects o hydrothermal and water supply were addressed in the ROS FEIS. In this reiew, TVA has ound that no new or additional cumulatie eects beyond those identiied in earlier NEPA documents are epected to result rom completing the construction o WBN Unit 2. As summarized in Table 2-1, or the most part, only minor, temporary, or insigniicant eects are epected or most o the resources considered. As such, these eects are not epected to contribute to cumulatie impacts on aected resources. The potential or additional operational cumulatie eects are considered in the ollowing assessments.

Completion and Operation o Watts Bar Nuclear Plant Unit 2 Final Supplemental Enironmental Impact Statement 343.1. Water uality 3.1.1. S W E Hydrothermal eects primarily consist o the impact o the heated eluent rom WBN on the Tennessee Rier. Here, hydrothermal eects are diided into two categories, near-ield eects and ar-ield eects. Near-ield eects consist o the impact o the heated eluent on the rier water temperature in the immediate icinity o the plant, as deined by the assigned miing zones or the outalls in the NPDES permit. Limits or rier water temperature are speciied by the State o Tennessee in the NPDES permit or the plant. Far-ield eects consist o the impact on the receiing stream on a larger scale, in this case all o Chicamauga Reseroir. Waste heat created by the operation o WBN is dissipated both in the atmosphere and in the Tennessee Rier. A description o the heat dissipation system is gien in Section 2.2.2. The current coniguration o the system includes three outalls to the rier. Outall 101 includes regulated releases through two multiport diusers located on the bottom o the rier at TRM 527.9. Outall 102 includes emergency oerlow rom the plant yard holding pond and consists o a surace discharge rom a local stream channel at TRM 527.2. Historically, releases rom Outall 102 hae been made only when maintenance is reuired or Outall 101. Outall 113 includes releases rom the WBN SCCW system through a discharge structure at TRM 529.2.

Outall 113, originally the outall or the retired WBF, consists o a shoreline release slightly below the water surace o the rier. The current coniguration o the SCCW system proides water solely or WBN Unit 1. For the combined operation o Unit 1 and Unit 2, the control structures that regulate the amount SCCW low between and out o the cooling tower basins would need to be modiied to presere the original design bases or all three outalls. An etensie number o preious studies on the hydrothermal characteristics o releases rom WBN hae been conducted oer the years. These studies are described and their results summarized in Appendi A. In general, these studies hae basically ealuated and

documented1. That WBN can be eectiely operated without causing iolations o water temperature limits in the Tennessee Rier (near-ield eect). 2. The alidity o operating assumptions made in preious analyses.

3. The alidity o the assigned miing zones and modeling results or rier temperature.

4. Ealuations or changes such as the addition o the SCCW system or the Reseroir Operations Study (ROS).5. That operation o WBN is not epected to hae any noticeable impact on Chicamauga Reseroir (ar-ield eect). PDS Rier Temerature Limits The current NPDES permit limits or managing the near-ield impact o the thermal eluent rom WBN outalls are summarized in Table 3-1. Those or Outall 101 and Outall 102 apply to the temperature o the eluent beore it enters the rier (i.e., end-o-pipe limitations). Those or Outall 113 are instream limitations and apply relatie to the assigned miing zones. Releases rom Outall 101 can be made only when the low in the rier rom WBH is at or aboe 3500 cs.

Chapter 3 Final Supplemental Enironmental Impact Statement 35Releases rom Outall 113 do not reuire a minimum low in the rier, ecept in eents where there is a planned, sudden change in the thermal loading rom the SCCW system. Table 3-1. PDS Temerature Limits for W Outfalls to the Tennessee Rier Outfallffluent Parameter Daily Reort Limit101 Eluent Temperature Daily Ag 35.0C (95F) 102 Eluent Temperature Grab35.0C (95F) 113 Instream Temperature 1Instream Temperature Rise 2Instream Temperature Rate-o-Change 1Instream Temperature Receiing Stream Bottom 3Ma Hourly AgMa Hourly AgMa Hourly Ag Ma Hourly Ag30.5C (86.9F) 3.0 C (5.4F) 2 C/hr (3.6 F/hour)33.5C (92.3F) Notes 1Downstream edge o miing zone 2Upstream ambient to downstream edge o miing zone 3 Mussel relocation zone at SCCW outlet iing ones The miing zone or Outall 101 is shown in Figure 3-1. The recommended dimensions o the miing zone are based on a physical hydrothermal model test o the diusers (TVA 1977b, 1977c). Measurements rom the model indicated that suicient miing would be achieed at a distance euialent to roughly the length o the outlow section o the diuser ports. The blowdown system includes two diuser legs, one containing an outlow section 80 eet long (upstream) and one containing an outlow section 160 eet long (downstream). Hence, the assigned miing zone or Outall 101 is 240 eet wide and 240 eet downstream. The width o the rier at Outall 101 is about 1100 eet, thus about 80 percent o the rier is aailable or sae passage o ish. The design o the diusers and miing zone are based on the operation o both units at WBN, and the etreme rier conditions used or the design o the diuser are still applicable (i.e., minimum rier low o 3500 cs). For the operation o one unit, the perormance o the diuser was conirmed by ield studies ater the startup o Unit 1 (TVA 1998b). Similar studies would be perormed to conirm the perormance o the diusers with the operation o two units at WBN. Since releases resulting rom the emergency oerlow o the yard holding pond are so inreuent, a miing zone currently is not deined in the NPDES permit or Outall 102. For Outall 113, standards or water temperature are enorced by means o two miing zones, actie and passie, as shown in Figure 3-2. Two miing zones are used to better align monitoring o Outall 113 with the behaior o the eluent in the rier. Computations and measurements show that spreading o the eluent rom Outall 113 aries substantially between conditions and low in the rier rom Watts Bar Dam (TVA 1997b, 2001, 2004b). For conditions low, the eluent tends to reside in the right-hand-side o the rier (acing downstream) and is monitored by the actie miing zone, which includes instream temperature monitors at its downstream edge. For conditions low, the eluent can spread across the rier and is monitored by the passie miing zone. Since the passie miing zone encompasses regions o the rier that must remain clear or naigation, the adeuacy o the passie miing zone is checed biannually (winter and summer) by special water termperature sureys (i.e., rather than instream monitors). Outall 113 is a near-surace discharge, and computations and measurements conirm that the heated eluent rom Outall 113 disperses in the surace region o the water column (TVA, 1997b, 2001, 2004b, 2005c, 2006a, 2007b, 2007c), proiding ample room beneath or the sae passage o ish, particularly in the deep Completion and Operation o Watts Bar Nuclear Plant Unit 2 Final Supplemental Enironmental Impact Statement 36naigation channel on the right-hand-side o the rier. TVA would not change the dimensions o the Outall 113 miing zones with the completion and startup o Unit 2. Figure 3-1. iing one for Outfall 11 Figure 3-2. iing ones for Outfall 113 It is important to note that since the startup o WBN Unit 1, the plant has operated successully through a wide range o rier low conditions, without any eceedences o the NPDES limits or the near-ield impact o thermal eluent on the Tennessee Rier. Concurrently, no signiicant Chapter 3 Final Supplemental Enironmental Impact Statement 37aderse impacts hae been reported on the ecological health o the rier as a result o releases rom any o the WBN discharge structuresOutall 101, Outall 102, or Outall 113. Udated ydrothermal Analyses In depth near-ield hydrothermal analyses o the heat dissipation system hae been updated or the proposed completion and operation o WBN Unit 2 (Dynamic Solutions 2007). This was necessary or seeral reasons. First, although the SCCW system has proen to be an eectie method to boost generation o the plant, the combined operation o Unit 1 and Unit 2 with the SCCW system had not been eamined. Second, detailed multiyear simulations with the dual miing zone or Outall 113, as depicted in Figure 3-2, had not been perormed. Third, preious model ealuations had not considered the combined operation o Unit 1 and Unit 2 coupled with the rier operating policy o the ROS FEIS or the characteristics o new steam generators recently installed or WBN Unit 1. Appendi A includes more detail about preious model ealuations and the modiications to the Outall 113 miing zone. The updated analyses began with the model used or the 1998 EA o the SCCW system (TVA 1998a). For the updated analyses, modiications were made in the model or (1) combined operation o Unit 1 and Unit 2, (2) discharges rom Outall 113 with dual miing zones, (3) ambient rier conditions based on the rier operations policies o the ROS, and (4) perormance characteristics o the new steam generators or WBN Unit 1. In this process, the ollowing modeling assumptions are emphasized The cooling tower or WBN Unit 2 would be upgraded to proide the same leel o perormance as that o the cooling tower or Unit 1.

WBN Unit 2 would operate with the original steam generators.

The SCCW system currently seres Unit 1. With the combined operation o Unit 1 and Unit 2, the SCCW system would sere both units. While some modiications to the SCCW system would be reuired or combined operation (see aboe), these modiications would be limited to installed plant systems and would not change the olume o water deliered and remoed by the SCCW system. The ollowing analysis assumes that the SCCW system would be changed to proide serice solely to Unit 2. This assumption proides a suitable bounding estimate o the potential order o magnitude o the hydrothermal impact on the Tennessee Rier rom the operation o Unit 2 while both Units are in operation. Although other options are possible, none would result in a substantial change in olume and/or temperature o low released to the rier through Outalls 101, 102, and 113. Miing o thermal eluent rom Outall 101 is adeuately described by the obsered behaiour in the physical model study o the discharge diusers (TVA 1977b TVA 1997c),

and in a ield study conducted ater the startup o Unit 1 (TVA 1998c). Miing o thermal eluent rom Outall 113 is adeuately described by an analysis tool recommended by the U.S. EPA nown as CORMIX (ira, et al. 1996). Model simulations were perormed or a 30-year period based on obsered hydrology and meteorology in the upper Tennessee Rier watershed or years 1976 through 2005. The model input reuires the low and ambient temperature o the rier at WBN. To incorporate the impact o the ROS operating policy, a reseroir scheduling model was used to help estimate the hourly rier low at WBN. Hourly alues o the ambient water temperature were estimated using SysTemp, a collection o lined water uality models o the ey water Completion and Operation o Watts Bar Nuclear Plant Unit 2 Final Supplemental Enironmental Impact Statement 38bodies in the Tennessee Rier reseroir system. The reseroir scheduling model and SysTemp were both preiously calibrated as a part o the ROS FEIS (TVA 2004a).An important aspect common to all the aboe assumptions is that with the addition o Unit 2, the blowdown and SCCW systems would be adapted, i needed, to ensure no substantial change in the design bases or Outalls 101, 102, and 113. That is, the maimum olume o low and heat rom the outalls would not change substantially rom their original design. For Outalls 101 and 102, this includes the operation o both WBN units, and or Outall 113, this includes a maimum low o about 365 cs, whether rom Unit 1, Unit 2, or both Unit 1 and Unit 2. In this manner, the updated hydrothermal analyses would primarily ascertain the epected impact o recent changes in rier operations, and proide assurance that with both WBN units, the current miing zones and methods o operating the plant and rier would eectiely satisy state standards or instream water temperature and proide sae passage or auatic species in Chicamauga Reseroir.Two operating cases or WBN were considered as part o the updated hydrothermal analysesUnit 1 only (i.e., current, base case conditions) and combined operation o Unit 1 and Unit 2, with the SCCW system sering only Unit 2. For both cases, the ey statistical properties o low and temperature o water released rom Watts Bar Dam are summarized in Table 3-2. As shown, daily aerage releases ranged rom a minimum o 3300 cs in May to a maimum o oer 150,000 cs in both March and April. Flows oer about 45,000 cs would be due to spill operations in support o lood control. On an hourly basis, releases can be 0 cs, due to peaing operations o the hydro units. The oerall aerage release or the entire 30-year period was about 27,000 cs. The hourly release temperature aried between a minimum o 36.3F in February and a maimum o 84.6F in August. Thus, based on historical hydrology and meteorology, the ambient rier temperature is not epected to eceed the state standard o 86.9F.Table 3-2. stimated ydrothermal Conditions for Release From Watts ar Dam Daily Aerage Release (cfs) ourly Release (cfs) ourly Release Temerature (F) onth in ean a in ean a in ean aan 5,600 36,900 122,400 0 36,900 122,40036.6 44.0 52.0 Feb 6,300 43,000 115,300 0 43,000 115,30036.3 43.8 52.2 Mar 5,000 36,600 156,600 0 36,600 156,60038.9 48.9 60.0 Apr 3,600 21,000 156,600 0 21,000 156,60047.8 56.3 65.4 May 3,300 17,300 119,300 0 17,300 119,30054.4 63.9 73.2 un 5,200 21,600 81,300 0 21,600 81,300 61.6 71.3 79.1 ul 5,900 19,300 60,200 0 19,300 60,200 68.7 76.4 83.9 Aug 5,600 22,600 41,200 0 22,600 49,100 72.4 78.0 84.6 Sep 4,300 22,400 81,300 0 22,400 81,300 69.6 76.2 82.7 Oct 4,000 21,000 70,600 0 21,000 70,600 57.5 68.3 79.2 No 6,500 29,700 85,000 0 29,700 85,000 47.1 58.5 68.1 Dec 4,400 32,300 102,300 0 32,300 102,30037.7 49.3 59.5 Notes1. Results per SysTemp hydrothermal model simulation

2. Reseroir operating policy per the ROS FEIS 3. Historical hydrology and meteorology or 1976 through 2005 Chapter 3 Final Supplemental Enironmental Impact Statement 39The ollowing summaries are proided or the results o the updated hydrothermal analyses. Outall 101The estimated hydrothermal conditions or the thermal eluent rom Outall 101 are gien in Table 3-3 or sole operation o Unit 1 (base case) and Table 3-4 or the combined operation o both Unit 1 and Unit 2. For the sole operation o Unit 1, the hourly discharge through Outall 101 aried between 0 cs and about 108 cs. Discharges o 0 cs occur or periods when the release rom WBH is less than 3500 cs. With both WBN units in serice, the hourly discharge rom Outall 101 can be as large as 175 cs, as shown in Table 3-4. This is about 3 percent larger than the maimum alue cited in preious design studies (TVA 1977b), but is not considered signiicant with respect to the as-built size o the blowdown system. For both cases, the estimated maimum daily aerage eluent temperature was 89.8F, well below the NPDES limit o 95F. For the purpose o udging the impact on instream rier temperatures, the statistical properties o the resulting hourly rier temperature and rier temperature rise also are gien in Tables 3-3 and 3-4. As shown, the maimum alues are well below the state standards o 86.9F or maimum rier temperature and 5.4 F or maimum rier temperature rise. For the latter, the estimated maimum temperature rise is 1.3 F or the sole operation o Unit 1 and 1.6 F or the combined operation o both Unit 1 and Unit 2. At these leels, the maimum instream temperature rate-o-change would be well below the state standard o 3.6 F per

hour.Table 3-3. stimated ydrothermal Conditions for Thermal ffluent From Outfall 11 With Unit 1 Oeration ourly Discharge (cfs) Daily Aerage ffluent Temerature (F) ourly Temerature at Donstream dge of iing one (F) ourly Temerature Rise at Donstream dge of iing one (F) onth in ean a in ean a in ean a in ean aan 0 44 102 49.0 64.0 79.4 38.2 45.8 53.8 0.0 0.1 1.1 Feb 0 44 102 49.2 65.9 78.4 37.9 45.6 55.7 0.0 0.1 1.1 Mar 0 43 102 53.2 69.6 82.1 40.3 50.5 61.0 0.0 0.1 1.1 Apr 0 43 108 62.5 74.2 84.6 48.9 58.2 66.9 0.0 0.2 1.3 May 0 43 108 70.7 78.9 85.8 57.3 66.1 73.8 0.0 0.2 0.9 un 0 43 108 75.3 83.6 89.0 62.7 72.8 79.6 0.0 0.1 0.8 ul 0 43 108 80.2 85.6 89.1 70.2 77.5 84.6 -0.2 0.1 0.5 Aug 0 43 108 77.4 85.6 89.8 73.8 78.8 84.7 -0.1 0.0 0.5 Sep 0 43 108 71.6 81.8 88.2 69.9 76.8 83.0 -0.3 0.0 0.5 Oct 0 43 102 63.7 75.3 83.9 58.3 68.8 79.3 -0.3 0.0 0.6 No 0 43 102 56.2 69.5 83.3 47.9 59.3 69.7 -0.1 0.0 1.0 Dec 0 43 102 49.4 65.2 81.2 38.2 50.7 61.7 -0.1 0.1 1.2 Notes1. Results per WBN hydrothermal model simulation 2. WBN Unit 1 with new steam generators o 2006 3. WBN Unit 2 idle 4. SCCW sering Unit 1 5. Reseroir operating policy per the ROS FEIS 6. Historical hydrology and meteorology or 1976 through 2005 Completion and Operation o Watts Bar Nuclear Plant Unit 2 Final Supplemental Enironmental Impact Statement 40Table 3-. stimated ydrothermal Conditions for Thermal ffluent From Outfall 11 With Unit 1 and Unit 2 Oeration ourly Discharge (cfs) Daily Aerage ffluent Temerature (F) ourly Temerature at Donstream dge of iing one (F) ourly Temerature Rise at Donstream dge of iing one (F) onth in ean a in ean a in ean a in ean aan 0 80 165 48.9 64.0 79.3 38.3 45.9 53.9 0.0 0.2 1.4 Feb 0 80 165 49.1 65.9 78.3 38.0 45.7 56.0 0.0 0.2 1.6 Mar 0 79 166 53.1 69.6 82.1 40.3 50.6 61.2 0.0 0.2 1.5 Apr 0 79 171 62.5 74.2 84.5 48.9 58.3 67.3 0.0 0.3 1.6 May 0 80 170 70.6 78.9 85.8 57.4 66.2 73.9 0.0 0.3 1.0 un 0 80 171 75.3 83.6 88.9 62.7 72.8 79.6 0.0 0.2 0.9 ul 0 81 175 80.1 85.5 89.0 70.2 77.6 84.6 -0.2 0.2 0.6 Aug 0 81 172 77.3 85.5 89.8 73.9 78.8 84.7 -0.2 0.1 0.6 Sep 0 80 170 71.6 81.7 88.2 69.9 76.8 83.1 -0.4 0.1 0.6 Oct 0 80 166 63.6 75.2 83.8 58.4 68.9 79.3 -0.4 0.1 0.9 No 0 80 166 56.1 69.4 83.2 47.9 59.4 69.8 -0.2 0.1 1.1 Dec 0 79 166 49.3 65.1 81.1 38.4 50.8 61.8 -0.2 0.2 1.5 Notes1. Results per WBN hydrothermal model simulation 2. WBN Unit 1 with new steam generators o 2006 3. WBN Unit 2 with original steam generators 4. SCCW sering Unit 2 5. Unit 2 cooling tower perormance the same as Unit 1 cooling tower perormance 6. Reseroir operating policy per the ROS FEIS 7. Historical hydrology and meteorology or 1976 through 2005 Outall 102For both the sole operation o Unit 1 (base case) and the combined operation o both Unit 1 and Unit 2, there were no eents with oerlow rom the plant yard holding pond. As a result, under normal operating conditions, releases rom Outall 102 are not epected.Outall 113The estimated hydrothermal conditions or the thermal eluent rom Outall 113 are gien in Table 3-5 or sole operation o Unit 1 (base case) and Table 3-6 or the combined operation o both Unit 1 and Unit 2. For both cases, the hourly discharge through Outall 113 aried between about 222 cs and about 294 cs. This demonstrates that the low rom the SCCW system is independent o the unit sered by the system (i.e., Unit 1 or the base case and Unit 2 or the case with both units in operation). In a similar ashion, or both cases, the hourly eluent temperature through Outall 113 aried between about 39.5F and 97.3F. Since the low and temperature o the SCCW eluent are essentially the same or both cases, similar conditions are ound or instream temperature conditions. The estimated maimum hourly instream rier temperature or both cases is 84.7F, well below the NPDES limit o 86.9F. The estimated maimum hourly instream rier temperature rise or both cases is 5.4 F, which is the same as the current NPDES limit. The estimated largest hourly instream rier temperature rate-o-change (up/+ or down/-) or both cases is -3.6 F per hour, which is the same as the current NPDES limit. The etreme alues or the temperature rise and temperature rate-o-change occur in the cooler winter months o the year, when the buoyancy-related miing o the thermal eluent is reduced. In practice, TVA would not ris operation o the SCCW system with the eluent parameters so close to the NPDES limits. In etreme temperature eents, the SCCW system would be operated in a more conseratie manner than what has been assumed in the hydrothermal model. In particular, the temperature o the Outall 113 eluent would be reduced 41Chapter 3Final Supplemental Enironmental Impact StatementTable 3-5. stimated ydrothermal Conditions for Thermal ffluent From Outfall 113 With Unit 1 Oeration ourly Discharge (cfs) ourly ffluent Temerature (F) ourly Temerature at Donstream dge of iing one (F) ourly Temerature Rise at Donstream dge of iing one (F) ourly Temerature Rate-of-Change at Donstream dge of iing one (Fhr) 1 onth in ean a in ean a in ean a in ean a in ean aan 222 222 223 39.5 62.7 82.7 38.1 45.8 53.7 0.0 1.8 5.4 -3.4 0.0 2.7 Feb 222 222 223 40.7 64.8 82.8 37.8 45.6 55.3 0.3 1.8 5.4 -3.6 0.0 2.4 Mar 222 223 227 45.9 68.3 86.1 40.2 50.9 62.0 0.0 1.9 5.4 -3.6 0.0 2.5 Apr 226 256 277 57.5 72.7 90.2 48.9 58.6 68.5 0.0 2.3 5.4 -3.6 0.0 2.4 May 240 286 292 63.6 79.3 90.9 56.8 66.3 74.6 0.0 2.4 5.4 -3.0 0.0 1.8 un 257 291 292 68.6 83.8 94.2 62.7 73.1 79.8 0.0 1.8 5.2 -2.8 0.0 1.7 ul 275 292 293 71.6 86.1 97.3 70.2 77.8 84.5 0.0 1.4 4.3 -2.2 0.0 1.7 Aug 284 292 293 73.2 85.5 94.9 73.6 78.9 84.7 0.0 0.9 3.5 -2.0 0.0 1.5 291 292 293 65.7 81.7 92.6 69.6 76.9 83.0 0.0 0.7 2.9 -1.7 0.0 1.3 Oct 287 291 292 57.7 75.0 89.7 58.3 69.3 80.4 0.0 1.0 4.8 -2.8 0.0 2.0 No 226 258 288 52.7 69.7 85.7 47.9 59.8 70.9 0.0 1.3 5.4 -3.4 0.0 2.1 Dec 222 222 226 44.5 64.7 84.4 39.1 51.0 63.2 0.0 1.7 5.4 -3.5 0.0 2.1 1Amount o change in reier temperature, up or down, in one hour. Additional Notes 1. Results per WBN hydrothermal model simulation

2. WBN Unit 1 with new steam generators o 2006 3. WBN Unit 2 idle 4. SCCW sering Unit 1 5. Reseroir operating policy per the ROS FEIS 6. Historical hydrology and meteorology or 1976 through 2005 42Completion and Operation o Watts Bar Nuclear Plant Unit 2 Final Supplemental Enironmental Impact Statement Table 3-. stimated ydrothermal Conditions for Thermal ffluent From Outfall 113 With Unit 1 and Unit 2 Oerationourly Discharge (cfs) ourly ffluent Temerature (F) ourly Temerature at Donstream dge of iing one (F) ourly Temerature Rise at Donstream dge of iing one (F) ourly Temerature Rate-Of-Change at Donstream dge of iing one (Fhr) onth in ean a in ean a in ean a in ean a in ean aan 222 222 222 39.5 62.6 82.6 38.1 45.8 53.7 0.0 1.8 5.4 -3.6 0.0 2.7 Feb 222 222 222 40.7 64.7 82.7 37.8 45.6 55.3 0.3 1.8 5.4 -3.5 0.0 2.4 Mar 222 222 227 45.9 68.2 86.0 40.2 50.9 62.0 0.0 1.9 5.4 -3.5 0.0 2.5 Apr 226 256 277 57.3 72.6 90.2 48.9 58.6 68.4 0.0 2.3 5.4 -3.5 0.0 2.6 May 240 285 292 63.5 79.2 90.8 56.7 66.2 74.6 0.0 2.3 5.3 -3.0 0.0 1.8 un 257 291 292 68.5 83.7 94.1 62.7 73.0 79.8 0.0 1.7 5.2 -2.8 0.0 1.7 ul 275 291 294 71.5 86.0 97.2 70.2 77.8 84.5 0.0 1.4 4.3 -2.2 0.0 1.7 Aug 284 292 292 73.1 85.4 94.8 73.6 78.9 84.7 0.0 0.9 3.4 -2.0 0.0 1.5 Sep 291 292 292 65.5 81.6 92.5 69.6 76.8 83.0 0.0 0.7 2.9 -1.7 0.0 1.3 Oct 287 291 292 57.5 74.8 89.6 58.3 69.3 80.4 0.0 0.9 4.8 -2.7 0.0 2.0 No 226 258 288 52.6 69.6 85.7 47.9 59.8 70.9 0.0 1.3 5.4 -3.4 0.0 2.1 Dec 222 222 226 44.3 64.6 84.3 39.1 51.0 63.3 0.0 1.7 5.4 -3.5 0.0 2.1 Notes1. Results per WBN hydrothermal model simulation 2. WBN Unit 1 with new steam generators o 2006 3. WBN Unit 2 with original steam generators 4. SCCW sering Unit 2 5. Unit 2 cooling tower perormance the same as Unit 1 cooling tower perormance 6. Reseroir operating policy per the ROS FEIS 7. Historical hydrology and meteorology or 1976 through 2005 Chapter 3 Final Supplemental Enironmental Impact Statement 43 40 50 60 70 80 90 100Water Temerature (F) Outall 113 Eluent Temperature MRZ Bottom TemperatureNPDES Limit 92.3FERCW Limit 88.0F 199920002001200220032004by passing additional water through the SCCW bypass conduit or perhaps by remoing the SCCW system rom operation. For Outall 113 the NPDES permit also includes a limitation on the maimum temperature o the receiing stream bottom (mussel relocation zone). This temperature is not estimated by the WBN hydrothermal model. Howeer, historical data can be eamined to demonstrate that the Outall 113 eluent would not create a signiicant impact on rier bottom temperature. Measured temperatures or the Outall 113 eluent and rier bottom in the mussel relocation zone (MRZ) are shown in Figure 3-3. Data are shown or 1999, when the SCCW system irst began operation, through mid-2004. In this span, 2002 was among the warmest years since TVA began monitoring water temperature below Watts Bar Dam. As shown, een in a warm year, the maimum MRZ bottom temperature is only about 84F, well below the NPDES limit o 92.3F. It is important to note that the maimum allowable temperature o essential raw cooling water (ERCW) or continued operation o WBN Unit 1 currently is 85F, which is needed to guarantee a sae shutdown o the reactor in the eent o an emergency. Eorts currently are underway to increase this limit to 88F (TVA, 2004c, 2006b). The completion o Unit 2 is epected to include an ERCW limit o 88F. I the water temperature at the plant pumping station located 1.3 miles downstream o Outall 113 approaches 88F, the operation o WBN would be suspended, and thus the heat load rom the SCCW system would be dramatically reduced. Thereore, in terms o protecting bottom-dwelling species and ish passage, the impact to the rier rom Outall 113 would by necessity be reduced by WBN suspension o operations should the ambient bottom temperature eer reach 88F, still well below the MRZ temperature limit o 92.3F. Figure 3-3. easured Temeratures for Outfall 113 ffluent and ottom of ussel Relocation one Completion and Operation o Watts Bar Nuclear Plant Unit 2 Final Supplemental Enironmental Impact Statement 44mact on W Oeration As emphasized in Section 2.2.1, the purpose o the WBN SCCW is to enhance the perormance o the unit(s) that it seres. When TVA anticipates that one or more o the NPDES temperature limits are threatened or Outall 113, part o the SCCW inlow is dierted ia the bypass to the discharge conduit to reduce the temperature o the SCCW eluent (e.g., see Figure 2-2). I the temperature o the Outall 113 eluent cannot be suiciently reduced by this process, the SCCW system is remoed rom serice. In this manner, the impact o the SCCW system on WBN operation can be ealuated based on the length o time the SCCW system is placed in bypass and the length o time the SCCW system is remoed rom serice. Proided in Table 3-7 is a summary o these impacts or the two cases eamined herein. As noted, compared to current conditions with the SCCW system supporting Unit 1, combined operation o both units with the SCCW system supporting Unit 2 proides a slight reduction in the hours o reuired bypass operation, and no change in the number o hours the system must be remoed rom serice. For all practical purposes, gien modeling uncertainties, the results in Table 3-7 suggest that the completion and operation o Unit 2 as assumed herein would not create a substantie change in the operation o the SCCW system. The aerage annual generation or base-case conditions with Unit 1 obtained by the updated analyses was about 10,602,000 megawatt hours per year (MWh/year). For the combined operation o Unit 1 and Unit 2, the aerage annual generation obtained by the analyses was about 21,182,000 MWh/year, which is less than 0.01 percent less than twice the amount o generation or the base-case (Unit 1) conditions. This slight dierence is due to the minor change in perormance characteristics o the new steam generators or Unit 1 erses the original steam generators or Unit 2. Table 3-. Predicted SCCW mact on W Oeration CaseAerage ours er ear SCCW in yassAerage ours er ear SCCW Remoed From Serice Unit 1 only with SCCW sering Unit 1 (base case) 525 10 Unit 1 and Unit 2 with SCCW sering Unit 2 515 10 Lo Rier Flo It is important to note that the simulation period rom 1976 through 2005 contains our o the ie driest years eer recorded in East Tennessee, 1988, 1986, 2000, and 2005 (1 st , 3 rd , 4 th , and 5 th driest or period o record rom 1875 to present). Thus, the simulations summarized herein encompass perhaps near the most etreme conditions epected or the impact o WBN thermal eluent on the rier. For Outall 101, the etent o dry conditions is o little signiicance because the thermal eluent can be released rom Outall 101 only when the discharge rom Watts Bar Dam is at least 3500 cs. That is, een in the driest years, there will be at least 3500 cs o low in the rier or the assimilation o waste heat rom WBN.

The minimum daily aerage release in Table 3-2, 3300 cs, would allow a release o 3500 cs or at least 22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br /> in a single day. In practice, hydro releases rom Watts Bar Dam are usually made at leels aboe 3500 cs (e.g., 6000 cs). Under these conditions, the impact o a dry year is to reduce the number o hours per day that a low o 3500 cs can be proided or Outall 101, thereby orcing a greater olume o water to be stored in the WBN yard holding pond. This would increase the probability o an oerlow rom the yard holding pond and unwanted releases rom Outall 102. But as presented earlier, in the 30-year Chapter 3 Final Supplemental Enironmental Impact Statement 45simulations, there were no eents where it was ound necessary to proide releases rom the yard holding pond ia the emergency oerlow (i.e., including years such as 1988). For Outall 113, the impact o a low low year would be to increase the duration o eents where hourly releases rom the SCCW system are made in the absence o hourly releases rom Watts Bar Dam. In general, or such eents, i there is a threat to one or more o the hourly instream water temperature limits, the amount o heat released rom Outall 113 would be reduced by passing water through the SCCW bypass conduit or perhaps by remoing the SCCW system rom operation. Since the plant can be operated without the SCCW system in serice, such action poses no threat to the oerall integrity o WBN generation. Oerall, because WBN in closed mode uses such a small amount o low compared to the potential minimum daily aerage low in the rier, the plant thermal eluent under etreme low low conditions would not hae an aderse impact on water temperature in the Tennessee Rier. Oerall ear-Field ffects Oerall, with the recent changes that hae been made at the plant (e.g., SCCW system and new steam generators or Unit 1) and or the operation o the Tennessee Rier (i.e., ROS),

the updated hydrothermal analyses reconirm, as concluded in the 1972 FES, that the operation o two units at WBN will not hae a signiicant impact on near-ield hydrothermal conditions in the Tennessee Rier. Eects on water temperatures in the rier can be eectiely maintained within the current NPDES limits or all the plant discharge outalls without signiicant aderse eects on plant generation. Additionally, data rom recent ield studies (Appendi A) support the methods o modeling the dissipation o waste heat in the rier, and the patterns o miing rom the outalls proide ample space or ish passage and protection o bottom habitat.

Far-Field ffects By irtue o the act that the heated eluent is epected to hae an insigniicant impact on near-ield conditions in rier, ar-ield impacts on Chicamauga Reseroir also are epected to be insigniicant, or both the operation o one or two units at WBN. This is supported by the WBN discharge temperature limit ealuation conducted in 1993 (TVA 1993b), by water uality modeling perormed as part o the ROS FEIS (TVA 2004a), and by operating eperience since the startup o Unit 1 in 1996. Ongoing actiities under the TVA Reseroir Releases Improement Program and the TVA Vital Signs Monitoring Program would continue to proide close scrutiny o any potential ar-ield impacts rom the heated eluent rom WBN. The near-ield and ar-ield eects summarized aboe are based on the hydrothermal analyses described herein, and are udged to hae no signiicant impact on temperatures in Chicamauga Reseroir. That conclusion, howeer, is limited to the impacts o discharge to the Tennessee Rier rom Outalls 101, 102, and 113 associated with the presumed simultaneous operation o Watts Bar Units 1 and 2. The potential or cumulatie eects o the completion o WBN Unit 2 in conunction with other actors that could impact Tennessee Rier temperatures was also considered. In une 2004, ollowing completion o a detailed ROS, TVA implemented a new reseroir operating policy (TVA 2004a). This policy speciied changes in the operating guide cures at Chicamauga and other reseroirs. Potential changes in reseroir and water uality characteristics were studied in detail as a part o the ROS FEIS. These characteristics included turbine discharges and associated temperatures, residence times, thermal Completion and Operation o Watts Bar Nuclear Plant Unit 2 Final Supplemental Enironmental Impact Statement 46stratiication, both cold and warm water olumes, dissoled oygen, and algae. The impacts o the adoption o the ROS preerred operating policy or all o these characteristics, relatie to the preious operating policy, were determined to be insigniicant in Chicamauga Reseroir. There is no eidence to suggest that the adoption o the new operating policy has had or will hae any contribution to cumulatie eects in Chicamauga Reseroir. Whereas the ROS studies included only the operation o WBN Unit 1, the updated hydrothermal analyses summarized aboe show that the impact to the near-ield rier temperature o adding WBN Unit 2 would be insigniicant. As such, the startup o WBN Unit 2 would not change this conclusion regarding the potential or cumulatie eects. 3.1.2. S W A R W The reerenced earlier enironmental reiews analyzed potential impacts to surace water and water uality. A primary area o concern or surace water and water uality relates to the chemicals added to treat raw water. These earlier analyses continue to adeuately depict the inds o chemicals used at the plant and associated enironmental impacts. Proposed chemical addities and their respectie toicological data are presented to the state or approal prior to plant use in the acilitys Biocide and Corrosion Treatment Plan (B/CTP) reuired by the WBN Unit NPDES permit. To ensure the water uality criteria in the receiing stream is maintained, the state reiews the chemical usage reuest and ealuates the reasonable potential enironmental impacts o a speciic chemical discharge to determine the plant NPDES permit monitoring reuirements and discharge limits. Upon start o operation in May 1996, WBN was issued NPDES permit number TN0020168 (TVA 2005d). WBN is authorized to discharge process and non-process wastewater, cooling water and storm water runo rom Outall 101 and Outall 102 turbine building sump water, alum sludge supernate, reerse osmosis reect water, drum dewatering water, water puriication plant water, and storm water runo rom internal monitoring point (IMP) 103

metal cleaning wastewater, turbine building station sump water, diesel generator coolant, and storm water through IMP 107 treated sanitary wastewater through IMP 111 HVAC cooling water, storm water, and ire protection wastewater through Outall 112 and SCCW rom Outall 113 to the Tennessee Rier (reer to Figure 1-2, Unit 2 Site Plan and Appendi B, NPDES Flow Diagram). In addition to reisions to the B/CTP, the potential sources o chemicals and chemical uantities are reiewed and updated in connection with the application or NPDES Permit renewal. Compliance with the State Water uality criteria is also conirmed by routine semi-annual Whole Eluent Toicity (WET) testing at Outall 101, Outall 112, and Outall 113.TVA applied to renew the WBN permit in May 2006. To support the application or this permit reissuance, a detailed waldown o the plant was conducted to ensure that preiously identiied discharge point sources remain alid. A comprehensie sampling and analysis eent was also conducted to characterize waste water discharges rom the authorized discharge points. As a component o the NPDES Pe rmit, Part III, Section G, B/CTP, WBN is authorized to conduct treatments o intae or process waters with biocides, dispersants, suractants, corrosion inhibiting chemicals, and detoiication chemicals. To ensure protection o the receiing stream, water treatment processes are controlled to comply with State Water uality criteria and applicable NPDES permit conditions. WBN monitors eluent discharges and reports to the state the speciic chemicals inected along with the respectie actie ingredient discharged on the monthly Discharge Mo nitoring Report (DMR) and the Annual B/CTP Report. In addition, WBN perorms semi-annual WET testing at Outall 101, Outall 112, and Outall 113. Most o the chemicals used in t hese treatment pro grams are added at Chapter 3 Final Supplemental Enironmental Impact Statement 47 the IPS to ensure all raw water systems are protected. Seeral o these systems, the High Pressure Fire Protection and the ERCW systems in particular, are essential or the sae operation o the plant. While WBN has reuested modiications to the B/CTP oer the years, the approach and actie ingredients or the arious water treatment programs at WBN hae not undamentally changed. Proposed chemicals undergo an etensie toicological reiew and comparison with maimum instream wastewater concentrations to ensure water uality standards are met. The products used hae changed oer the years to slightly dierent ormulations o the same actie ingredients or constituents and the processes or reuencies o applying those products occasionally hae been changed. These B/CTP modiications continue to proide the same high leel o protection or auatic lie in the Tennessee Rier while increasing the leibility o plant euipment treatment options. Most recently, WBN submitted a B/CTP modiication reuest to the state in December 2006. TVA sought approal (1) to replace the dispersant PCL-401 with 73200, (2) or continuous use o oidizing biocides, and (3) to chlorinate using sodium hypochlorite. In addition, TVA reuested to add the non-oidizing biocide H150M to the B/CTP approal list. This reuest was approed by the state on April 30, 2007. The history o the use o chemicals or treatment during the same time period is shown in Table 3-8 and Table 3-9. Table 3-. istory of et Chemical Treatment of Ra Water at W 1-Present Chemicals Chemical Start ear nd ear System Clamtrol CT1300* 1996 1998ERCW/RCWSpectrus NX1104* 1998 PresentERCW/RCWCopperTrol CU-1 1996 1998ERCW/RCWBiotrol 88P 19961998ERCW/RCW*Vendor global chemical name change rom Clamtrol CT1300 to Spectrus NX1104 in 1998 **ERCW = Essential Raw Cooling Water RCW = Raw Cooling Water Table 3-. istory of alco Chemical Treatment of Ra Water at W 1-Present 1 Chemical Start ear nd ear System H-901G 1996 Present ERCW 3/RCW 4Coppertrol 1996 1999 ERCW/RCW PCL-10Z 1996 2002 ERCW/RCW PCL-60 1996 2002 ERCW/RCW PCL-401 1996 2006 ERCW/RCW Towerbrom 960 1999Present Cooling Tower H-130M 2 2002 2002 ERCW/RCW MSW-109 2003 Present ERCW/RCW H-130M 2004 2004 ERCW/RCW Coagulant Aid-35 2004 Present ERCW/RCW H150M 2005 Present ERCW/RCW 1 nown as Calgon Corporation, 1996-2001 Ondeo-Nalco, 2001-2003 Nalco, 2003-present 2 H-130M used with no detoiication in 2002 3ERCW = Essential Raw Cooling Water 4 RCW = Raw Cooling Water Completion and Operation o Watts Bar Nuclear Plant Unit 2 Final Supplemental Enironmental Impact Statement 48Ra Water Chemical Treatment Summary for the W Unit 1 CTP The ollowing summarizes chemical treatment programs currently in use or aailable or uture use at WBN Unit 1 and/or Unit 2 or corrosion, deposit, microbiological, and macroouling control in the raw water systems in accordance with the current B/CTP. Protection o the raw water cooling water pipe systems reuires oidizing biocide (chlorination) and non-oidizing biocide treatments to control macro inertebrates and microbiologically induced corrosion (MIC). WBN currently uses products rom Nalco, a maor industrial water treatment company. Raw Water Corrosion and Deposit Treatment WBN uses a zinc/orthophosphate-based program (MSW-109) or mild steel corrosion control o the ERCW and raw cooling water (RCW) systems. MSW-109 contains 12.6 percent zinc chloride and 36 percent orthophosphate. A seasonal eed program is used where MSW-109 is ed to the raw water system when rier water temperature is aboe 60 o F. The concentration o zinc and phosphorous is not to eceed 0.2 parts per million (ppm) at eluent discharges Outall 101 and Outall 113.WBN has the option to eed a dispersant (73200) to the ERCW and RCW systems that controls deposits o calcium phosphate, zinc, iron, manganese, and suspended solids.

Dispersant 73200 contains 36 percent high stress polymer (HSP). The actie HSP leel will not eceed 0.2 ppm at eluent discharges Outall 101 and Outall 113. WBN has the option to eed tolytriazole (Nalco 1336) on a continuous basis to small portions o the ERCW and RCW systems or copper corrosion control. Nalco 1336 contains 42.8 percent tolytriazole. Tolytriazole leel will not eceed 0.25 ppm at eluent discharges Outall 101 and Outall 113. Raw Water Microbiological/Macroouling TreatmentMicrobiological and macroouling reers to the undesirable accumulation o microorganisms, plants, algae, and auatic animals on submerged structures and piping systems. WBN currently inects on a continuous basis the oidizing biocide BCDMH (H-901G)or microbiological and macroouling control in the ERCW and RCW systems. Continuous oidation is necessary to ensure plant saety as TVA has recently obsered year-round eliger (mussel larae) inestations. H-901G puts 57 percent o its actie halogen ingredient into solution as bromine and chlorine. Chlorine, or Total Residual Oidant (TRO) is monitored ie (5) days per wee at Outall 101 and Outall 113 in accordance with permit reuirements to ensure discharge limits o 0.10 ppm or 0.158 mg/l daily maimum (respectiely) are met. As an alternatie to H-901G, WBN has the option to eed liuid bleach in the orm o sodium hypochlorite. Liuid bleach, containing 10.2 percent aailable chlorine, can also be ed on a continuous basis. Monitoring or chlorine leels in the eluent would remain the same as or H-901G. An option to eed a biodetergent (73551) to increase the eicacy o either H-901G or liuid bleach with microbiological control has been retained by WBN. The 73551 biodetergent consists o a 20 percent blend o non-ionic suractants and is ed or 30 minutes one to three times per wee to the ERCW and RCW systems. The actie suractant leel will not eceed 2.0 ppm to the eluent discharges Outall 101 and Outall 113.

Chapter 3 Final Supplemental Enironmental Impact Statement 49WBN de-chlorinates as reuired using sodium bisulite (Nalco 7408) to ensure the current discharge limit o 0.1 ppm TRO is not eceeded at eluent discharges Outall 101 or 0.158 mg/l daily maimum at Outall 113. Nalco 7408 consists o 45 percent sodium bisulite and is ed at a ratio o approimately 4 ppm product or eery 1.0 ppm o TRO. The sodium bisulite leel will not eceed 10 ppm at eluent discharges Outall 101 and Outall 113. When rier temperatures are greater than or eual to 60F, WBN terminates oidizing biocides treatment and perorms a periodic (minimum o 4 times per train per year) non-oidizing biocide treatment o the raw water systems. A train is the cluster o euipment which must be operational to perorm a certain unction. WBN uses a non-oidizing biocide (H150M, Clamtrol) to limit Asiatic clam and zebra mussel populations in the raw water system, the presence o which can signiicantly aect ERCW and RCW system perormance. H150M is a uaternary amine (uat) which consists o 25 percent dimethyl benzyl ammonium chloride and 25 percent dimethyl ethylbenzyl ammonium chloride. H150M is used to treat the A and B trains o ERCW and the RCW systems a minimum o our times per year. Spectrus NX1104 (uat), and Clamtrol are used or short-term (4-6 hour), low concentration applications or cross-tie (piping which oins the A train to the B train) treatments. In order to limit the actie H150M residual to no more than 0.05 ppm at eluent discharges Outall 101 and Outall 113, bentonite clay (Coagulant Aid-35) is ed into the Unit 1 cooling tower basin prior to eluent discharge to the rier ia NPDES outalls Outall 101 or Outall 113. Coagulant Aid-35 is ed at a ratio o 5 parts to 1 part H150M during each mollus treatment. Total clay leel is not to eceed 10 ppm at eluent discharges Outall 101 and Outall 113. The eectieness o detoiication is conirmed with twice daily sampling or the actie ingredient in the discharge during the treatment period.

Cooling Tower TreatmentsWBN currently adds Towerbrom 960 to the cooling tower basin on a periodic basis or microbiological control or CCW. Towerbrom 960 is an oidizing biocide, containing 57 percent aailable halogen, and generates bromine and chlorine solutions when dissoled in water. WBN also has the option to eed liuid bleach in place o Towerbrom 960. This treatment is perormed with the diusers and the SCCW system isolated (closed). To ensure the current discharge limit o 0.1 ppm TRO is not eceeded at eluent discharges Outall 101 or 0.158 mg/l daily maimum at Outall 113, the chemically treated water is not released to the rier until the discharge concentration o chlorine is below the NPDES permit limit. To enhance the eectieness o this program, WBN has reuested the option to eed Biodetergent 73551 with Towerbrom 960. WBN de-chlorinates as needed using sodium bisulite (Nalco 7408) to ensure the current discharge limit o 0.1 ppm TRO is not eceeded at eluent discharges Outall 101 or 0.158 mg/l daily maimum at Outall 113.

Nalco 7408 is ratio-ed at a rate o 4 ppm product or eery 1.0 ppm o chlorine. Additional Chemicals Used in W Processes In addition to the raw water addities or biocide and corrosion treatment chemicals discussed aboe, other chemical addities are used in plant processes. These chemicals may be ound in trace uantities at the arious NPDES discharge points (Outall 101, Outall 102, IMP 103, IMP 107, Outall 112) due to cooling tower blowdown (CTBD) to the Yard Holding Pond (YHP) or Outall 101, leaage, and system maintenance actiities (see Figure 2.1). Since the potential discharge o these chemicals is through the CTBD line, Completion and Operation o Watts Bar Nuclear Plant Unit 2 Final Supplemental Enironmental Impact Statement 50Outall 113 does not receie these discharges. The summary o potential chemicals discharged by NPDES outall number is shown in Table 3-10. Table 3-1. Potential Chemical Discharge to PDS Outfalls at W Outfall umberOutfall Descrition Chemical101 Diuser Discharge Ammonium Hydroide, Ammonium Chloride, Alpha Cellulose, Boric Acid, Sodium Tetraborate, Bromine, Chlorine, Copolymer Dispersant, Ethylene Glycol, Hydrazine, Laboratory Chemical Wastes, Lithium, Molybdate, Monoethanolamine, Molluscicide H150M, Oil and Grease, Phosphates, Phosphate Cleaning Agents, Paint Compounds, Sodium Hydroide, Suractant -

Dimethylamide and Alcohol, Tolyltriazole, Zinc Sulate, Zinc Acetate Dihydrate, LCS-60 102 YHP Oerlow Weir Alternate discharge path or Outall 101 103 LVWTP Ammonium Hydroide, Ammonium Chloride, Boric Acid, Sodium Tetraborate, Bromine, Chlorine, Copolymer Dispersant, Ethylene Glycol, Hydrazine, Laboratory Chemical Wastes, Molybdate, Monoethanolamine, Molluscicide

H150M, Oil and Grease, Phosphates, Phosphate Cleaning Agents, Paint Compounds, Sodium Hydroide, Suractant - Dimethylamide and Alcohol, Tolyltriazole, Zinc Sulate 107 LP and ULP Metals - Iron and Copper, Acids and Caustics, Ammonium Hydroide, Ammonium Chloride, Boric Acid, Sodium Tetraborate, Bromine, Chlorine, Copolymer Dispersant,Hydrazine, Laboratory Chemical Wastes, Molybdate, Monoethanolamine, Molluscicide H150M, Oil and Grease, Phosphates, Phosphate Cleaning Agents, Sodium, Sodium Hydroide, Suractant - Dimethylamide and Alcohol, Tolyltriazole, Zinc Sulate 111 Sewage Treatment Plant Chlorine, Organic Matter, Laboratory Chemical Wastes, Paint Compounds 112 Runo Holding Pond Chlorine, Organic Matter, Paint Compounds, Potable Water (Cooling Tower at Training Center), High Pressure Fire Protection lushes, Superior SWS 4550Primary System Chemical AdditionsThe Primary Systems are generally located in the radiologically controlled areas o the plant and support the Reactor Cooling System (RCS). These systems include the Component Cooling Water System (CCS) and the Ice Condenser. At plant startup lithium hydroide is added to the RCS ia components in the Auiliary Building to establish the initial pH and corrosion control. Ater Chapter 3 Final Supplemental Enironmental Impact Statement 51the reactor becomes critical, lithium is a byproduct o a neutron-boron reaction and no urther lithium hydroide additions are reuired. A boric acid concentration is established in the RCS at startup to control neutron lu and is limited based upon core design. This concentration is reduced or approimately one month ater restart rom a reueling outage. For approimately the net month the concentration is increased and then oer the course o the operating cycle the concentration steadily decreases. Hydrogen peroide is added during a reueling outage to enhance primary system cleanup to reduce radiation eposure to maintenance personnel and ensure water clarity. Hydrazine is added stoichiometrically prior to heat-up rom a reueling outage to scaenge oygen and minimize system corrosion. The RCS is a closed system, thereore any leaage or letdown rom the RCS system would be processed through the liuid radiological waste system. WBN receied state approal in October 2006 to add low concentrations o Zinc Acetate Dihydrate to the RCS. Industry eperience has shown zinc additions yield a 20 to 30 percent reduction in plant dose rates and reduce primary water stress corrosion cracing in plant materials. Zinc would also reduce the corrosion rate and release o corrosion products to the coolant rom the metal suraces o replacement or new steam generators. WBN initiated inection at 20 grams per day ia components in the Auiliary Building and maintained this eed rate until a zinc residual was obsered in RCS samples. As the residual built in and the crud layer absorption o zinc slowed, WBN lowered the eed rate to maintain 5 ppb zinc in the RCS. Since the RCS is a closed system, any leaage or letdown rom the RCS system would be processed through the liuid radiological waste system. A history o Zinc Acetate Dihydrate

and other chemical treatment are shown in Table 3-11. Table 3-11. istory of Other Chemical Treatment of Ra Water at W 2-Present Chemical Start ear nd ear System Zinc Acetate Dihydrate2006 Present RCS 1 Superior SWS 4550 2006 Present Training Center Cooling Tower 1 RCS = Reactor Coolant Systemodium molybdate, tolyltriazole, sodium hydroide are added to this system in the Auiliary Building to control pH and corrosion. Leaage rom this system would be processed through the radwaste system while complete system draining is routed to the Turbine Building Station Sump (TBSS).

The TBSS is normally routed to the discharge to the Low Volume Waste Treatment Pond (LVWTP), but can be routed to the Lined Pond (LP), the Unlined Pond (ULP), or the YHP. . Sodium tetraborate is used in the Ice Condenser or emergency boration. The Ice Condenser is located in the Reactor Building and the components to mi and initially reeze the tetraborate solution are located in the Additional Euipment Building. Ice melt bypasses the radwaste demineralizer beds, is routed to a radwaste discharge tan, and is discharged through the radwaste system. Ethylene glycol is used in the ice condenser chiller pacages. Leaage with concentrations less than10 percent is discharged to the ULP or degradation, while greater than or eual to 10 percent is collected in drums and shipped to a endor to be recycled.

Completion and Operation o Watts Bar Nuclear Plant Unit 2 Final Supplemental Enironmental Impact Statement 52 Secondary System Chemical AdditionsThe main Secondary Systems are the Condensate System, the Main Feedwater System and the Main Steam System. The purpose o the Secondary Systems is to heat and pressurize cooler water to produce eed water or the steam generators. The Main Steam System then routes steam rom the steam generators to the plant turbines or power generation. The Condensate System receies ehausted steam rom the turbine discharge

to repeat the cycle. Hydrazine, ammonia, ammonia chloride, boric acid, and monoethanolamine (ETA) are inected into the Condensate System at the turbine building or secondary chemistry control. Hydrazine unctions as a dissoled oygen scaenger while ammonia and ETA are added or pH control and corrosion control. Ammonia chloride is inected as necessary or molar ratio control to aid in reduction o stress corrosion cracing in the steam generators. Boric acid is also inected at the turbine building or reduction or preention o stress corrosion cracing in the steam generators. The reduction o stress corrosion cracing assists in the maintenance o steam generator integrity thereby realizing their design liespan. Up to 300 pounds o modiied alpha cellulose may be added to the condenser intae channel to temporarily plug pinhole tube leas in the condenser.

Other Plant SystemsChemicals are also added to other plant systems and include Chilled Water Systems, Turbine Building Heating System, Auiliary Boilers, and Diesel acet Cooling Systems. Hydrazine and ammonia are added to the Chilled Water Systems, Turbine Building Heating System, and Auiliary Boilers or pH and corrosion control LCS-60 is added to the diesel acet cooling water or corrosion control and consists o sodium nitrite, sodium tetraborate and tolytriazole. These chemicals are incidental discharges that are are controlled ia BMPs. Discharges occur ia leaage or maintenance actiities and are discharged to the LP, ULP, LVWTP, or

YHP.Superior SWS 4550 is added to the Training Center Cooling Tower Water System to neutralize the chemical deposits in the Training Center Cooling Tower and inhibit corrosion. Any blowdown discharge is routed to the Runo Holding Pond (RHP) and Outall 112. nironmental Consequences of Chemical Additions to Ra Water Under the preerred alternatie, TVA would complete the construction o WBN Unit 2 and the plant would operate at its ull capacity as originally designed. Prior to construction actiity, WBN would deelop an erosion and sedimentation control plan as part o an application or a General NPDES Permit or Storm Water Discharges Associated with Construction Actiity although it is epected that most o the construction wor would occur inside constructed buildings, and all o the wor is epected to occur within the eisting plant site ootprint. Operation o Unit 2 along with Unit 1 would result in an increase o raw water intae usage at the IPS by an estimated 33 percent compared to sole operation o Unit 1, with a corresponding increase o ERCW and RCW raw water chemical addities by an estimated 33 percent. This increase is within original design basis or operation o Units 1 and 2. Since an additional eisting cooling tower would be placed in serice, Towerbrom 960 treatment or CCW treatment would increase by an estimated 100 percent.

Chapter 3 Final Supplemental Enironmental Impact Statement 53The current NPDES permit contains proisions reuiring authorization o the B/CTP and the use o the water treatment chemicals described aboe are epected to continue in use i and when WBN Unit 2 starts up. TVA would use the same protocols or Unit 2 as used with Unit 1 to show permit compliance with the treatment plans using mass balance calculations where possible. In addition, detoiication o non-oidizing biocides would be conirmed with twice-daily sampling or the actie ingredient in the eluent during the treatment period. The state retains the authority to reuire WBN to conduct additional monitoring to ensure that Unit 2 operation does not hae an aderse aect on NPDES eluent limitations or other permit conditions. In the eent the state determines that additional monitoring should be conducted, the results would need to be ealuated and submitted to the state per the conditions set orth. Potential changes in plant discharges are not epected to be signiicant as compliance with applicable regulatory saeguards and internal assessments would ensure that resulting eects to water uality are insigniicant. 3.1.3. The 1995 FSER updated the groundwater inormation in the 1972 FES, and the descriptie inormation about groundwater systems in the icinity o WBN proided in that update is still accurate. In August 2002, tritium was detected in one o the on-site enironmental monitoring locations at leels that were ust at the detectable leel. At that time, TVA notiied the NRC and State o Tennessee enironmental and radiological representaties.To address this issue, in December 2002, TVA installed our new enironmental monitoring locations on the plant site as a modiication to the Radiological Enironmental Monitoring Program. Since that time TVA has been closely monitoring in-ground tritium and reporting these results in the WBN Annual Radiological Enironmental Operating Reports to NRC and the state o Tennessee. Samples taen anuary 2003 through December 2004 indicated the presence o low leels o tritium in three o the our monitoring locations, which are maintained or enironmental monitoring purposes only. The sources o this tritium were leaage rom an underground radioactie eluent piping and leaage rom a bellows or the Unit 2 uel transer tube. In order to stop the tritium ingress into the groundwater, the radioactie eluent piping was replaced with a new 4-inch pipe. In addition, the Unit 2 uel transer tube was sealed, and the uel transer canal was coated. These actiities were completed by Noember 2005. Results rom two o the new indiidual sample locations, taen in February 2005 and une 2005, were greater than the NRC 30-day reporting leel o 30,000 picocuries per liter (pCi/L). Further inspections reealed no leaage in underground radioactie eluent piping.

TVAs inestigation determined that the source o the increased tritium leels was a result o the preious eluent piping lea, which had been repaired. The highest amount o tritium detected was approimately 550,000 pCi/L. Some residual tritium will remain in the groundwater until the tritium either decays or is diluted. Eentually, this groundwater will migrate into the rier where these degraded tritium leels will be een urther reduced and thereore pose no public health hazard. TVA continues to monitor wells monthly to eriy past repairs and detect any new sources o contaminated groundwater. Routine reports are made to the NRC and the state. Completion o WBN Unit 2 would not impact groundwater resources in the icinity o WBN.

Completion and Operation o Watts Bar Nuclear Plant Unit 2 Final Supplemental Enironmental Impact Statement 543.2. Aquatic cology The characteristics o the WBN sites auatic enironment and biota were described in the 1972 FES (TVA 1972) with updated inormation described in the NRC 1995 FES (NRC 1995a) and the TVA 1998 FEA or the WBN SCCW Proect (TVA 1998a). This inormation was based on site-speciic data combined with general nowledge o Tennessee Rier tailwater habitats and associated auatic biota. Etensie supplemental inormation speciic to WBN is aailable rom reports detailing results o the TVA Vital Signs Monitoring Program (TVA, unpublished data). These cited reports and data were eamined and determined to continue to represent current enironmental conditions adeuately in the Watts Bar Dam tailwaters and upper Chicamauga Reseroir. They were used or the present FSEIS as a basis or a reiew o the auatic ecology in the icinity o the WBN site. PlantonRecent studies indicate that the maority o plantonic organisms (including ish eggs, laral ish, microinertebrates, algae, etc.) in the icinity o WBN originate in the Watts Bar Reseroir and pass through the turbines at Watts Bar Dam. Planton density aries greatly rom day to day. Sampling sureys (1973-1985) indicate that planton populations decreased rapidly as distance rom Watts Bar Dam increased due to the swit-lowing, rierine nature o the upper portions o Chicamauga Reseroir. As water enters the reseroir pool o Chicamauga Reseroir (25-30 miles downstream o WBN), elocities decrease and planton densities gradually increase to leels comparable to those in the Watts Bar Dam orebay (TVA 1986). Though there are no data on phytoplanton densities in the icinity o the WBN site, comparisons between preoperational (1976-1985) and operational (1996-1997) densities o ish eggs and laral ish show similar patterns (Appendi C, Table C-1) (TVA 1998d). An entrainment study conducted during the spring and summer o 1975 estimated the aerage loss o ish larae in the icinity o WBF as a result o water diersion to the plant was 0.24 percent o the total population (TVA 1976b). In the TVA FEA or the SSCW, TVA ealuated one-unit operation and concluded that the proposed proect would result in loss o ish eggs and larae through entrainment at approimately the same rate as preiously studied in 1976 (TVA 1998a). Similar results were reported in the 2001 ish monitoring program or the SCCW and it was concluded that no signiicant impact to ichthyoplanton populations rom WBN SCCW operation would occur (Bater et al. 2001). These entrainment rates indicate the operation o both WBN Unit 1 and Unit 2 would hae little or no eect on laral ish and egg populations in Chicamauga Reseroir because the WBN condenser cooling water system (CCW) is

commensurate with a closed cycle cooling system. nasie and oninasie Aquatic Plants Auatic plants present in Chicamauga Reseroir include the inasie species Eurasian water miloil (), spinylea naiad (), and the natie southern naiad () (TVA 1994a). Ecessie auatic plant coerage can cause reseroiruse conlicts in areas around industrial water intaes, public access and recreation sites, and laeshore deelopments. These eects hae not been seen in the icinity o WBN because the WBN site is located in the rierine tailwater area o the reseroir downstream o Watts Bar Dam. Auatic plants hae diiculty establishing dense growths in this area een during years o pea coerage due to current elocity. As a result, auatic plant densities in the reseroir near WBN hae not reached nuisance leels, and no control measures hae been taen in the icinity o the plant. Pea auatic plant Chapter 3 Final Supplemental Enironmental Impact Statement 55coerage in Chicamauga Reseroir occurs in shallow, oerban laelie habitat ar downstream o WBN. Combined operation o WBN Units 1 and 2 would not hae eects on the occurrence o inasie or noninasie auatic plants. Aquatic Communities Beore 1978, isheries biologists thought the tailwaters o Watts Bar Dam contained aorable spawning habitat or seeral species including sauger (),smallmouth bass (), white bass () and possibly yellow perch (). Howeer, the ealuation o inormation in the 1978 NRC FES discounted this theory. Since 1978, additional studies hae conirmed that the reach between the Watts Bar Dam and the WBN site is a staging area, not an area o signiicant spawning actiity or these species (NRC 1995a). TVA began a program to systematically monitor the ecological conditions o its reseroirs in 1990, though no samples were taen on the Watts Bar or Chicamauga Reseroirs until 1993. Preiously, reseroir studies had been conined to assessments to meet speciic needs as they arose. Reseroir (and stream) monitoring programs were combined with TVAs ish tissue and bacteriological studies to orm an integrated Vital Signs Monitoring Program. Part o the monitoring consisted o the reseroir ish assemblage inde (RFAI), a method o assessing the uality o the ish community. Since the institution o the Vital Signs Monitoring Program, the uality o the ish community in the icinity o the WBN site has remained relatiely constant with an aerage rating o good (see Appendi C, Tables C-2 and C-3). Another aspect o the Vital Signs Monitoring Program is the benthic inde, which assesses the uality o benthic communities in the reseroirs (including upstream inlow areas such as that around WBN). The tailwaters o Watts Bar Dam support a ariety o benthic organisms including seeral large mussel beds. One o these beds has been documented along the right-descending shoreline immediately downstream rom the mouth o Yellow Cree. To protect these beds, the state has established a mussel sanctuary etending 10 miles rom TRM 520 to TRM 529.9. Since the institution o the Vital Signs Monitoring Program, the uality o the benthic community in the icinity o the WBN site has remained relatiely constant. The rierine tailwater reach downstream o Watts Bar Dam and WBN rated good in 2001 and the rating has increased to ecellent in 2003-2005 (Appendi C, Tables C-4 and C-5). Under the proposed action, no construction actiities would occur within 500 eet o the reseroir, and all construction actiities would be subect to appropriate BMPs to ensure that there are no impacts to surace water uality. NPDES discharge limits as outlined in the 1995 NRC FES and in this document would not be reised. No discharges eceeding current NPDES limits would occur during operation o WBN Units 1 and 2. The amount o cooling water reuired or operation o both WBN Unit 1 and WBN Unit 2 would result in increases in cooling water intae and discharge olumes, but thermal discharge rates would remain below maimum allowed leels outlined in the 1978 NRC FES (see section 3.1). Because all construction wor would be conducted using appropriate BMPs, and no additional discharge-related impacts would occur, there would be no eect on auatic animals or their habitats in the icinity o WBN. Because intae lows would not be increased aboe leels outlined in the 1978 NRC FES, ish entrainment rates would not eceed maimum leels preiously ealuated in that FES or operation o both WBN Units 1

and 2.

Completion and Operation o Watts Bar Nuclear Plant Unit 2 Final Supplemental Enironmental Impact Statement 56nasie and otic Aquatic Animals At the time the 1972 FES was issued, the Asiatic clam () was the only benthic nuisance species nown to occur in Chicamauga Reseroir. Subseuently, the zebra mussel () has become established in the Watts Bar Dam tailwater area. The plantonic larae o zebra mussels can be drawn into raw-water piping systems, and attach to pipe suraces. Multiple layers o adult zebra mussels can accumulate resulting in partial to total blocage o pipes and grates. This can cause damage to pipes and acilities reuiring acility outage time to remoe the blocage.

Currently, WBN has implemented the use o Clamtrol (WBN uses H150M), a nonoidizing molluscide, within the acility to inhibit bioouling by Asiatic clams and zebra mussels. Howeer, this control method is restricted to the acility itsel and concentrations o molluscide released into the reseroir are too low to hae any eect on natie mussel beds (NRC 1995a). 3.3. Terrestrial cology 3.3.1. The terrestrial plant communities were assessed during the initial enironmental reiew or the construction o WBN Units 1 and 2 (TVA 1972). Maor plant community types are described and statistical alues were calculated rom data obtained rom egetation plot analyses rom each terrestrial community. In addition, importance alues along with reuency, density, basal area and olume or all tree species occurring on the Watts Bar reseration are presented. In the 1976 Enironmental Inormation Report or WBN Units 1 and 2, the maor community types are listed as oa-hicory orest, oa-gum orest, yellow pine-hardwood orest, Virginia pine orest, sumac shrub community, early old-ield community, horseweed-type community, escue meadow community, and a marsh community (TVA 1976a). O the 967 acres acres identiied or building WBN, 210 wooded acres were to remain undisturbed (approimately 80 percent o the eisting woodlands). More than 70 percent o the plant area was already disturbed in the orm o cultiated or old ields.The terrestrial plant communities o the WBN site hae changed ery little oer the past 34 years. The maority o the proect area (oer 70 percent) is composed o herbaceous egetation types ound in old ields, grael paring areas, roadside rights-o-way and arious other disturbed sites. Approimately 30 percent o the site is still orested with the ollowing orested egetation classes deciduous orest and eergreen-deciduous orest. The deciduous orest can be characterized as two separate community types, oa-hicory orest and bottomland hardwood orest. Inasie species including apanese stilt grass, apanese honeysucle, multilora rose, and Russian olie occur on WBN Reseration. Some disturbance o eisting plant communities may occur i construction o WBN Unit 2 recommences although most construction actiities are epected to occur in already constructed buildings or within the preiously disturbed plant ootprint. Because no uncommon terrestrial communities or otherwise unusual egetation occurs on the lands to be disturbed under the proposed action, impacts to the terrestrial ecology o the region are epected to be insigniicant as a result o the proposed actions. No new inestations o eotic inasie plant species are epected as a result o the Action Alternatie.

Chapter 3 Final Supplemental Enironmental Impact Statement 573.3.2. W The terrestrial ecology at the WBN acility has changed little rom those described in earlier enironmental reiews. Habitats surrounding the acilities consist o mowed grass, ields o short egetation, and ditches that are intermittently wet. The proect site, which is highly deeloped, includes paring areas and ball ields in addition to these habitats. Wildlie using these areas, primarily adacent to the disturbed area ootprint, include locally abundant species that are tolerant o human actiity and highly modiied habitats. Species such as eastern meadowlar, American goldinch, eastern bluebird, and song sparrow were obsered at or adacent to the proposed proect site. Spotted sandpiper and illdeer were obsered in or near the settling ponds at the acility most o these ponds are lined with riprap and proide poor habitat or shorebirds. Howeer, species including double-crested cormorants, mallards, Canada geese, blac ultures, roc pigeons, and white-tailed deer were noted near the ponds. An osprey nest was also obsered on a nearby structure. Due to the oerall lac o wildlie habitat at the proect site and the limited amount o additional habitat disturbance anticipated, the proposed proect is not epected to result in aderse impacts to terrestrial animal resources within the disturbed area ootprint (Figure 1-2) or in the adacent areas. Wildlie in the proect area is locally abundant and no rare or uncommon habitats eist at the site. 3.. Threatened and ndangered Secies As discussed in Sections 3.2 and 3.3, most o the auatic and site disturbance reuired or completion o WBN Unit 2 has already occurred. The ollowing sections proide an update o the ederally listed and state-listed species ound in the icinity o the WBN site and the potential or impacts rom the proposed action. 3.4.1. A A Four mussel species ederally listed as endangered, dromedary pearlymussel, pin mucet, rough pigtoe, and anshell, are nown to occur in mussel beds in the icinity o WBN (Appendi C, Table C-6). To protect these beds, the state has established a mussel sanctuary etending 10 miles rom TRM 520 to TRM 529.9 (Appendi C, Table C-7) (TVA 1998b). Figure 3-4 shows the location o the mussel sanctuary relatie to WBN. The snail darter, ederally listed as threatened, is also nown to occur occasionally in this reach o the Tennessee Rier. The maority o the snail darter population in the area is conined to Sewee Cree, a tributary to the Tennessee Rier, which enters the rier at TRM 524.6.The larae o snail darters are pelagic and can drit substantial distances (miles) during early lie stages. Spawning o snail darters has not been documented in the main stem o the Tennessee Rier downstream o Watts Bar Dam, and no snail darter larae hae been

collected during entrainment sampling. Two mussel species considered sensitie by the State o Tennessee pyramid pigtoe and Tennessee clubshell, and one state-listed threatened ish species blue sucer, are also nown rom this reach o the Tennessee Rier (Appendi C, Table C-6).

Completion and Operation o Watts Bar Nuclear Plant Unit 2 Final Supplemental Enironmental Impact Statement 58Figure 3-. Location of ussel Sanctuary in Chicamauga Reseroir elo Watts ar Dam Chapter 3 Final Supplemental Enironmental Impact Statement 59Under the proposed action, wor would be conducted on WBN Unit 2 in order to bring it to ull operational capacity. No construction actiities would occur within 500 eet o the reseroir, and all construction actiities would be subect to appropriate BMPs to ensure that there are no impacts to surace water uality. NPDES discharge limits as outlined in the 1995 NRC FES would not be reised. No discharges eceeding current NPDES limits would occur during operation o WBN Units 1 and 2. The amount o cooling water reuired or operation o both WBN Unit 1 and WBN Unit 2 would result in increases in cooling water intae and discharge olumes up to the original two-unit design. Thermal discharge rates would remain below maimum allowed leels outlined in the 1978 NRC FES. The steam generator blowdown (SGDB) contains low leels o ammonia, which is inected in the turbine building to control corrosion. The highest concentration o ammonia measured in the SGDB during the past our years was 4.2 mg/l (or 4.2 ppm). The maimum SGBD discharge or Units 1 and 2 would be 524 gallons per minute (gpm) through the diusers at outall 101 and would reuire 3500 cs o minimum rierlow. Based on the hydrothermal analysis in Section 3.1 and preious diuser studies (Haderioua, et.al. 2003), in the worst case conditions, ammonia concentrations would be ully mied prior to reaching the stream bottom in the 240-eet wide by 240-eet-long assigned miing zone. SGDB is dierted to the yard holding pond with cooling tower blowdown when the minimum rier low o 3500 cs is not aailable, unless it has already been dierted to the condensate system. When the minimum rierlow o 3500 cs is aailable, the YHP discharges through outall 101. The YHP has an emergency oerlow that discharges through outall 102. In general, the operation o Watts Bar Dam and the WBN blowdown system are ery careully coordinated so that there are no unepected oerlows rom the yard holding pond. (see Section 2.2.2). No eents with oerlow rom the YHP occurred

during the hydrothermal analysis described in Section 3.1, thereore under operating conditions, releases rom Outall 102 are not epected. Thereore, there would be no eect to any ederally listed as endangered or threatened mussels. Because all construction wor would be conducted using appropriate BMPs, and no additional discharge-related impacts would occur, there would be no eect on state-listed or ederally listed auatic animals or their habitats in the icinity o WBN. Because intae lows would not be increased aboe leels outlined in the 1978 NRC FES, ish entrainment rates would not eceed maimum leels preiously ealuated in that FES or operation o both WBN Units 1 and 2. Because snail darter larae hae not been encountered in entrainment sampling at WBN, there is no potential or snail darter larae to be entrained at the cooling water intae or WBN een under the increased withdrawal rates reuired to support operation o both WBN Units 1

and 2.3.4.2. Historically, one plant species, spider lily, (now ), was identiied as being a proposed rare and endangered species by the USFWS in the original FES (TVA 1972). This designation was made prior to the Endangered Species Act o 1973, and the species was not listed as threatened or endangered under this act nor is it gien any special status within the state o Tennessee. In addition, ield sureys in 1994 ailed to ind any populations o spider lilies in the icinity o WBN (TVA 1995a 1995b). The FEA or the WBN Unit 1 Replacement o Steam Generators documents si Tennessee state-listed plant species nown rom within 5 miles o WBN, and no sensitie plant species or habitat to support these species were ound during ield reiews (TVA 2005a).

Completion and Operation o Watts Bar Nuclear Plant Unit 2 Final Supplemental Enironmental Impact Statement 60The si Tennessee state-listed plant species nown rom within 5 miles o WBN are shown in Table 3-12. There are no nown ederally listed as threatened or endangered plant species within Rhea County, Tennessee. No designated critical habitat or plant species are nown rom within 5 miles o WBN or Rhea County. Table 3-12. State-Listed Plant Secies Reorted From Within 5 iles of the Proosed Proect in Rhea County, Tennessee Common ame Scientific ame StateStatusRan Appalachian bugbane THR (S3) Heay sedge SPCO (S1) Northern bush honeysucle THR (S2) Prairie goldenrod END (S1S2) Slender blazing star THR (S2) Spreading alse ogloe THR (S3) Status abbreiations END=Endangered, SPCO=Species o special concern, THR = Threatened, S1 = critically imperiled with 5 or ewer occurrences S2 = imperiled with 6 to 20 occurrences, S3 = Rare or uncommon with 21 to 100 occurrences No occurrences o state-listed or ederally listed plant species are nown on or immediately adacent to the area to be disturbed under the proposed Action Alternatie. Thereore, no impacts to sensitie plant species are epected. 3.4.3. W Earlier reiews indicated that ederally listed as threatened or endangered gray bats () and bald eagles () were reported within 5 miles o the proect. Small numbers (less than 500) o gray bats continue to roost in a cae approimately

3.3 miles

rom the proect. Bald eagles nest on Chicamauga and Watts Bar Reseroirs approimately 1.8 and 4.7 miles, respectiely, rom the proect site. Gray bats and bald eagles orage oer the Tennessee Rier in the icinity.Seeral heron colonies hae been reported rom the icinity since the late 1980s. Many o these colonies were destroyed during recent pine beetle inestations. The closest actie colony is located 4 miles north o WBN. Hellbenders (), listed as in need o management by the State o Tennessee, hae been reported rom the upper reaches o Sewee Cree, approimately 2.5 miles rom the proect site. The species may continue to inhabit streams in the icinity. Completion o WBN Unit 2 is not epected to result in impacts to any ederally listed or statelisted as threatened or endangered species o terrestrial animals or their habitats. No suitable habitat or gray bats or bald eagles eists on or adacent to the proect site. Construction and operation o WBN Unit 2 would not result in impacts to bald eagles and gray bats in the region.

Chapter 3 Final Supplemental Enironmental Impact Statement 61 3.5. Wetlands Wetland communities were assessed during the initial enironmental reiew or the construction o WBN Units 1 and 2 (TVA 1972), and were also assessed or the construction o arious other operational components o the site (TVA 1995a TVA 1995b TVA 2005a). Forested wetlands are present on the southwest portion o the site, and emergent wetlands hae deeloped within ash disposal sites and in containment ponds located in the southwest portion o the site.

Scattered areas o ringe emergent wetlands are present along the shoreline o the WBN site, and there are small areas o orested, scrub-shrub, emergent wetlands associated with streams on the plant site. A ield surey or wetlands conducted on October 30, 2006, indicated a orested wetland is present adacent to the proect ootprint. This wetland is associated with an unnamed stream between the road and the rail line ust outside o the northeast corner o the proect ootprint.

The area is approimately 1 acre in size dominant egetation includes tag alder, sycamore, and blac willow. The remainder o the site is composed o upland plant communities, grael paring areas, and deeloped areas. Since there are no plans to disturb the aboe-mentioned orested wetland, no impacts to wetlands would occur as the result o construction actiities related to the completion o WBN Unit 2. I proect plans are modiied and impacts to this wetland are unaoidable, mitigation may be reuired as a condition o state and/or ederal wetland protection regulations (Section 404, Clean Water Act, and Auatic Resources Alterations Permit). Mitigation may consist o o-site mitigation in the orm o wetland creation or purchase o credits in a wetland mitigation ban. Oerall impacts to wetlands in the proect area would be insigniicant due to the small size and limited ecological unction o the wetland. 3.. atural Areas Changes (since the 1978 NRC FES NRC 1995b and TVA 1998a) in natural areas and the enironmental impact on natural areas within 3 miles o WBN are assessed below or the purpose o updating preious documentation to current conditions. Three o ie natural areas currently listed in the Natural Heritage database and within 3 miles o WBN were reiewed in preious documents. These areas are Yellow Cree unit o the Chicamauga State Wildlie Management Area (WMA), the Chicamauga Reseroir State Mussel Sanctuary, and the Chicamauga Shoreline TVA Habitat Protection Area (HPA). TVA 1998a ound no direct or indirect eects to Yellow Cree WMA or the TVA HPA. NRC 1995b, which reiewed the 1978 NRC FES, noted no signiicant changes in, and thereore no signiicant impacts to, the auatic enironment in the icinity o WBN. Additionally, no impacts to the mussel sanctuary (an area designated by the State o Tennessee to be a biological presere or mussel species) are anticipated rom the proposed action (Stephanie Chance, TVA, personal communication, Noember 14, 2006). No signiicant changes in area or management obecties o the WMA and TVA HPA hae occurred since they were last reiewed, and thereore, no direct or indirect impacts to these areas are anticipated rom the proposed action.Two additional natural areas within 3 miles o WBN include Meigs County Par, a 240-acre public recreation area approimately 1.5 miles north o the site, and Yuchi Wildlie Reuge at Smith Bend, a 2600-acre haen or migratory waterowl and shorebirds. This reuge, managed by the Tennessee Wildlie Resources Agency, is approimately 2.2 miles south o the site. The Completion and Operation o Watts Bar Nuclear Plant Unit 2 Final Supplemental Enironmental Impact Statement 62distance rom the site to these two areas is suicient such that no direct or indirect impacts are anticipated. 3.. Cultural Resources As part o the etensie history o enironmental reiew o constructing and operating WBN, TVA has considered the potential impact on historic and archaeological resources associated with each undertaing. It was determined during the initial enironmental reiew that two archaeological sites (40RH6 and 40RH7) would be adersely aected by construction o the plant. Based on this inding, TVA proceeded with data recoery o these sites (Calabrese 1976 Schroedl 1978). One historic cemetery (Leuty Cemetery) was located on the property prior to plant construction. Two graes were remoed in 1974 and placed in Ewing Cemetery. Subseuent enironmental reiews conducted resulted in a no-eect inding or archaeological resources. In the 1998 reiew o the WBN SCCW proect (TVA 1998a), TVA determined that WBF was eligible or listing on the National Register o Historic Places (NRHP). Howeer, it was determined that this property would not be adersely aected. Four archaeological sites are located within the WBN property (40RH6, 40RH7, 40RH8, and 40RH64). The irst three sites were recorded as part o the Watts Bar Basin surey in 1936. The latter was recorded later during a post-inundation Chicamauga Reseroir shoreline surey.

While a portion o these sites was ecaated, the sites remain eligible or listing on the NRHP with a potential or signiicant archaeological deposits and eatures to be present. Sites 40RH8 and 40RH64 are both considered potentially eligible or listing on the NRHP. While a reconnaissance surey was conducted on the plant property prior to its construction, archaeological surey techniues hae signiicantly improed since that time. Based on what we already now, undisturbed areas outside the current proects area o potential eect (APE) hae a high potential or archaeological resources to be present. Any uture ground-disturbing actiity in these areas would hae to be reiewed. A maority o the APE or this proect has been etensiely disturbed. Completing WBN Unit 2 would result in some additional ground-disturbing actiities but largely would be restricted to the eisting disturbed portion o the plant property. A ield isit conducted conirmed the prior disturbance in these areas. Proect plans submitted include a larger ootprint surrounding the plant that has been identiied as the disturbance area. A portion o this ootprint east o the cooling towers (the aoidance area shown on Figure 3-5) includes parts o archaeological site 40RH6 and it is unnown i this site contains signiicant archaeological deposits. Although this site is within the area identiied as potentially to be disturbed, current plans actually would not disturb it. I those plans change and this area would be disturbed, an archaeological surey o the aected area would be conducted to determine the signiicance o the site and i determined to be archaeologically signiicant, appropriate measures would be taen to aoid adersely impacting identiied resources. This would include coordination with the SHPO.

Chapter 3 Final Supplemental Enironmental Impact Statement 63Figure 3-5. Archaeological Aoidance Area Within the Area of Potential ffect Completion and Operation o Watts Bar Nuclear Plant Unit 2 Final Supplemental Enironmental Impact Statement 64As planned, archaeological resources within the APE at WBN should not be adersely aected by this action. TVA is coordinating with the SHPO or concurrence with this inding.3.. Socioeconomic, nironmental ustice, and Land Use 3.8.1. The 1972 FES on WBN Units 1 and 2 estimated the 1970 population within 10 miles o the site to be 10,515. Rhea County, in which the plant is located, and Meigs County which is located ust east o the site across the rier, were both slow growing, with a total net population growth o 400 between 1960 and 1970. This inormation was updated and epanded or the 1978 NRC FES. While the 1972 FES proected population by the year 2000 to be 11,995 within 10 miles o the site and 1,028,345 within 50 miles, the 1978 NRC FES had slightly lower proections o 10,770 within 10 miles and 950,461 within 50 miles.

In 1995, NRC and TVA proided estimates or 1990 and proections or 2040 (1995 NRC FES, and 1995 FSER). For 1990, population within 10 miles was estimated to be 15,842, and within 50 miles, 862,465. Proections or 2040 were a total population o 17,854 within 10 miles and 1,066,580 within 50 miles. Based on the 2000 Census o Population, the population or 2000 is estimated to be 16,392 within 10 miles and 1,064,513 within 50 miles, indicating that the area around the site has been growing aster than proected. Based on these trends, the population in 2040 is proected to be about 29,300 within 10 miles and 1,519,000 within 50 miles, a much higher growth rate than in earlier proections. Since the earlier reports were prepared both Rhea and Meigs Counties, as well as most o the surrounding counties, hae seen a substantial increase in population growth rates.

Rhea County increased by only about 0.4 percent rom 1980 to 1990, but by 16.7 percent rom 1990 to 2000. Meigs County eperienced a similar increase in growth rate, rom 8.1 percent between 1980 and 1990 to 38.0 percent between 1990 and 2000. Fast-growing areas in Meigs and Rhea Counties include much o the area near the Tennessee Rier, on both sides, and the area to the east toward Athens, Tennessee. Increases rom 1990 to 2000 in surrounding counties within the 50-mile range aried rom 4.5 percent in Anderson County to 34.7 percent in Cumberland County. Population estimates or 2005 show continuing growth in the area and speciically in Rhea and Meigs Counties, but at a somewhat slower rate than during the 1990s. During construction, population would increase due to the inlu o worers. At pea construction employment, the total construction and design employment could be as high as 3000 howeer, many o these are engineers, nonmanual crat, and other worers who liely would not relocate to the site. TVA is conducting a more detailed study o construction reuirements, which will proide a more precise estimate. For this analysis, a conseratie estimate is made by assuming that the pea on-site wororce would be 2200. Based on preious eperience at the site, it is assumed that 40 percent o these would moe into the area. Gien this assumption, the total number o moers would be 880. The remaining 60 percent or more o the worers would either be local residents or would commute rom the surrounding area, including the Chattanooga and noille areas. Impacts o this increase in population should be similar to those described in the earlier documents reerenced aboe.

Chapter 3 Final Supplemental Enironmental Impact Statement 65Based on eperience during construction at Unit 1 rom 1982 to 1986, about two-thirds o the in-moing worers would moe into Rhea and Meigs Counties due to their proimity to the site. Most o the others would locate in readily accessible locations such as McMinn and Roane Counties, and a small number to no or Hamilton Counties and other nearby areas. Actual locations would, o course, depend on the aailability o housing or o sites or recreational ehicles (RVs) and trailers. The widespread distribution o the residential location o worers, including those who moe into the area, would lessen the impacts.

Oerall, this inlu should be similar to what occurred during the mid-1980s with earlier construction at the site, ecept that the number o worers is epected to be slightly lower than during much o the earlier construction. 3.8.2. E I The earlier studies noted that the immediate icinity o the plant, Rhea and Meigs Counties, had been eperiencing employment growth, in particular industrialization. The latest employment data suggest that these counties hae been able to retain their industrial competitie edge. While the nation, the state, and almost all o the counties within the 50 mile area around the plant eperienced substantial decreases in manuacturing employment between 1995 and 2005, Meigs County had a small increase (rom 697 to 741) and Rhea County a ery small increase (rom 4701 to 4711). The aerage decrease or all the counties within the 50-mile area was 20.7 percent, while the state decreased by 23.3 percent and the nation by 22.5 percent. Priate employment other than arm and manuacturing generally had signiicant increases throughout the area, as in the state and

in the nation. The 1995 NRC FES noted that real income in Meigs and Rhea Counties continued to grow. This trend has continued since that time, with per capita personal income in 2005 in Meigs County, 51.3 percent higher than in 1995, and in Rhea County, 40.2 percent higher. In contrast, the Consumer Price Inde increased by 28.1 percent during this time. The growth rate o income in the 50-mile area was 44.4 percent. Most o these rates, howeer, are lower than the state and national aerages o 46.3 and 49.4 percent, respectiely. Much o the income receied by these worers on the WBN Unit 2 proect would be spent in the area, especially by those who moe amilies into the area and those who are already residents. This would increase income o businesses in the area, especially those oriented directly to consumers, and could lead to a small temporary increase in employment. Ater

construction is completed, there would still be some increase in income and employment in the area rom operation o Unit 2, although the size o the increase would be much smaller. 3.8.3. L-I M In Rhea and Meigs Counties in 2000, the minority population was 5.4 and 2.7 percent, respectiely, o the total population. Within 10 miles o the site, the aerage was 3.5 percent and within 50 miles, 11.5 percent. Minority population in the area o Rhea County immediately around the site in 2000 was 2.7 percent o total population (Census Tract 9751, Bloc Group 2) and was 4.5 percent in the area o Meigs County immediately across the Tennessee Rier (Census Tract 9601, Bloc Group 2). In both bloc groups, the minority population is somewhat geographically distributed, not highly concentrated in one location. All o these aerages are well below the state aerage o 20.8 percent and the national aerage o 30.9 percent.

Completion and Operation o Watts Bar Nuclear Plant Unit 2 Final Supplemental Enironmental Impact Statement 66According to the 2000 Census o Population, the poerty leel in Rhea County is 14.7 percent and in Meigs County, 18.3 percent. These rates are higher than both the statewide rate o 13.5 and the national rate o 12.4 percent. The county rates show decreases rom rates 10 years earlier o 19.0 and 22.3 percent the total o persons below the poerty leel decreased rom 4476 to 4042 in Rhea County and increased rom 1761 to 2000 in Meigs County. The most recent estimates, or the year 2004, show a poerty leel in Rhea County o 16.2 percent and in Meigs County, 17.5 percent gien the conidence leels o the estimates, little or no change seems to be indicated since the 2000 Census. Poerty leels within the 10-mile area around the plant are slightly higher than both the state and national leels, with a poerty rate estimated to be about 15.1 percent among those who lie within 10 miles o the site and 11.8 percent within 50 miles. Based on the 2000 Census o Population, the poerty leel in the area immediately around the site (Rhea County, Census Tract 9751, Bloc Group 2) is 18.1. This was a decrease rom 19.0 percent 10 years earlier, although the number o persons below the poerty leel increased rom 237 to 282. In the area immediately across the rier (Meigs County, Census Tract 9601, Bloc Group 2) the poerty leel is 21.7 percent. This was an increase rom 19.2 percent 10 years earlier and an increase in the number o persons below poerty rom 184 to 333.

Within the 10-mile area around the site, the poerty leel decreased rom 16.2 percent in 1989 to 15.1 percent in 1999, increasing rom about 3300 persons to about 3800. This decrease (1.1 percentage points) was greater than the national decrease o 0.7 percentage points, but less than the statewide decrease o 2.2 percentage points. Thus, the poerty leels in the area around the site hae been declining, as hae the rates statewide and nationally, while the number o persons in poerty has continued to increase in some o the areas around the site as it has statewide and nationally. Howeer, the oerall poerty leel in the area is still aboe the state and national aerages and also aboe the leel or the 50-mile area around the site. The low minority population share, along with the diused nature o potential negatie impacts, maes it unliely that there would be disproportionate impacts to minority or low-income populations. Howeer, such impacts are possible, particularly impacts arising rom housing needs and increased traic during the construction period. TVA would wor with local representaties and oicials to help reduce impacts rom these sources by proiding more detailed inormation about the anticipated wororce. A mitigating action could be identiication o the area as an impact area under the eisting state ta code (see Section 3.8.7). This would allow more o the ta euialent payments that TVA annually maes to Tennessee to be allocated to these counties. 3.8.4. S Both Rhea and Meigs Counties hae eperienced notable increases in the number o housing units in recent years. This increase rom 1990 to 2000 was 2204 housing units, 21.3 percent, in Rhea County and 1499 units, 40.6 percent, in Meigs County. Both counties eperienced a higher rate o increase than the state as a whole, which increased by 20.4 percent. This growth may result in more diiculty in inding sites or temporary housing, such as RVs and trailers. Howeer, the temporary inlu o worers during construction would be spread out among not only Rhea and Meigs Counties, but nearby counties also, especially those within 30 to 35 miles away. In addition, many o the worers would be commuting rom their eisting homes in this area or slightly arther away, especially the Chattanooga and noille areas. The result would be some increase in temporary housing needs, including apartments and acilities or trailers and RVs. To the etent that the pattern rom construction in the 1980s is ollowed, Rhea and Meigs liely would see Chapter 3 Final Supplemental Enironmental Impact Statement 67close to 600 temporary worers locating in those two counties o these, about three-ourths would bring amilies with them. At that time, amilies on the aerage had about 1.3 children, maing an aerage amily size o 3.3. Families, especially those with children, would be more liely to loo or houses or apartments while worers moing alone may be more liely to bring trailers or RVs with them or to rent trailers or small apartments. Many, especially those whose wor is liely to continue through most o the construction period, are liely to loo or houses to purchase. The result o this increased demand or temporary housing and or locations or RVs and trailers would be noticeable, especially in Rhea and Meigs Counties. TVA would wor with local representaties and oicials to help reduce impacts by proiding more detailed inormation about the anticipated wororce. A mitigating action could be identiication o the area as an impact area under the eisting state ta code (see Section 3.8.7). Community serices such as health serices, water and sewer, and ire and police protection would also be impacted. While Rhea and Meigs Counties liely would eel the greatest impact, nearby counties would also be impacted. These impacts should be similar to those that occurred earlier with construction o Unit 1 at the site, which were proected to hae no aderse eects. Ater construction is completed, there would be an increase o approimately 150 in permanent employment at the site this increase would be small enough that the community could accommodate it with no noticeable impacts. 3.8.5. S As noted aboe, Rhea and Meigs Counties most liely would be the residential location o roughly two-thirds o the worers who moe into the general area to wor at the site. I the location patterns and moer characteristics o worers during construction o Unit 1 in the 1980s is ollowed, there would be an increase o approimately 660 school-age children in the broader area around the site, o which an estimated 434 liely would reside in Rhea and Meigs Counties. Total public school enrollment in these two counties is approimately 6800. There is some capacity or certain grade leels in some o the schools. Howeer, the systems oerall are at or near capacity, and in some cases oer capacity, such as at Rhea County High School and in some lower grade leels in Rhea County. The schools in these counties hae been eperiencing a steady growth in enrollment or seeral years, and this growth is epected to continue. Additional growth due to an inlu o construction worers would increase the oercrowding already being eperienced. TVA would wor with local representaties and oicials to help reduce impacts by proiding more detailed inormation about the anticipated wororce. A mitigating action could be identiication o the area as an impact area under the eisting state ta code (see Section 3.8.7). 3.8.6. L U Land use in the area around the site was discussed in earlier studies, particularly in the TVA 1972 FES. Since that time, the same general pattern o land use and land use change has continued, with signiicant increases in land used or housing and or commercial purposes, along with ongoing decreases in open space and land used or arming.

Completion and operation o Unit 2 are not liely to hae a maor impact on this trend, although it might accelerate it slightly. As discussed aboe, the number o construction worers and their amilies that would locate in the area during the construction period is epected to be less than 2000.

Completion and Operation o Watts Bar Nuclear Plant Unit 2 Final Supplemental Enironmental Impact Statement 683.8.7. L R Under Section 13 o the TVA Act, TVA maes ta euialent payments to the State o Tennessee, with the amount determined 50 percent by the boo alue o TVA property in the state and 50 percent by the alue o TVA power sales in the state. In turn, the state redistributes 48.5 percent o the increase in payments to local goernments. Payments to counties are based on relatie population (30 percent o the total), total acreage in the county (30 percent), and TVA-owned acreage in the county (10 percent). The remaining 30 percent is paid to cities, distributed on the basis o population. In 2006, ta euialent payments to Rhea County were 724,050 and to Meigs County, 484,465. Completion o WBN Unit 2 would increase boo alue o TVA property in the state and would, thereore, increase ta euialent payments to the state. This increase would be distributed in part to local goernments as described aboe, resulting in a small increase in payments to Rhea

and Meigs Counties. During construction, Tennessee law (Tennessee Code Annotated TCA, 67-9-101) proides or allocation o additional payments to impacted local goernments rom the TVA ta euialent payments. These additional payments would be made to the local goernments, upon designation by TVA o these areas as impacted areas, and would continue throughout the construction period. Payments would continue to be made in decreasing amounts or three years aterward. The actual amount paid would be determined by the state comptroller o the treasury, based on the proisions o TCA 67-9-102(b). The additional payments rom state allocation o TVA ta euialent payments to these local goernments during construction could be used to address some o the impacts on public serices discussed aboe. In addition, there would be additional ta reenue associated with ependitures made in the area or materials associated with the proposed plant completion as well as sales ta reenue associated with purchases by indiiduals employed during construction and subseuently during operation. The magnitude o these increases could ary greatly, depending on the amount o local purchases or construction and on the relocation and buying decisions o worers employed at the site. 3.8.8. E No cumulatie socioeconomic eects were identiied in earlier WBN-related enironmental reiews. The maor change in the areas socioeconomic enironment since those earlier documents were prepared is the more rapid population growth the area has seen and is epected to continue to eperience, especially in the areas along the Tennessee Rier in Rhea and Meigs Counties (Section 3.8.1). Much o this area is sparsely populated and capable o supporting additional growth. Along with this population growth, the area economy is dierse and growing howeer, this growth has resulted in some impact to community serices, most notably in increased oercrowding in certain public schools. The increase rom the inlu o worers during construction o WBN Unit 2 would temporarily add to these impacts, especially to the school systems in Rhea and Meigs Counties. TVA is currently updating the drat land plan and drat enironmental impact statement (TVA 2005d) or Watts Bar Reseroir. TVA plans to issue an amended DEIS or the Watts Bar Reseroir Land Management Plan in the summer o 2007. In the eent that nearby TVA land is allocated or industrial or recreational deelopment in the reised land plan, potential cumulatie eects rom subseuent deelopment in conunction with construction Chapter 3 Final Supplemental Enironmental Impact Statement 69or operation o WBN Unit 2 would be addressed when proposals or deelopment are reiewed.The etent o the impact oerall and on indiidual school systems and schools is largely dependent on where in-moing worers locate their residences. The recent growth that has occurred, along with the epected continuation o this growth, could result in location patterns dierent in some ways rom the patterns associated with earlier construction at the site. For eample, some o the in-coming worers might locate arther away rom the site than they would preer. This could hae the eect o decreasing the number locating in Rhea and Meigs Counties, or parts o these counties, and increasing the number in some nearby counties. Improed roadways in the area, as contrasted to earlier construction periods, may also mae location at greater distances relatiely more attractie, increasing the tendency to locate arther rom the site. In addition to schools, other community serices could be impacted by the temporary inlu o construction worers in conunction with the current growth pattern. These impacts are liely to be less noticeable than the school impacts. Additional road traic at pea times, gien the combination o construction worers and the growth o permanent population, could cause a noticeable impact at some locations. There could also be noticeable impacts to other community serices such as medical acilities and public saety. The etent o all these cumulatie impacts would depend greatly on the residential locations o the in-moing worers. As noted aboe, TVA is conducting a labor study, the results o which will be proided to oicials in the impacted counties to help with local planning to accommodate the anticipated impacts In addition, TVA would wor with the local communities to acilitate planning or these potential impacts. 3.. Floodlains and Flood Ris In the TVA 1972 FES or WBN Units 1 and 2, a letter was included to Mr. Gartrell, with the U.S. Department o the Interior, regarding siting o these units. The letter states Plant Siting--The Geological Surey is reiewing geologic and hydrologic data releant to WBN Units 1 and 2, as supplied by TVA in a preliminary saety analysis report (PSAR) to the AEC. This reiew pertains to geologic and hydrologic aspects o the site such as earthuae eects, oundation conditions, and looding potential. The PSAR became the FSAR on une 30, 1976, with the submittal o amendment 23 (TVA 1976c). The FSAR contains inormation related to potential looding o the Watts Bar site rom the Tennessee Rier and local probable maimum precipitation 4 (PMP) site drainage and is still current. Section 3.7 Floodplains and Flood Ris o the FEA or the WBN Unit 1 Replacement o the Steam Generators describes the current conditions at WBN (TVA 2005a). WBN is located on the right ban o Chicamauga Reseroir between TRM 528.0 and 528.6 in Rhea County, Tennessee. The area potentially impacted by this proect would etend rom about TRM 528.4 to 529.0. The proposed proect area could possibly be looded rom the Tennessee Rier and local PMP site drainage.

4 The Probable Maimum Precipitation is deined as the theoretically greatest depth o precipitation or a gien duration that is physically possible oer a particular drainage area at a certain time o year (American Meteorological Society, 1959). In consideration o the limited nowledge o the complicated processes and interrelationshipsin storms, PMP alues are identiied as estimates.

Completion and Operation o Watts Bar Nuclear Plant Unit 2 Final Supplemental Enironmental Impact Statement 70The 100-year loodplain or the Tennessee Rier would be the area below eleation 697.3 eet aboe mean sea leel (msl) at TRM 528.4 and eleation 697.6-eet msl at TRM 529.0. The Tennessee Rier TVA lood ris proile (FRP) eleation would be eleation 701.1-eet msl at TRM 528.4 and 701.4 at TRM 529.0. The FRP is used to control residential and commercial deelopment on TVA lands and lood damageable deelopment or TVA proects. In this area, the FRP eleations are eual to the 500-year lood eleations. Under current conditions, the estimated Tennessee Rier Probable Maimum Flood 5 (PMF) leel would be eleation 734.9-eet msl at WBN. Conseuent wae run-up aboe the lood leel would be 2.0 eet, which would produce a maimum lood leel o eleation 736.9-eet msl (TVA 2004d). Based on site topography, much o the proposed proect area would be inundated at this eleation. It has preiously been determined that the critical eleation or PMP site drainage should be no higher than eleation 729.0-eet msl. The loodplains and lood ris assessment inoles ensuring that acilities would be sited to proide a reasonable leel o protection rom looding. In doing this, the reuirements o Eecutie Order 11988 (Floodplain Management) would be ulilled. Due to the act that the proposed proect could potentially impact lood eleations at seeral buildings at a nuclear generating acility, the NRC reuires a lood ris ealuation o possible impacts rom the PMF and PMP site drainage or all alternaties. The ollowing proposed actiities could be impacted by lood conditions material handling buildings, materials storage building, a multipurpose building, a new construction access acility, temporary outage building, and an in-processing center would be constructed temporary crat trailers would be added and temporary paring and laydown areas would be deeloped. All proposed acilities would be located outside the limits o the Tennessee Rier 100- and 500-year loodplains, but many o the proposed structures would be located on ground below the Tennessee Rier PMF eleation o 734.9-eet msl. For those structures located below the Tennessee Rier PMF, an acceptable leel o lood ris would be proided because the probability o looding would be etremely low, and looding o these structures would not impact the sae operation o the plant. None o the proposed actiities would result in changes to the Tennessee Rier PMF eleation. All eisting saety-related acilities, systems, and euipment are housed in structures that would proide protection rom looding or all lood conditions up to plant grade at eleation 728-eet msl. Other rainall loods would eceed plant grade eleation 728-eet msl and reuire plant shutdown. Howeer, lood warning criteria and orecasting techniues hae been deeloped to assure that there will always be adeuate time to shut the plant down and be ready or loodwaters aboe plant grade (TVA 2004d). The placement o temporary and permanent structures both inside and outside the security ence would be reuired to complete Unit 2. The tentatie locations o the proposed new structures are shown on the site plan (Figure 1-2). The building numbers in the ollowing analysis correspond to the legend o Figure 1-2. The material handling buildings (2),

materials storage building (4), and in-processing center (32) would be located outside o the The Probable Maimum Flood is deined as the most seere lood that can reasonably be predicted to occur at a site as result o hydrometeorological conditions. It assumes an occurrence o PMP critically centered on the watershed and a seuence o related meteorologic and hydrologic actors typical o etreme storms.

Chapter 3 Final Supplemental Enironmental Impact Statement 71security ence. These structures would not be located within critical areas or PMP site drainage and would not adersely impact PMP site drainage eleations. The new multipurpose building (28) and temporary crat trailers (29) are both within the area deined as Area East o Main Plant in the site drainage calculation that were deeloped or the Watts Bar FSAR (TVA 2004d). The original site analysis determined the eleation resulting rom the site PMP would be less than the critical eleation o 729.0. This was based on a low path rom north to south along the east side the turbines and turbine building and through the switchyard. The new multipurpose building (28) and temporary crat trailers (29) are being designed not to eceed the ootprint o the buildings that hae been remoed rom this area (Richard ing, TVA, personal communication, December 2006). Thereore, the new structures would not impact preiously determined PMP eleations. The proposed new construction access acility (31) would be located adacent to the eisting control building and auiliary (reactor) building and would not impact lood eleations. The temporary outage building (33) would not be an obstruction as shown on the current site plan. Construction o the temporary paring areas (3) could result in minor changes to the eisting topography, but PMP drainage rom these areas does not low toward the plant and, thereore, no aderse impacts would be epected. An area on the west side o the plant south o the Unit 2 material handling building that has in the past been used or temporary paring should be designated as a no paring area. This area is located within the PMP drainage ditch and any cars pared in the area could adersely impact PMP drainage eleations. Although there is no indication that deelopment would tae place in the switchyard area (30), this area has been identiied as critical or PMP drainage.

Thereore, any structural modiications that are proposed in the switchyard should be reiewed prior to construction to ensure they would not adersely impact PMP drainage eleations.Based on the current design and site plan, the proposed proect would be consistent with Eecutie Order 11988, and there would be no anticipated aderse lood-related impacts.

Any changes to the tentatie site plan would be reiewed to determine the potential or lood related impacts. 3.1. Seismic ffects The 1972 FES described the maimum historical Modiied Mercalli Intensity (a scale o earthuae eects that ranges rom Roman numeral I through XII) eperienced at WBN rom local uaes and the origins o this ground motion. The 1995 FSER described the sae shutdown earthuae or WBN and its basis and discussed seismic analyses o WBN using a site-speciic earthuae model and a reiew leel earthuae (TVA 1995b). The WBN FSAR (TVA 2004d) proides a thorough description o the geology and seismicity in the icinity o WBN in Section 2.5. The basic conclusions o the 1995 FSER and the 1972 FES with respect to the regional seismology o WBN and its seismic design remain alid.

There are two items that reuire updating. First, the largest earthuae in the southern Appalachians since the 1972 FES is now the April 29, 2003, Fort Payne, Alabama, earthuae, which had a moment magnitude o 4.6 and Nuttli body wae magnitude o 4.9. The Fort Payne earthuaes magnitude is still lower than the design basis earthuae, which has a body wae magnitude o 5.8 thereore, the occurrence o the 2003 Fort Payne earthuae has no signiicant impact on preious indings.

Completion and Operation o Watts Bar Nuclear Plant Unit 2 Final Supplemental Enironmental Impact Statement 72Second, preliminary results o the Indiidual Plant Eamination or Eternal Eents (IPEEE) or WBN were discussed in the 1995 FSER. The inal results o this study were completed and transmitted to NRC in February 1998 (TVA 1998e). The study included an eamination o seismic eects and concluded that the seismic capacity o WBN or a Reiew Leel Earthuae eceeds 0.3g 6, the minimum leel reuired by NRC. Thereore, no seismic design change recommendations resulted rom the IPEEE seismic ealuation. 3.11. Climatology and eteorology The 1972 FES contains a discussion o the climatology and meteorology or the Watts Bar site. The 1995 FSER proides a description o the Watts Bar on-site meteorological program and a reiew o the preious discussion. The conclusion was that the regional climate description in the 1972 FES remained alid. Some o the inormation was updated based on more recent data. It also concluded that the 20-year data period update (1974-1993) in local meteorology was more representatie than the one year o data used preiously. The seere weather inormation in the 1972 FES was udged to be alid ecept or an update to the tornado data. Regional Climatology The regional climate description in the 1972 FES remains accurate as discussed in this section. This conclusion is based on inormation contained in the , or 2005(U.S.Department o Commerce 2005) and in the 1 (U.S. Department o Commerce 2003). Temperature data or the 1971-2000 period o record or Chattanooga, Tennessee, indicate an aerage annual temperature o 60.0F, with monthly aerages ranging rom 39.4F in anuary to 79.6F in uly. These temperatures are slightly warmer than data or the 1961-1990 period o record used in the 1995 FSER. The etreme temperatures, maimum rainall in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and maimum snowall in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at Chattanooga are the same or the 1971-2000 period as or the 1961-1990 period. Wind speed data rom Chattanooga or the 1971-2000 period o record indicate an aerage wind speed o 5.9 miles per hour. This is slightly lower than data or the 1961-1990 period o record. Local eteorology The one year o data collected rom the temporary WBN meteorological acility is supplemented with more representatie data rom the 20-year period rom 1986-2005. These data were collected rom the permanent meteorological acility. On an annual basis, the most reuent wind directions at 10 meters are south-southwest and southwest at 16.0 percent and 8.4 percent, respectiely. This relects a small shit rom easterly to westerly directions rom the on-site data rom 1974-1993 used in the 1995 FSER. The annual aerage wind speed decreased rom 4.1 miles per hour to 3.7 miles per hour at the 10-meter leel in the more recent 20-year data period. In addition, the annual reuency o calms, deined as wind speeds less than 0.6 mi/h, increased rom 3.0 percent to 3.4 percent. The impact o these changes on dispersion alues is discussed below under the

heading dispersion. Percent g is the orce o graity (an acceleration o 9.78 meters/second 2). When there is an earthuae, the orces caused by the shaing can be measured as a percentage o the orce o graity, or percent g.

Chapter 3 Final Supplemental Enironmental Impact Statement 73Seere Weather Based on Section 2.3.1.3 o the WBN FSAR (TVA 2004d), the seere weather inormation in the 1972 FES remains accurate, ecept or the ollowing update. During the period rom 1916-2005, only one tornado has been reported in Rhea County. The FSAR estimate o the probability o a tornado striing the site is 1.48E-4 with a recurrence interal o 6755 years. This is based on tornado data rom 1950 through 1986. Etension o the tornado database end date rom 1986 to 2005 increases the estimate o the probability o a tornado striing the site to 2.7 E-4 with a recurrence interal o 3703 years. During the period rom 1950-2005, 44 tornadoes were identiied within a 30-nautical-mile radius o Watts Bar (approimately 2827 suare miles). The mean tornado path was 0.96 suare miles, and the annual tornado reuency was 0.80. DisersionSection 5.10 o the 1995 FSER presents the estimated annual airborne doses as calculated by the (TVA 1994b). It uses the 20-year period o meteorological data rom 1974-1993. Use o the later 20-year data period discussed in under local meteorology, aboe, results in an increase o the maimum dispersion alue rom 1.09E-5 to 1.43E-5 second/cubic meters and shits the critical downwind sector rom southeast to east-southeast. The impact o this increase is discussed in Section 3.13.

Air uality Two oil-ired boilers used or building heat and startup steam emit small amounts o air pollutants as addressed in the 1972 FES. These emissions are controlled to meet applicable regulatory reuirements, and resulting impacts are insigniicant. 3.12. uclear Plant Safety and Security 3.12.1. S A A TVA maintains a probabilistic saety assessment model to use in ealuating the most signiicant riss o radiological release rom WBN uel into the reactor and rom the reactor into the containment structure. In 1995, both TVA and NRC concluded that, ecept or a ew procedural changes implemented as part o the WBN operation, none o the seere accident mitigation design alternaties were beneicial to mitigating the ris o seere accidents urther. The term accident reers to any unintentional eent (i.e., outside the normal or epected plant operation enelope) that results in a release or a potential or a release o radioactie material to the enironment. The NRC categorizes accidents as either design basis or seere. Design basis accidents are those or which the ris is great enough that NRC reuires plant design and construction to preent unacceptable accident conseuences. Seere accidents are those that NRC considers too unliely to warrant normal design controls. Since 1995, TVA has implemented the industry-reuired design and corresponding design and corresponding mitigating action changes as reuired by NRC or continued operation o WBN Unit 1 and would implement them or operation o Unit 2. The design changes hae already been implemented in the WBN Unit 1 probabilistic saety assessment model. The analysis is based on the WBN Unit 1 probabilistic saety assessment model, which is considered applicable or Unit 2 operations because o its similarity to Unit 1.

Completion and Operation o Watts Bar Nuclear Plant Unit 2 Final Supplemental Enironmental Impact Statement 74An analysis was perormed or this FSEIS to estimate the human health impacts rom potential accidents at WBN in the eent that Unit 2 became operational (arimi 2007). Only seere reactor accident scenarios leading to core damage and containment bypass or containment ailure are presented here. Accident scenarios that do not lead to containment bypass or containment ailure are not presented because the public and enironmental conseuences would be signiicantly less. The MACCS2 computer code (Version 1.13.1) was used to perorm probabilistic analyses o radiological impacts. The generic input parameters gien with the MACCS2 computer code that were used in NRCs seere accident analysis (NUREG-1150) ormed the basis or the analysis. These generic data alues were supplemented with parameters speciic to WBN and the surrounding area. Site-speciic data included population distribution, economic parameters, and agricultural product. Plant-speciic release data included nuclide release, release duration, release energy (thermal content), release reuency, and release category (i.e., early release, late release). The behaior o the population during a release (eacuation parameters) was based on declaration o a general emergency and the emergency planning zone (EPZ) eacuation time. These data in combination with site-speciic meteorology were used to simulate the probability distribution o impact riss (eposure and atalities) to the surrounding 80-ilometer (within 50 miles) population. The conseuences o a beyond-design-basis accident, with mean meteorological conditions, to the maimally eposed o-site indiidual, an aerage indiidual, and the population residing within an 80-ilometer (50-mile) radius o the reactor site are summarized in Table 3-13. The analysis assumed that a site emergency would hae been declared early in the accident seuence and that all nonessential site personnel would hae eacuated the site in accordance with site emergency procedures beore any radiological releases to the enironment occurred. In addition, emergency action guidelines would hae been implemented to initiate eacuation o 99.5 percent o the public within 16 ilometers (10 miles) o the plant. The location o the maimally eposed o-site indiidual may or may not be at the site boundary or these accident seuences because emergency action guidelines would hae been implemented and the population would be eacuating rom the path o the radiological plume released by the accident. Table 3-13. Seere Accident Annual Riss aimally osed Off-Site ndiidual Aerage ndiidual ember of Poulation Within ilometers (5 miles) Release Category (frequency er reactor year) Dose Ris a(remyear) Cancer Fatality bDose Ris a(remyear) Cancer Fatality bI - Early Containment ailure (3.4 10

-7) 2.2 10-5 2.6 10-81.8 10-7 1.1 10-10II - Containment Bypass (1.4 10

-6) 2.2 10-5 1.3 10-8 8.2 10-7 4.9 10-10III - Late Containment Failure (3.0 10

-6) 4.6 10-7 2.8 10-10 1.3 10-7 7.8 10-11 a Includes the lielihood o occurrence o each release category b Increased lielihood o cancer atality per yearThe results presented in this table indicate that the highest ris to the maimally eposed o-site indiidual is one atality eery 38 million years (or 2.6 10

-8 per year) and the Chapter 3 Final Supplemental Enironmental Impact Statement 75highest ris to an aerage indiidual member o the public is one atality eery 2 billion years (or 4.9 10

-10 per year). Oerall, the ris results presented aboe are small. Completion and operation o WBN Unit 2 would not change the riss ealuated here because the lielihood o an accident that could aect both units and lead to radioactie releases beyond those analyzed here would be etremely low. This is consistent with the conclusions o NRCs Generic Enironmental Impact Statement or License Renewal o Nuclear Plants (GEIS) (NRC 1996a). Accidents that could aect multi-unit sites are initiated by eternal eents. Seere accidents initiated by eternal eents as tornadoes, loods, earthuaes, and ires traditionally hae not been discussed in uantitatie terms in inal enironmental statements and were not considered in the GEIS. In the GEIS, howeer, NRC sta did ealuate eisting impact assessments perormed by NRC and the industry at 44 nuclear plants in the United States and concluded that the ris rom beyond-design-basis earthuaes at eisting nuclear power plants is small. Additionally, the sta concluded that the riss rom other eternal eents are adeuately addressed by a generic consideration o internally initiated seere accidents. 3.12.2. T Some nongoernmental entities and members o the public hae epressed concern about the riss posed by nuclear generating acilities in light o the threat o terrorism. Because WBN is already an actie nuclear generating acility, the riss posed by adding a second generating unit are not the same as the riss that may be associated with locating a nuclear generating acility at a new location. The ris posed by a terrorist attac already eists at this site. Regardless, TVA beliees that the possibility o a terrorist attac aecting operation o WBN Unit 2 or the combined operation o both WBN units is ery remote and that postulating potential health and enironmental impacts rom a terrorist attac inoles substantial speculation. TVA has in place detailed, sophisticated security measures to preent physical intrusion into its nuclear plant sites, including WBN, by hostile orces seeing to gain access to plant nuclear reactors or other sensitie acilities or materials. TVA contract security personnel are trained and retrained to react to and repel hostile orces threatening TVA nuclear acilities. TVAs security measures and personnel are inspected and tested by the NRC. It is highly unliely that a hostile orce could successully oercome these security measures and gain entry into sensitie acilities, and een less liely that they could do this uicly enough to preent operators rom putting plant reactors into sae shutdown mode.

Howeer, the security threat that is more reuently identiied by members o the public or in the media are not hostile orces inading nuclear plant sites but attacs using hiaced et airliners, the method used on September 11, 2001, against the World Trade Center and the Pentagon. The lielihood o this now occurring is eually remote in light o todays heightened security awareness, but this threat has been careully studied. The Nuclear Energy Institute (NEI) commissioned the Electric Power Research Institute (EPRI) to conduct an impact analysis o a large et airline being purposeully crashed into sensitie nuclear acilities or containers including nuclear reactor containment buildings, used uel storage ponds, used uel dry storage acilities, and used uel transportation containers. The EPRI analysis was peer reiewed when it was inished. Using conseratie analyses, EPRI concluded that there would be no release o radionuclides rom any o these acilities or containers. They are already designed to withstand potentially destructie eents. Nuclear reactor containment buildings, or eample, hae thic concrete walls with heay reinorcing steel and are designed to withstand large Completion and Operation o Watts Bar Nuclear Plant Unit 2 Final Supplemental Enironmental Impact Statement 76earthuaes, etreme oerpressures, and hurricane orce winds. Using computer models, a Boeing 767-400 was crashed into containment structures that were representatie o all U.S. nuclear power containment types. The containment structures suered some crushing and chipping at the maimum impact point but were not breached. The results o this analysis are summarized in an NEI paper titled Aircrat Crash Impact Analyses Demonstrate Nuclear Power Plants Structural Strength (NEI 2002). (For security reasons, the EPRI analysis has not been publicly released.) The EPRI analysis is ully consistent with research conducted by NRC. When NRC recently considered such threats, NRC Commissioner McGaigan obsered

()()(2)Notwithstanding the ery remote ris o a terrorist attac aecting WBN operations, TVA increased the leel o security readiness, improed physical security measures, and increased its security arrangements with local and ederal law enorcement agencies at all o its nuclear generating acilities ater the eents o September 11, 2001. These additional security measures were taen in response to adisories issued by NRC. TVA continues to enhance security at its plants in response to NRC guidance. The security measures TVA has taen at WBN are complemented by the measures taen throughout the United States to improe security and reduce the ris o successul terrorist attacs. This includes measures designed to respond to and reduce the threats posed by hiacing large et

airliners.In the ery remote lielihood that a terrorist attac did successully breach the physical and other saeguards at WBN resulting in the release o radionuclides, the conseuences o such a release are reasonably captured by the discussion o the impacts o seere accidents discussed aboe in this section. 3.13. Radiological ffects This section discusses the potential epected radiological dose eposure o the public during normal operations o WBN Units 1 and 2. Based on operational data rom WBN Unit 1, TVA epects WBN Unit 2 dose data to be o the same magnitude as those proected in its 1972 FES or a single unit. TVA has determined that the doses to the public resulting rom the discharge o radioactie eluents rom WBN would liely be less than two percent o the NRC guidelines gien in 10 CFR 50 Appendi I, and that there would be no new or Chapter 3 Final Supplemental Enironmental Impact Statement 77dierent eects on the surrounding enironment due to these releases than rom those discussed in the FES. NRC addressed potential radiological eects in detail in its SEIS, at pp. 5-11 to 5-21 (NRC 1995b). TVAs assessment o potential impact agrees with NRCs. The dose alues used in the Drat SEIS assessment were based on calculations that used meteorological data rom anuary 1974 to December 1993. TVA has recalculated the dose alues using meteorological data rom anuary 1986 to December 2005 or the FSEIS. The reised alues do not dier materially rom those presented in the DSEIS. Radiological macts on umans Radionuclides in Liuid EluentsThe eposure pathways to humans that were used in the 1972 FES analysis remain alid. The pathways considered are illustrated in Figure 3-6. Seeral o the pathways included in the 1972 FES analysis are not considered in the current analysis o the impact o the release o radioactiity in liuid eluents in the area around WBN site. These pathways are doses receied rom swimming in and boating on the Tennessee Rier. These pathways are no longer considered because they hae been ound to be seeral orders o magnitude lower than the dose receied rom shoreline recreation. The eclusion o these eternal dose pathways or the analysis does not signiicantly change the calculated dose commitments to indiiduals or populations since essentially all o the total body dose due to the release o radioactie material is accounted or by ish and water ingestion. Doses to terrestrial ertebrates rom the consumption o auatic plants, and doses to auatic plants, auatic inertebrates, and ish hae not been reassessed in the current analysis o the impact o radioactiity in liuid eluents because doses to these organisms are less than or eual to the doses to humans (TVA 1972). Current analyses o potential doses to members o the public due to releases o radioactiity in liuid eluents are calculated using the models presented in NUREG-0133 (NRC 1996b) and 111 (NRC 1977). These models are essentially those used in the 1972 FES, and are based on the

2. Changes in the model assumptions since the release o the 1972 FES include The calculation o doses to additional organs (idney and lung). Rier water use (ingestion, ish harest), and recreational use data hae been updated using more recent inormation (Tables 3-14 and 3-15). Decay time between the source and consumption is handled as describe in 11(NRC 1977)Only those doses within a 50-mile radius o WBN are considered in the population dose.

The population data are updated and proected through the year 2040.

Completion and Operation o Watts Bar Nuclear Plant Unit 2 Final Supplemental Enironmental Impact Statement 78Figure 3-. Pathays to an Due to Releases of Radioactie aterial Chapter 3 Final Supplemental Enironmental Impact Statement 79Table 3-1. Public Water Sulies Within a 5-ile Radius Donstream of W ameTennessee Rier ile stimated 2 Poulation Dayton, Tennessee 50419,170Soddy-Daisy/Falling Water Utility District 487 11,452 East Side Utility, Tennessee 47349,700Chattanooga, Tennessee 465237,048Table 3-15. stimated Recreational Use of Tennessee Rier Within a 5-ile Radius Donstream of W ame eginning TR 1 nding TRSie (acres) stimated 2 Recreational isitsyear Chicamauga Reseroir (rom WBN to 100 percent miing point) 528 510 4,799 120,986 Chicamauga Reseroir (rom 100 percent miing point to SN) 510 484 22,101 1,297,880 Chicamauga Reseroir (rom SN to Chicamauga Dam) 484 471 9,889 7,421,905 Nicaac Reseroir (rom Chicamauga Dam to WBN 50-mile radius) 471 460 1,799 284,000 1Tennessee Rier Mile Transer coeicients, consumption rates, and bioaccumulation actors used are those presented in the documents listed aboe, or more recent data, i aailable. The models and input ariable used are those presented in the (TVA 1994b) which was approed by the NRC on uly 26, 1994. The estimated liuid radioactie releases used in the analysis are gien in Table 3-16.

Completion and Operation o Watts Bar Nuclear Plant Unit 2 Final Supplemental Enironmental Impact Statement 80Table 3-1. W Total Annual Discharge-Liquid Waste Processing System for To-Unit Oeration uclide 1 Unit LRW 1 1 Unit S 2 1 Unit Totals 2 Unit Totals Br-84 1.65E-04 5.23E-04 6.88E-04 1.38E-03 I-131 2.63E-02 1.14E+00 1.16E+00 2.33E+00 I-132 1.32E-02 1.08E-01 1.21E-01 2.43E-01 I-133 5.29E-02 8.57E-01 9.10E-01 1.82E+00 I-134 6.26E-03 2.65E-02 3.28E-02 6.55E-02 I-135 4.75E-02 4.22E-01 4.70E-01 9.39E-01 Rb-88 6.89E-03 7.84E-04 7.68E-03 1.54E-02 Cs-134 2.93E-02 1.68E-01 1.98E-01 3.95E-01 Cs-136 2.55E-03 1.72E-02 1.98E-02 3.96E-02 Cs-137 4.03E-02 2.21E-01 2.61E-01 5.23E-01 Na-24 1.86E-02 0.0E+00 1.86E-02 3.72E-02 Cr-51 7.03E-03 9.27E-02 9.98E-02 2.00E-01 Mn-54 4.99E-03 5.10E-02 5.59E-02 1.12E-01 Fe-55 8.09E-03 0.0E+00 8.09E-03 1.62E-02 Fe-59 2.42E-03 9.05E-03 1.15E-02 2.29E-02 Co-58 2.20E-02 1.44E-01 1.66E-01 3.31E-01 Co-60 1.44E-02 1.72E-02 3.16E-02 6.32E-02 Zn-65 3.82E-04 0.0E+00 3.82E-04 7.65E-04 Sr-89 1.92E-04 4.33E-03 4.52E-03 9.03E-03 Sr-90 2.20E-05 3.88E-04 4.10E-04 8.19E-04 Sr-91 2.84E-04 2.18E-03 2.47E-03 4.94E-03 Y-91m 1.68E-04 0.0E+00 1.68E-04 3.37E-04 Y-91 9.00E-05 3.00E-04 3.90E-04 7.80E-04 Y-93 1.27E-03 0.0E+00 1.27E-03 2.54E-03 Zr-95 1.39E-03 1.20E-02 1.34E-02 2.68E-02 Nb-95 2.10E-03 8.98E-03 1.11E-02 2.22E-02 Mo-99 4.20E-03 9.95E-02 1.04E-01 2.07E-01 Tc-99m 3.35E-03 0.0E+00 3.35E-03 6.70E-03 Ru-103 5.88E-03 0.0E+00 5.88E-03 1.18E-02 Ru-106 7.63E-02 0.0E+00 7.63E-02 1.53E-01 Te-129m 1.41E-04 0.0E+00 1.41E-04 2.82E-04 Te-129 7.30E-04 0.0E+00 7.30E-04 1.46E-03 Te-131m 8.05E-04 0.0E+00 8.05E-04 1.61E-03 Te-131 2.03E-04 0.0E+00 2.03E-04 4.06E-04 Te-132 1.11E-03 2.93E-02 3.05E-02 6.09E-02 Ba-140 1.02E-02 3.48E-01 3.58E-01 7.16E-01 La-140 1.62E-02 4.98E-01 5.14E-01 1.03E+00 Ce-141 3.41E-04 0.0E+00 3.41E-04 6.81E-04 Ce-143 1.53E-03 0.0E+00 1.53E-03 3.05E-03 Chapter 3 Final Supplemental Enironmental Impact Statement 81Table 3-1 (continued) uclide 1 Unit LRW 1 1 Unit S 2 1 Unit Totals 2 Unit Totals Ce-144 6.84E-03 1.26E-01 1.33E-01 2.66E-01 Np-239 1.37E-03 0.0E+00 1.37E-03 2.75E-03 H-3 1.25E+03 0.0E+00 1.25E+03 2.51E+03 H-3 (TPC) 3.33E+03 0.0E+00 3.33E+03 4.58E+03 Totals o -3 .3-1 . . Totals -3 1.253 1.23 2.523 Total -3 (TPC

3) 3.333 3.333 .53 1Liuid Radwaste 2Steam Generator Blowdown 3 Tritium Production Core (single unit) A companion igure, illustrating the release points or radioactie plant liuid eluents rom WBN is presented in Figure 3-7. A simpliied diagram o the WBN radioactie liuid waste (radwaste) system is shown in Figure 3-8. The liuid radwaste system is designed to control and minimize release o the subect radionuclides. A tabulation o the resulting calculated doses or Unit 2 without TPC is gien in Table 3-17. Doses or adults, teens, children, and inants are in millirem (mrem). Population doses are in man-rem.The estimated annual liuid releases and resulting doses as presented by the TVA 1972 FES, the WBN Unit 1 FSAR, Unit 2, Unit 1 and 2 totals, and recent historical data rom WBN Unit 1 (as submitted in the Annual Radioactie Eluent Reports to the NRC) with the guidelines gien by NRC in 10 CFR 50, Appendi I are compared in Table 3-18. These guidelines are designed to assure that releases o radioactie material rom nuclear power reactors to unrestricted areas during normal conditions, including epected occurrences, are ept as low as practicable.

Completion and Operation o Watts Bar Nuclear Plant Unit 2 Final Supplemental Enironmental Impact Statement 82GPM = Gallons per Minute Figure 3-. Plant Liquid ffluent Pathays and Release Points Chapter 3 Final Supplemental Enironmental Impact Statement 83Figure 3-. Watts ar uclear Plant Liquid Radaste System Completion and Operation o Watts Bar Nuclear Plant Unit 2 Final Supplemental Enironmental Impact Statement 84Table 3-1. Watts ar uclear Plant Doses From Liquid ffluents er Unit for ear 2 (mrem) ADULT TB 1 Bone GIT 2 Thyroid Lier idney Lung Sin 0.72 0.56 0.132 0.88 0.96 0.352 0.136 0.031 TTB Bone GIT Thyroid Lier idney Lung Sin 0.44 0.6 0.104 0.8 1 0.356 0.1520.031 CLD TB Bone GIT Thyroid Lier idney Lung Sin 0.188 0.76 0.06 0.92 0.88 0.312 0.128 0.031 FATTB Bone GIT Thyroid Lier idney Lung Sin 0.032 0.0360.033 0.264 0.036 0.034 0.032 0.031 (man-rem)

POP 3 DOS TB Bone GIT Thyroid Lier idney Lung Sin 1.14 1.24 1 10.8 1.5 0.98 0.73 0.222 TB Bone GIT Thyroid Lier idney Lung Sin POP DOS 2 1.619 1.7611.42015.3362.1301.392 1.0370.315 1Total body 2 Gastro intestinal tract 3Population Table 3-1. Comarison of stimated Annual Liquid Releases and Resulting Doses er Unit at W12 FS(Table 2.-2)

Unit 1 FSAR Unit 2 aluation Units 1 2 Combined Unit 1 1 year Oerational Aerage 1 CFR 5 Aendi uidelines er Unit Tritium Released (Ci) 11.46E+02 3.33E+03 1.25E+03 4.58E+03 707 N/A 2 Actiity Released (Ci) 13.2E-01 4.84 4.84 9.682.2E-01 10 Total ody Dose (mrem)31.7E-02 7.2E-01 7.2E-01 1.44E+00 3.1E-02 3 aimum Organ Dose (mrem)35.5E-02 1.0 E+00 1.0E+00 2.0E+004.25E-02 10 1 Ci = Curies 2 N/A = Not Applicable 3 mrem = millirem Chapter 3 Final Supplemental Enironmental Impact Statement 85Seeral conclusions can be drawn rom the data in Table 3-18 The Unit 2 estimates, een though based on ery conseratie (worst-case) assumptions, indicate that estimated doses would continue to meet the per unit dose guideline gien in 10 CFR Part 50, Appendi I. Recent WBN operational data or liuid eluents indicated that actual releases and resulting dose estimates to the public are a small raction o the Appendi I guidelines (aeraging about two percent or less). Based on these conclusions, the analyses o radiological impact to humans rom liuid releases in the TVA FES continue to be alid, and operation o WBN Unit 2 would not materially change the result. Radionuclides in Gaseous EluentsThe eposure pathways used in the current analyses o the impact o radioactie material released in gaseous eluents are epanded rom those used in the 1972 FES. The pathways considered are illustrated in Figure 3-6. These pathways include eternal doses due to noble gases, and internal doses rom particulates due to inhalation, and the ingestion o mil, meat, and egetables rom the area around WBN. Changes in the model assumptions since the publication o the TVA FES include the calculation o internal doses to additional organs (bone, lier, total body, gastrointestinal tract, idney, and lung) actual land use surey results are used (shown in Table 3-19) and the population data are proected through the year 2040. Current analyses o potential doses to members o the public due to releases o radioactiity in gaseous eluents are calculated using the models presented in NUREG-0133 (NRC 1996b) and 111(NRC 1977) These models are those used in the TVA FES, and are based on the 2Transer coeicients, consumption rates, and bioaccumulation actors used are those presented in the documents listed aboe, or more recent data, i aailable. The models and input ariable used are those presented in the which was approed by the NRC on uly 26, 1994. The estimated gaseous radioactie releases used in the analysis are gien in Table 3-20.

Completion and Operation o Watts Bar Nuclear Plant Unit 2Table 3 Recetors from Actual Land Use Surey Results Used for Potential aseous Releases From W Unit 2Recetor umberRecetorTye Sector Distance (meters)1.Nearest Resident N21342.Nearest Resident NNE36003.Nearest Resident NE33534.Nearest Resident ENE24145.Nearest Resident E32686.Nearest Resident ESE44167.Nearest Resident SE13728.Nearest Resident SSE15249.Nearest Resident S158510.Nearest Resident SSW 197911.Nearest Resident SW423012.Nearest Resident WSW182913.Nearest Resident W289614.Nearest Resident WNW164615.Nearest Resident NW206116.Nearest Resident NNW 438917.Nearest Garden N766418.Nearest Garden NNE617319.Nearest Garden NE335320.Nearest Garden ENE492721.Nearest Garden E637222.Nearest Garden ESE475823.Nearest Garden SE463324.Nearest Garden SSE745425.Nearest Garden S225426.Nearest Garden SSW 197927.Nearest Garden SW810028.Nearest Garden WSW466729.Nearest Garden W512030.Nearest Garden WNW590931.Nearest Garden NW317032.Nearest Garden NNW 460233.Mil Cow ESE670634.Mil Cow SSW 228635.Mil Cow SSW 335386Final Supplemental Enironmental Impact Statement Chapter 3 Table 3 W Total annual aseous discharge Per Oerating Unit (curiesyearreactor)uclide Containment uildingAuiliary uilding Turbine uilding Totalr-85m 3.72E+004.53E+001.23E+009.48E+00r-856.69E+027.05E+001.86E+006.78E+02r-874.48E-014.27E+001.09E+005.81E+00r-883.10E+007.95E+002.13E+001.32E+01Xe-131m 1.07E+031.73E+014.53E+001.09E+03Xe-133m 4.07E+011.90E+005.21E-014.31E+01Xe-133 2.82E+036.70E+011.77E+012.90E+03Xe-135m 2.26E-023.68E+009.80E-014.68E+00Xe-135 5.83E+012.40E+016.46E+018.88E+01Xe-137 3.76E-049.67E-012.58E-011.23E+00Xe-138 1.69E-023.42E+009.06E-014.34E+00Ar-413.40E+010.00E+000.00E+003.40E+01Br-848.16E-075.02E-024.81E-045.07E-02I-1316.74E-031.39E-017.08E-031.53E-01I-1321.36E-046.56E-011.70E-026.73E-01I-1332.36E-034.35E-012.03E-024.57E-01I-1344.26E-051.06E+001.47E-021.07E+00I-1358.80E-048.10E-013.13E-028.42E-01H-31.39E+020.00E+000.00E+001.39E+02H-3 (TPC) 3.70E+020.00E+000.00E+003.70E+02Cr-519.21E-055.00E-040.00E+005.92E-04Mn-54 5.30E-053.78E-040.00E+004.31E-04Co-578.20E-060.00E+000.00E+008.20E-06Co-582.50E-042.29E-020.00E+002.32E-02Co-602.61E-058.71E-030.00E+008.74E-03Fe-592.70E-055.00E-050.00E+007.70E-05Sr-891.30E-042.85E-030.00E+002.98E-03Sr-905.22E-051.09E-030.00E+001.14E-03Zr-954.80E-081.00E-030.00E+001.00E-03Nb-951.80E-052.43E-030.00E+002.45E-03Ru-1031.60E-056.10E-050.00E+007.70E-05Ru-1062.70E-087.50E-050.00E+007.50E-05Sb-1250.00E+006.09E-050.00E+006.09E-05Cs-1342.53E-052.24E-030.00E+002.27E-03Cs-1363.21E-054.80E-050.00E+008.01E-05Cs-1375.58E-053.42E-030.00E+003.48E-03Ba-1402.30E-074.00E-040.00E+004.00E-04Ce-1411.30E-052.64E-050.00E+003.95E-05C-142.80E+004.50E+000.00E+007.30E+00Final Supplemental Enironmental Impact Statement 87 Completion and Operation o Watts Bar Nuclear Plant Unit 2 Final Supplemental Enironmental Impact Statement 88Figure 3-. Watts ar uclear Plant aseous ffluent Release Points AuxiliaryBuildingVent(common) andContainment

Continuous

Vents Chapter 3 Final Supplemental Enironmental Impact Statement 89A tabulation o the resulting calculated gaseous doses to indiiduals per operational unit is gien in Table 3-21. Table 3-21 W Doses From aseous ffluent for Unit 2 Without Tritium Production for ear 2 ffluent Pathay uideline

• Location Dose Noble Gases Air dose 10 mrad Maimum Eposed Indiidual 1 0.801 mrad/year Air dose 20 mrad Maimum Eposed Indiidual 1 2.710 mrad/year Total body 5 mrem Maimum Residence2,3 0.571 mrem/year Iodines/Particulate Sin 15 mrem Maimum Residence2,3 1.540 mrem/year Bone (critical organ) 15 mrem Maimum Real Pathway 49.15 mrem/year Breadown o Iodine/Particulate Doses (mrem/yr) Total Vegetable Ingestion 6.57Inhalation 0.0704 Ground Contamination 0.0947 Submersion 0.130 Bee Ingestion 5 2.28 Total 9.145

• Guidelines are deined in Appendi I to 10 CFR Part 50.

1Maimum eposure point is at 1250 meters in the ESE sector.

2Dose rom air submersion.

3Maimum eposed residence is at 1372 meters in the SE sector.

4Maimum eposed indiidual is a child at 1979 meters in the SSW sector.

5Maimum dose location or all receptors is 1250 meters in the ESE Sector.

The estimated annual airborne releases and resulting doses as presented by the 1972 FES, the WBN Unit 1 FSAR, Unit 2, Unit 1 and 2 totals, and recent historical data rom WBN Unit 1 (as submitted in the Annual Radioactie Eluent Reports to the NRC) with NRC guidelines gien in 10 CFR 50 Appendi I are compared in Table 3-22. These guidelines are designed to assure that releases o radioactie material rom nuclear power reactors to unrestricted areas during normal conditions, including epected occurrences, are ept as low as practicable.

Completion and Operation o Watts Bar Nuclear Plant Unit 2 90 Final Supplemental Enironmental Impact Statement Table 3 Comarison of stimated Annual Airborne Releases and Resulting Doses 1972 (Table 2.4-2)

Unit 1 FSAR Unit 2 Ealuation Units 1 2 Combined Unit 1 10-year Operational Aerage 10CFR50 Appendi I Guidelines per Unit Particulate Actiity (Ci 1)3.00E-01 4.71E-01 4.71E-01 9.42E-01 9.29E-05 10 oble as Actiity (Ci 1)7.00E+03 4.84E+03 4.84E+03 9.68E+03 2.70E-03 N/A 2 ternal Dose (mrad 3)6.60E+00 2.71E+00 3.50E+00 6.21E+00 3.69E-01 10 Organ Dose (mrem 4)3.50E+00 (inhalation and mil only) 9.41E+00 (all pathways) 9.15E+00 (all pathways) 1.86E+01 (allpathways) 8.30E-02 (all pathways) 15 1 Ci = Curies 2 N/A = Not Applicable 3 mrad = millirad 4 mrem = millirem Two conclusions can be drawn rom the data in Table 3-20 The Unit 2 FSAR estimates, een though based on ery conseratie (worst-case) assumptions, indicate that estimated doses continue to meet the per unit dose guidelines gien in 10 CFR Part 50, Appendi I. Historical WBN operational data or airborne eluents indicate that actual releases and resulting dose estimates (eternal and organ) to the public are a small raction o the Appendi I guideline (aeraging about 1 percent or less). Based on these conclusions, the analyses o radiological impact rom airborne release in the 1972 FES continue to be alid, and operation o WBN Unit 2 would not materially change the results. Population DosesTVA has estimated the radiological impact rom the normal operation o WBN Unit 2 using a 50-mile regional population proection or the year 2040 o 1,523,385. The estimated population doses are presented by the 1972 FES, the WBN Unit 1 FSAR, Unit 2, Unit 1 and Unit 2 totals, and recent historical data rom WBN (as submitted in the annual radioactie Eluent Reports to the

NRC) are presented in Table 3-23. Table 3 stimated Poulation Doses From Oeration of Watts ar uclear Plant 1972 (Table 2.4-4)

Unit 1 FSAR Unit 2 EaluationUnits 1 2 Combined Unit 1 10-year OperationalAerage 10 CFR 50 Appendi I Guidelines3.10E+01 4.35E+00 6.66E+01 1.10E+01 3.38E-01 N/A Chapter 3 Final Supplemental Enironmental Impact Statement 91Releases to Sanitary SewersReleases to sanitary sewage systems rom WBN would continue to be sampled or radioactiity. Any identiied radioactiity will be ealuated or its source. I the source o the radioactiity is determined to be rom plant operation, the sewage would not be released to the sewer system, but will be treated as radioactie waste. 3.1. Radioactie Waste The 1995 FSER described changes in plans or the radioactie water treatment systems, which had occurred since the 1970s (TVA 1995b). Many o the systems described in that document were based on TVAs eperience rom SN, which are comparable to the systems in use at WBN Unit 1. The updates in this section are based on TVAs operating eperience at WBN Unit 1. Since hazardous waste handling euipment is either shared between units or would be similar, the processing o radioactie waste produced by the operation o Unit 2 would be perormed in the same manner as Unit 1. Only minor changes hae been made to the radioactie waste treatment system at WBN Unit 1 since 1995, and these changes do not alter the conclusions preiously reached. Liquid Radioactie Waste Treatment Systems The 1995 FSER discussed attributes such as separation and processing o tritiated and nontritiated liuids, laboratory sample processing, and processing o waste rom regeneration o condensate polishing demineralizer and spent resin. Since 1995, the boric acid eaporators and condensate demineralizer waste eaporator (CDWE) system hae been deactiated and the unctions hae been replaced with the mobile waste demineralizer system described in the 1995 FSER. These changes are shown in Figure 3-10 or tritiated water and Figure 3-11 or nontritiated water (reised rom Figure 4-1, TVA 1995b). The conclusion in the FSER that any releases rom these systems would meet the reuirements o the NPDES permit, 10 CFR 20, Appendi B 10 CFR 50, Appendi I and 40 CFR 190, as applicable, remain alid, and operation o WBN Unit 2 would not change this conclusion. aseous Radioactie Waste Treatment Systems The gaseous waste processing system is designed to remoe ission product gases rom the nuclear steam supply system and to permit operation with periodic discharges o small uantities o ission gasses through the monitored plant ent. No changes to euipment or operation hae occurred and, thereore, the conclusions remain alid.

Completion and Operation o Watts Bar Nuclear Plant Unit 2 Final Supplemental Enironmental Impact Statement 92Figure 3-1. Liquid Radaste Processing System Simlified Flo Diagram for Tritiated Water Chapter 3 Final Supplemental Enironmental Impact Statement 93Figure 3-11. Liquid Radaste Processing System Simlified Flo Diagram for ontritiated Water Completion and Operation o Watts Bar Nuclear Plant Unit 2 Final Supplemental Enironmental Impact Statement 94Solid Radioactie Wastes Radioactie waste (radwaste) generated rom the operation o WBN Unit 2 would be handled in the same manner as radwaste rom Unit 1. The solid radwaste disposal system (SRDS) processes and pacages the dry and wet solid radioactie waste produced through power generation or o site shipment and disposal. The dry actie waste (DAW) consists o compactable and noncompactable material. Compactable material includes paper, rags, plastic, mop heads, discarded clothing, and rubber boots. Noncompactable wastes include tools, pumps, motors, ales, piping, and other large radioactie components. The wet actie wastes (WAW) consist o spent resins and ilters. Radwaste is classiied as either A, B, or C, with Class A being the least hazardous and Class C being t he most hazardous. Class A includes both DAW and WAW. Classes B and C are normally WAW. The SRDS is a shared system between Units 1 and 2. The sharing does not inhibit the sae shutdown o one unit while the other unit is eperiencing an accident. Some minor changes to the SRDS hae occurred since 1995. The 1995 FSER discusses solidiication o resins and eaporator concentrates using cement and ermiculite. Eaporator concentrates are no longer generated at WBN due to the deactiation o the CDWE (see Liuid Radioactie Waste Treatment Systems, aboe). Handling o resins has

not changed. In 1995, TVA planned to send low-leel radwaste to Barnwell, South Carolina, until a new disposal acility at Wae County, North Carolina, opened in mid-1998. This acility was not constructed. TVA has continued to ship all WAW (Classes A, B, and C) to the Barnwell acility and will do so through 2008 when that acility is scheduled to close. All DAW is currently shipped to a processor in Oa Ridge, Tennessee, or compaction and then by the processor to Clie, Utah, or disposal. Following 2008, Class A WAW will also be shipped to Clie, Utah. Class B and C waste will be shipped either to SN, which is licensed to receie and store lowleel radwaste rom WBN, or to another licensed Class B and C radwaste disposal acility. WBN also has the option o compacting DAW on site. The shipping distances to these acilities are comparable or shorter than those analyzed in preious enironmental reiews. Transortation of Solid Waste In the 1995 FSER, TVA used records documenting radioactie eluents and the results o o-site radiological monitoring at SN to conirm the 1972 FES conclusion that insigniicant enironmental ris would result rom the transportation o low-leel waste to o-site disposal grounds is still alid. The eposures in Table 4-1 o the 1972 FSER were calculated rom an estimated 43 shipments and 15,119 cubic eet o waste rom SN. WBN now has oer 10 years o radwaste shipment records. During a one-year period ranging rom May 2005-May 2006, there were eight shipments rom WBN, or a total o 5120 cubic eet o waste. The addition o a second unit at WBN would result in a total o 16 shipments per year and 11,060 cubic eet o waste (Table 3-24). These igures represent 37.2 percent and 73.1 percent o the alues presented in the 1995 FSER, and thereore, it can be epected that eposures to the truc drier and to the public would also range rom 37.2 percent and 73.1 percent o the eposure estimated in the 1995 FSER. The 1995 FSER conirmed the conclusion in the 1972 FES that the enironmental ris rom transportation o low-leel waste to o-site disposal grounds would be insigniicant. Gien that the number and size o shipments per year are less than preiously proected, this conclusion is not changed.

Chapter 3 Final Supplemental Enironmental Impact Statement 95Table 3-2. aimum Anticiated To-Unit Annual Solid Radaste to be Processed Waste Tye olume (cubic feet) Spent Resins and Filter Sludges 720Filter Cartridges 240Compactable and Noncompactable Trash10,000Contaminated Oil 100Total11, 3.15. Sent Fuel Storage The 1972 FES assumed that spent uel would be shipped to the reprocessing plant in Barnwell, South Carolina. The 1993 reiew o the FES noted that reprocessing was no longer liely, and that TVA then epected to store spent uel on-site until the DOE completed the construction o storage or permanent disposal acilities in accordance with the Nuclear Waste Policy Act o 1982 (TVA 1993a). The reised plan was or TVA to proide additional storage capacity on site, i needed, until a licensed DOE acility became aailable. On-site storage o spent uel was mentioned in the 1995 FES, but not in the 1995 FSER. The need to epand on-site spent uel storage at TVA nuclear plants was addressed when DOE prepared the CLWR FEIS (DOE 1999). This FEIS analyzed spent uel storage needs at BFN Units 1, 2, and 3, SN Units 1 and 2, and WBN Unit 1 and included a thorough reiew o the enironmental eects o constructing and operating an on-site independent spent uels storage installation (ISFSI). The present FSEIS incorporates by reerence the spent uel storage impact analysis in the CLWR FEIS and updates the analysis to include operation o WBN Unit 2. Operation o a second unit at Watts Bar would increase the number o spent uel assemblies generated at the site. For the purpose o this FSEIS, it is assumed that the additional spent uel generated by the operation o a second unit would be accommodated at the site in a dry cas ISFSI. This generic ISFSI would be designed to store the number o additional spent nuclear uel assemblies reuired or 40-year, two-unit operation at the reactor site. The additional uel generated by the operation o Unit 2 would accelerate the schedule or on-site dry cas spent uel storage epansion at WBN. To date, no ISFSI has been constructed at WBN. Under the current schedule or Unit 1, an ISFSI would be needed by 2018. Assuming WBN Unit 2 would begin operation in 2012, the ISFSI would be needed by 2015. The CLWR FEIS assessed the number o dry storage cass needed to accommodate tritium production at WBN Unit 1 based on 24-pressurized water reactor spent nuclear uel assembly capacity o our o the ISFSI cas designs in the United States at the time. Table 3-25 below updates Table 5-48 in the CLWR FEIS or WBN Unit 1 and adds data or Unit 2 to proide an estimated total number o cass that would be needed or 40 years o operation i WBN Unit 2 were completed. Although SN has receied licensing approal to use cass that can contain 32 spent uel assemblies, this ealuation uses the more conseratie 24-uel assembly cas design capacity. Note that the data or WBN Unit 2 relects the dierence between a unit producing tritium (Unit 1) and one that would not produce tritium (Unit 2).

Completion and Operation o Watts Bar Nuclear Plant Unit 2 Final Supplemental Enironmental Impact Statement 96Table 3-25. Data for umber of SFS Cass Determination Data Parameter W Unit 1W Unit 2Operating cycle length 18 months 18 months Fresh uel assemblies per cycle no tritium 8080Fresh uel assemblies per cycle maimum tritium 136 N/A Increase in resh uel assemblies due to tritium 56N/ANumber o operating cycles in 40 years 1 27 27Number o additional uel assemblies or tritium1512 N/A Number o ISFSI dry cass needed to store uel assemblies due to tritium production actiities 63 0 Number o uel assemblies or 40 year operation 2160 2160 Number o ISFSI dry cass needed to store uel assemblies or spent uel pool (SFP) capacity shortall, 2 3 27 90 Number o ISFSI dry cass needed to store uel or each unit.

b 90 90 Total number of SFS dry cass required for W site, to-unit oeration 1 1Forty years o operation coers 26 reueling outages and 27 operating cycles. Spent uel is discharged 27 times rom each unit.

2Number is based on 24 uel assembly cas designs.

3SFP capacity shortall is based on eisting SFP usable capacity o 1363 storage cells. The number o cass tabulated aboe or Unit 1 SFP capacity shortall has been reduced rom leel proected in the CLWR FEIS to relect actual tritium generation rates o uel assemblies being less than originally estimated (56). A number o ISFSI dry storage designs hae been licensed by the NRC and are in operation in the United States, including acilities at TVAs SN and BFN. Licensed designs include the metal cass and concrete cass. The maority o these operating ISFSIs use concrete cass. Concrete cass consist o either a ertical or a horizontal concrete structure housing a baset and metal cas that conines the spent nuclear uel.

Currently, there are three endors with concrete pressurized water reactor spent nuclear uel dry cas designs licensed in the United States, Holtec International, NAC International, and Transnuclear Inc. The Holtec International and NAC International designs are ertical concrete cylinders whereas, the Transnuclear design is a rectangular concrete bloc. These designs store arying numbers o spent nuclear uel assemblies, ranging rom 24 to 37. Howeer, since the Holtec design is currently being used at TVAs SN and is representatie o all other designs, the enironmental impact o using the Holtec concrete dry storage ISFSI design has been addressed. As stated aboe, although the multipurpose canister (MPC)-32 is being used at SN, this update has taen a more conseratie approach using the MPC-24, since it would reuire more cass and correspondingly more concrete and steel. The enironmental analysis o spent uel storage in the CLWR FEIS, which ocused on dry storage cass, is still alid. The ollowing sections update inormation about the euipment Chapter 3 Final Supplemental Enironmental Impact Statement 97endors and processes currently used at WBN and proide analysis o the eects o completing WBN Unit 2 on spent uel storage construction and operation. 3.15.1. I The CLWR FEIS describes a NUHOMS-24P horizontal spent uel storage module. Currently, HI-STORM ertical storage modules are used at SN. For the purposes o this analysis, it is assumed that the same type o storage modules would be used at WBN. The modules used at SN consist o cylindrical structure with inner and outer steel shells illed with concrete. The stainless steel MPC that contains the spent uel assemblies is placed inside the ertical storage module. The MPC is abricated o site. The spent uel storage site described or WBN Unit 1 in the CLWR FEIS was proposed to contain 63 spent nuclear uel cass (see Table 3-25). Using the SN ISFSI as a basis or calculating an appropriately sized pad, an area o approimately 55,800 suare eet would be needed to store the 180 cass reuired to support a two-unit operation at WBN or 40 years. Assuming a proportionate ratio o area reuired or construction disturbance, nuisance encing, and transport actiities, a proected net disturbed area o approimately 2.2 acres would be reuired. The dierences between constructions o an ISFSI or Unit 1 alone as compared to an ISFSI that would sere two units are shown in Table 3-26.

Construction and installation o the HI-STORM modules would be similar to that described in the CLWR FEIS or the NUHOMS-24P, as would be the enironmental eects. There is ample room at the WBN site to locate a storage acility. Table 3-2. SFS Construction for Watts ar uclear Plant Unit 1 as Comared to Construction of oth Units 1 and 2 nironmental Parameter Unit 1 (from 1 CLWR FS)Units 1 2 Eternal appearance 63 Horizontal storage modules Rectangular cubes 19 9.7 eet constructed on three concrete cas oundation pads approimately 116.4 38 eet 180 Vertical cylindrical storage modules (cass) placed on a concrete cas oundation pad o an approimate area o 55,800 suare eet and 2 eet thic. Each cas would be a nominal 12 eet in diameter and 21 eet tall.Health and saety (only construction wor perormed subseuent to the loading o any storage modules with spent uel may result in worer eposures rom direct and syshine radiation in the icinity o the loaded horizontal storage modules) Dose rate 0.5 mrem per hour 1Total dose during construction 47.25 person-remDose Rate 0.5 mrem per hour 1Total dose during construction 135 person-remSize o disturbed area ISFSI ootprint 1.3 acres Disturbed 5.3 acres ISFSI ootprint 1.3 acres Disturbed 2.2 acres Materials (approimate) Concrete 10,618 tons Steel 1,208 tons Concrete 27,675 tons Steel 3150 tons 1 DOE 1999 Completion and Operation o Watts Bar Nuclear Plant Unit 2 Final Supplemental Enironmental Impact Statement 983.15.2. I The NUHOMS horizontal storage module dry cas system described in the CLWR FEIS was designed and licensed to remoe up to 24 ilowatts (W) o decay heat saely rom spent uel by natural air conection. The Holtec HI-STORM dry cas storage system currently in use at SN is licensed to remoe up to 28 W o decay heat saely.

Conseratie calculations hae shown that, or 24 W o decay heat, air entering the cas at a temperature o 70F would be heated to a temperature o 161F. For a 28-W maimum heat load, and assuming similar air mass low rate through the cooling ents, the resulting temperature would be approimately 176F. The enironmental impact o the discharge o this amount o heat can be compared to the heat (336 W) emitted to the atmosphere by an automobile with a 150brae horsepower engine (Bosch 1976). The heat released by an aerage automobile is the euialent o as ew as 12 ISFSI cass at their design maimum heat load o 28 W. Thereore, the decay heat released to the atmosphere rom the spent nuclear uel ISFSI is euialent to the heat released to the atmosphere rom approimately 15 aerage cars. SN has proposed and the NRC is reiewing the use o storage cass with a licensed maimum heat load o up to 40 W. The use o this higher allowable maimum heat load cas would result in an increase rom the alues reported in the paragraph aboe. For eample, or a 40 W maimum heat load, and assuming similar air mass low rate through the cooling ents results in a proected temperature o approimately 221F. The heat released by an aerage automobile is the euialent o as ew as nine ISFSI cass at their proposed higher design maimum heat load o 40 W. The decay heat released to the atmosphere rom the spent nuclear uel ISFSI would be euialent to the heat released to the atmosphere rom approimately 20 aerage cars. I approed, this type o cas could be used at WBN. The CLWR FEIS concluded that the heat emitted rom the WBN ISFSI would hae no eect on the enironment or climate because o its small magnitude. Although an ISFSI large enough to accommodate two-unit spent uel storage would emit somewhat more heat, the amount is still negligible.The heat emitted by the ully loaded, largest proected ISFSI, een at the maimum design-licensed decay heat leel or each cas o 28 W, would be approimately 5000 W (i.e., 180 cass 28 W = 5040 W or 5.04 MW), as compared to 2000 W or the system analyzed in 1999. This increase o 3000 W o heat added to the atmosphere is not large enough to change the conclusion that this amount o heat is about

0.1 percent

the heat released to the enironment rom any o the proposed nuclear power plantson the order o 2,400,000 W or each operating nuclear reactor. The actual decay heat rom spent nuclear uel in the ISFSI should be lower than 5000 W and would decay with time due to the natural decay o ission products in the spent nuclear uel. As stated in the CLWR FEIS, the incremental loading o the ISFSI oer a 40-year period would not generate the ull ISFSI heat until 40 years ater the initial operation. The proposed use o cass with higher allowable maimum heat load (40 W) would result in an increase rom the alues reported aboe. For eample, or a 40-W maimum heat load, a site total o 7200 W would represent about 0.15 percent o the heat released to the enironment rom any o the proposed nuclear power plants. Thereore, or the proposed 40-W cas design, no noticeable eects on the enironment or climate would be epected. The dierences between the operation o an ISFSI or Unit 1 alone as compared to an ISFSI that would sere two units are shown in Table 3-27. TVA has concluded that due to the small magnitude o the total potential dose, the radiation dose to worers rom ISFSI Chapter 3 Final Supplemental Enironmental Impact Statement 99operation would be minor. In general,the operational eects o the HI-STORM modules would be similar to that described in the CLWR FEIS or the NUHOMS-24P, as would be the enironmental eects. Table 3-2. SFS Oeration for Watts ar uclear Plant Unit 1 as Comared to Oeration of oth Units 1 and 2 nironmental ParameterUnit 1 (from CLWR FS)

Units 1 and 2Eects o operation o the heat dissipation system Euialent to heat emitted into the atmosphere by approimately 2-6 aeraged-sized cars. Euialent to heat emitted into the atmosphere by approimately 15 aerage size cars, or 20 cars i the higher maimum heat load cas proposed at SN is used. Facility water use Transer cas decontamination water consumption o less than 946 cubic eet. Transer cas decontamination water consumption o less than 2703 cubic eet. Radiological impact rom routine operation Worer eposure As the result o daily inspection o cass, during a 40-year lie cycle, worers would be eposed to 58.8 person-rem. Public eposure The regulatory limit or public eposure is 25 mrem per year. Doses receied by a member o the public liing in the icinity o the ISFSI would be well below the regulatory reuirements. Worer eposure As the result o daily inspection o cass, during a 40-year lie cycle, worers would be eposed to 168 person-rem. Public eposure The regulatory limit or public eposure is 25 mrem per year. Doses receied by a member o the public liing in the icinity o the ISFSI would be well below the regulatory reuirements. Radwaste and

source termsCas loading and decontamination operation generates less than 126 cubic eet o low-leel radioactie waste. Cas loading and decontamination operation generates less than 360 cubic eet o low-leel radioactie waste.

Climatological impactSmall (less than 0.1 percent o the nuclear power plants heat emission to the atmosphere) Small (approimately 0.1 percent o the nuclear power plants heat emission to the atmosphere, or approimately .15 percent i 40 W cas are used)Impact o runo rom operation The horizontal storage module surace is not contaminated. No contaminated runo is epected. The storage cas surace is not contaminated. No contaminated runo is epected. 3.15.3. A The CLWR FEIS analyzed the postulated accidents that could occur at an ISFSI and concluded that the potential radiological releases would all be well within regulatory limits.

The impact o the calculated doses, which were approimately 50 mrem or less or dierent scenarios, were compared with the natural radiation dose o about 300 mrem annually receied by each person in the United States (DOE 1999). The storage cass proposed or use at WBN or a two-unit operation would be o similar or better design than those analyzed in the mid-1990s, and any accident doses resulting rom such a postulated eent would be consistent with doses preiously determined. 3.1. Transortation of Radioactie aterials The eects o transporting nuclear uels and radioactie wastes are addressed in the 1972 FES. The 1995 FSER addressed the transportation o spent uels and radioactie waste. The transportation o radioactie waste and spent uel are addressed briely in Section 3.14 and 3.15 o this document. The 1972 FES analysis was based on the annual shipment o about 100 tons o natural uranium. Analysis was based on 30 years o plant operation with annual reueling. As the FES eplained, relatiely low leels o radiation are emitted rom Completion and Operation o Watts Bar Nuclear Plant Unit 2 Final Supplemental Enironmental Impact Statement 100unirradiated new uel assemblies. Thereore, the only eposure to people rom the routine shipment o new uel would be in direct iew and to the indiidual truc driers assigned.

The eposure in the cab o the uel transport truc was estimated to be 0.1 mrem per hour, and eposure to transportation personnel was estimated to be less than 1 mrem per shipment. This leel would not cause any aderse eects. The FES also discussed accident potential, concluding that there would be no signiicant enironmental riss rom radiation resulting rom an accident inoling a shipment o new uel (TVA 1972). In the reiew o the FES, TVA concluded that the analysis o new uel shipments in the 1972 FES was still alid at that time (TVA 1993a). When TVA applied or an operating license or WBN Unit 1, plans were or 40 years o operations, with reueling to occur eery 18 months. The 1995 NRC FES stated that the proposed changes would result in a slight reduction in uel usage as compared to the original application and that the changes would not alter the conclusion that the dose and potential health eects would be small compared to the eects o natural radiation doses (NRC 1995a). Currently, 54 tons o new uel is shipped annually to WBN Unit 1. I WBN Unit 2 were completed, or two-unit operation, there would be our reloads in three years, which would wor out to 107 tons shipped annually. The 1972 FES indicated that uel would most liely be shipped by truc, although transport by barge or rail was also considered. An estimated 10 shipments per year were epected, with up to seen shipping containers per load, each containing two uel assemblies or a maimum o 14 assemblies per truc shipment. The FES discussed si shipping routes. Currently, TVA receies seen shipments per reload with a maimum number o assemblies per truc o 12, paced in si shipping containers.

Westinghouse is deeloping new shipping containers and will only be able to ship 10 assemblies per truc in 10 shipping containers. They epect to be reuired to start using the new containers in 2009.

The (AEC 1972) and 1 (NRC 1975) ealuated the enironmental eects o transportation o uel and waste or light water reactors and ound the impacts to be small.

These analyses proided the basis or Table S-4 in 10 CFR 51.52, which summarizes the enironmental impacts o transportation o uel and radioactie wastes to and rom a reerence reactor. Both normal conditions o transport and accidents are addressed in the table.Subparagraph 10 CFR 51.52(a)(5) reuires that unirradiated uel be shipped to the reactor site by truc. A condition that the truc shipments not eceed 73,000 pounds as goerned by ederal or state gross ehicle weight restrictions is included in Table S-4. New uel assemblies would be transported to WBN Units 1 and 2 by truc rom a uel abrication acility, in accordance with U.S. Department o Transportation and NRC regulations. The initial uel loading or Unit 2 would consist o 193 uel assemblies. Eery 18 months, reueling would reuire an aerage o 80 uel assemblies. The uel assemblies, which are abricated at a uel abrication plant, would be shipped by truc to WBN shortly beore they are reuired. Truc shipments would not eceed the applicable ederal or state gross ehicle weight. I WBN Unit 2 were completed, TVA would comply with all NRC, state, and ederal reuirements or transport o unirradiated uel, as it does with uel delieries or Unit 1. The impacts o such delieries on human health and the enironment are epected to be

minimal.

Chapter 3 Final Supplemental Enironmental Impact Statement 1013.1. Decommissioning Post-operational impact considerations were addressed in the 1972 FES (TVA 1972) under short-term ersus long-term productiity and irreersible and irretrieable commitment o resources. Decommissioning is also addressed in the 1995 NRC FES (NRC 1995a) and TVAs 1995 FSER (TVA 1995b). As these documents eplain, at the end o the operating lie o the WBN units, TVA would see the termination o its operating license rom NRC.

Termination reuires that the units be decommissioned, a process that ensures the units are saely remoed rom serice and the site made sae or unrestricted use. Consistent

with the 1995 FSER, TVA is not proposing a decommissioning plan now. A decommissioning plan would be deeloped or approal by NRC, with appropriate enironmental reiews, when TVA applies or decommissioning o these units in the uture.

ethodsThe three NRC-approed methods o decommissioning nuclear power acilities described in the 1995 FSER are still iable alternaties. These are 1.DCO. The DECON option calls or the prompt remoal o radioactie material at the end o the plant lie. Under DECON, all uel assemblies, nuclear source material, radioactie ission and corrosion products, and all other radioactie and contaminated materials aboe NRC-restricted release leels are remoed rom the plant. The reactor pressure essel and internals would be remoed along with remoal and demolition o

the remaining systems, structures, and components with contamination control employed as reuired. This is the most epensie o the three options.

2.SAFSTOR. SAFSTOR is a deerred decontamination strategy that taes adantage o the natural dissipation o almost all o the radiation. Ater all uel assemblies, nuclear source material, radioactie liuid, and solid wastes are remoed rom the plant, the

remaining physical structure would then be secured and mothballed. Monitoring systems would be used throughout the dormancy period and a ull-time security orce would be maintained. The acility would be decontaminated to NRC-unrestricted release leels ater a period o up to 60 years, and the site would be released or unrestricted use. Although this option maes the site unaailable or alternate uses or an etended period, worer and public doses would be much smaller than under DECON, as would the need or radioactie waste disposal.

3.TO. As the name implies, this method inoles encasing all radioactie materials on site rather than remoing them. Under ENTOMB, radioactie structures, systems, and components are encased in a structurally long-lied substance, such as concrete.

The entombed structure is appropriately maintained and monitored until radioactiity decays to a leel that permits termination o the license. This option reduces worer and public doses, but because most power reactors will hae radionuclides in concentrations eceeding the limits or unrestricted use een ater 100 years, this option may not be easible under current regulation. It is epected that by the time WBN is decommissioned, new, improed technologies, including use o robotics, will hae been deeloped and approed by NRC.

CostIn 1995, NRC estimated that it would cost up to 200 million to decommission a pressurized water reactor lie WBN Units 1 and 2. NRC currently estimates that decommissioning Completion and Operation o Watts Bar Nuclear Plant Unit 2 Final Supplemental Enironmental Impact Statement 102would cost up to 366 million in todays dollars. TVA maintains a nuclear decommissioning trust to proide money or the ultimate decommissioning o its nuclear power plants. The und is inested in securities generally designed to achiee a return in line with oerall euity maret perormance. In une 1994, this und had accumulated 50 million. Since then, unds hae been accumulated to coer the cost o decommissioning TVAs operating nuclear units. The assets o the decommissioning trust und as o December 31, 2006, totaled 1004 million. This balance is greater than the present alue o the estimated uture nuclear decommissioning costs or TVAs operating nuclear units. The present alue is calculated by escalating the decommissioning cost in todays dollars by 4 percent per year through decommissioning. This liability is then discounted at a 5 percent real rate o return. This euates into an estimated decommissioning liability present alue o 699 million at calendar year end 2006. TVA monitors the assets o its nuclear decommissioning trust ersus the present alue o its liabilities and beliees that, oer the long term and beore cessation o nuclear plant operations and commencement o decommissioning actiities, adeuate unds rom inestments will be aailable to support decommissioning. At the time WBN Unit 2 commences operation, TVA would create a separate trust account or the unit within the decommissioning trust und and would mae any necessary contributions to the und to coer the costs o uture decommissioning. Potential macts to the nironment Enironmental issues associated with decommissioning were analyzed in the , NUREG1437 (NRC 1996a 1999). The generic enironmental impact statement included a determination o whether the analysis o the enironmental issue could be applied to all plants and whether additional mitigation measures would be warranted. Issues were sorted into two categories. For those issues meeting Category 1 criteria, no additional plant-speciic analysis is reuired by NRC, unless new and signiicant inormation is identiied. Category 2 issues are those that do not meet one or more o the criteria o Category 1 and thereore reuire additional plant-speciic reiew. Enironmental analysis o the uture decommissioning plan or WBN would tier rom this or the appropriate NRC document in eect at the time. TVA has not identiied any signiicant new inormation during this enironmental reiew that would indicate the potential or decommissioning impacts not preiously reiewed.

Thereore, TVA does not at this time anticipate any aderse eects rom the decommissioning process. As stated earlier, urther enironmental reiews would be conducted at the time a decommissioning plan or WBN is proposed. Response to FSAR Chapter 11 and FSEIS, Chapter 3 Request For Additional Information List of Commitments 1. Because TVA will not meet all 10 CFR 50, Appendix I addendum RM 50-2 dose limits for the site, TVA will complete a Cost Benefit Analysis per Regulatory Guide

1.110 by July 29, 2011. 2. TVA also received additional request for information at a public meeting on May 11, 2011, regarding inputs for the dose calculations. This additional information will be provided by May 27, 2011. 3. The proposed FSAR revision (Enclosure 2, Attachment 3) will be included in FSAR Amendment A104. 4. The proposed FSEIS revisions will be issued by June 10, 2011.