ML11166A154

OL - Chapter 11 FSAR RAI Response

ML11166A154
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Site:	Watts Bar
Issue date:	05/23/2011
From:	- No Known Affiliation
To:	Division of Operating Reactor Licensing
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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, Here is the Chapter 11 FSAR RAI Response As always, please call us if you should have any questions, Rickey Stockton Unit 2 Licensing (423) 365-7741 1

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 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 , Attachments 2 through 5. , 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 TVAs 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

Enclosure 1 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 1 The 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 NRCs draft EIS.

TVA Response Land 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.

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ENCLOSURE 1 WATTS BAR NUCLEAR PLANT UNIT 2 RESPONSE TO FINAL SAFETY ANALYSIS REPORT CHAPTER 11 AND FSEIS CHAPTER 3 REQUEST FOR ADDITIONAL INFORMATION Unit 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 2 TVA 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 TVAs 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 Response There are multiple parts to this requested clarification. Numbering has been added to the individual parts. The individual questions and answers are provided below.

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ENCLOSURE 1 WATTS BAR NUCLEAR PLANT UNIT 2 RESPONSE TO FINAL SAFETY ANALYSIS REPORT CHAPTER 11 AND FSEIS CHAPTER 3 REQUEST FOR ADDITIONAL INFORMATION

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.

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 of TVAs 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 TVAs 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 TVAs 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 , 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.

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ENCLOSURE 1 WATTS BAR NUCLEAR PLANT UNIT 2 RESPONSE TO FINAL SAFETY ANALYSIS REPORT CHAPTER 11 AND FSEIS CHAPTER 3 REQUEST FOR ADDITIONAL INFORMATION Response 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.

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Enclosure 1, 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 Ta le 11 3 Design For 1 Failed Fuel E pected Gas Release Concentration Effluent Concentration Limit Wit Continuous Filtered Containment Vent S eet 1 of 2 Exp. 10CFR Single Unit Dual Unit Des/Ex Design Design( Ci/c Rel. 20 Operation Operation p (Ci/yr) c)

(Ci/yr) (ECL) C/ECL C/ECL r-85m 9.48E 00 12.28 1.16E 02 4.02E-11 1.0E-07 0.0004024 0.0008048 r-85 6.78E 02 33.08 2.24E 04 7.75E-09 7.0E-07 0.0110743 0.0221486 r-87 5.81E 00 7.45 4.33E 01 1.50E-11 2.0E-08 0.0007480 0.0014960 r-88 1.32E 01 12.33 1.63E 02 5.63E-11 9.0E-09 0.0062505 0.0125010 Xe-131m 1.09E 03 2.91 3.18E 03 1.10E-09 2.0E-06 0.0005489 0.0010978 Xe-133m 4.31E 01 43.24 1.86E 03 6.44E-10 6.0E-07 0.0010735 0.0021470 Xe-133 2.90E 03 111.07 3.22E 05 1.11E-07 5.0E-07 0.2227110 0.4454220 Xe-135m 4.68E 00 5.04 2.36E 01 8.15E-12 4.0E-08 0.0002038 0.0004076 Xe-135 8.88E 01 6.97 6.19E 02 2.14E-10 7.0E-08 0.0030561 0.0061122 Xe-138 4.34E 00 5.43 2.36E 01 8.15E-12 2.0E-08 0.0004073 0.0008146 Br-84 5.07E-02 2.50 1.27E-01 4.38E-14 8.0E-08 0.0000005 0.0000010 I-131 1.53E-01 52.41 8.00E 00 2.77E-12 2.0E-10 0.0138277 0.0276554 I-132 6.73E-01 4.00 2.69E 00 9.30E-13 2.0E-08 0.0000465 0.0000930 I-133 4.57E-01 26.85 1.23E 01 4.24E-12 1.0E-09 0.0042433 0.0084866 I-134 1.07E 00 1.65 1.77E 00 6.10E-13 6.0E-08 0.0000102 0.0000204 I-135 8.42E-01 7.91 6.66E 00 2.30E-12 6.0E-09 0.0003837 0.0007674 Cs-134 2.27E-03 40.60 9.20E-02 3.18E-14 2.0E-10 0.0001589 0.0003178 Cs-136 8.01E-05 165.20 1.32E-02 4.57E-15 9.0E-10 0.0000051 0.0000102 Cs-137 3.48E-03 153.22 5.33E-01 1.84E-13 2.0E-10 0.0009203 0.0018406 Cr-51 5.92E-04 0.29 1.73E-04 5.96E-17 3.0E-08 0.0000000 0.0000000 n-54 4.31E-04 0.47 2.03E-04 7.01E-17 1.0E-09 0.0000001 0.0000002 Fe-59 7.70E-05 3.48 2.68E-04 9.27E-17 5.0E-10 0.0000002 0.0000004 Co-58 2.32E-02 5.37 1.24E-01 4.30E-14 1.0E-09 0.0000430 0.0000860 Co-60 8.74E-03 1.38 1.21E-02 4.17E-15 5.0E-11 0.0000833 0.0001666 Sr-89 2.98E-03 22.45 6.69E-02 2.31E-14 1.0E-09 0.0000231 0.0000462 Sr-90 1.14E-03 13.49 1.54E-02 5.33E-15 6.0E-12 0.0008877 0.0017754 r-95 1.00E-03 1.71 1.71E-03 5.92E-16 4.0E-10 0.0000015 0.0000030 Nb-95 2.45E-03 2.34 5.73E-03 1.98E-15 2.0E-09 0.0000010 0.0000020 Ba-140 4.00E-04 0.31 1.26E-04 4.34E-17 2.0E-09 0.0000000 0.0000000

-3 1.39E 02 1 1.39E 02 4.80E-11 1.0E-07 0.0004811 0.0009622

-3 (TPC) 3.70E 02 1 3.70E 02 1.28E-10 1.0E-07 0.0012775 0.0012775 1 rod 1.53E 03 1 1.53E 03 5.29E-10 1.0E-07 0.0052869 0.0052869 2 rod 2.69E 03 1 2.69E 03 9.30E-10 1.0E-07 0.0092962 0.0092962 C-14 7.30E 00 1 7.30E 00 2.52E-12 3.0E-09 0.0008410 0.0016820 Ar-41 3.40E 01 1 3.40E 01 1.18E-11 1.0E-08 0.0011752 0.0023504 Total 0.2696131 0.5392262 Total (TPC) 0.2704095 0.5400226 1 rod 0.2744189 0.5440320 2 rod 0.2784283 0.5480413

FSAR Ta le 11 3 Design For 1 Failed Fuel E pected Gas Release Concentration Effluent Concentration Limit Wit Continuous Filtered Containment Vent S eet 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 Ta le 11 3 c Total Releases ased on ANSI 1 1 1 in Ci r it Continuous Filtered Containment Vent S eet 1 of 1 Table based on operation of one unit Nuclide Containment Auxiliary Turbine Total Building Building Building r-85m 3.72E 00 4.53E 00 1.23E 00 9.48E 00 r-85 6.69E 02 7.05E 00 1.86E 00 6.78E 02 r-87 4.48E-01 4.27E 00 1.09E 00 5.81E 00 r-88 3.10E 00 7.95E 00 2.13E 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-41 3.40E 01 0.00E 00 0.00E 00 3.40E 01 Br-84 8.16E-07 5.02E-02 4.81E-04 5.07E-02 I-131 6.74E-03 1.39E-01 7.08E-03 1.53E-01 I-132 1.36E-04 6.56E-01 1.70E-02 6.73E-01 I-133 2.36E-03 4.35E-01 2.03E-02 4.57E-01 I-134 4.26E-05 1.06E 00 1.47E-02 1.07E 00 I-135 8.80E-04 8.10E-01 3.13E-02 8.42E-01

-3 1.39E 02 0.00E 00 0.00E 00 1.39E 02 Cr-51 9.21E-05 5.00E-04 0.00E 00 5.92E-04 n-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 r-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 Ru-103 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 3.95E-05 C-14 2.80E 00 4.50E 00 0.00E 00 7.30E 00

FSAR Ta le 11 3 Data On Points Of Interest Near Watts Bar Nuclear Plant Page 1 of 2 Sector Distance Chi-over D-over-Q Terrain ilk

( eters) (s/m 3) (1/m 2) Adjustment Feeding Factor Factor Unrestricted Area Boundary N 1550 5.12e-06 8.13e-09 1.70 Unrestricted Area Boundary NNE 1980 6.35e-06 1.23e-08 1.80 Unrestricted Area Boundary NE 1580 1.05e-05 1.10e-08 2.10 Unrestricted Area Boundary ENE 1370 1.23e-05 8.77e-09 1.70 Unrestricted Area Boundary E 1280 1.37e-05 9.66e-09 1.60 Unrestricted Area Boundary ESE 1250 1.43e-05 1.16e-08 1.80 Unrestricted Area Boundary SE 1250 1.11e-05 9.49e-09 1.50 Unrestricted Area Boundary SSE 1250 6.04e-06 8.21e-09 1.50 Unrestricted Area Boundary S 1340 5.33e-06 1.17e-08 1.90 Unrestricted Area Boundary SSW 1550 4.14e-06 1.05e-08 2.00 Unrestricted Area Boundary SW 1670 4.46e-06 7.34e-09 2.10 Unrestricted Area Boundary WSW 1430 5.47e-06 6.37e-09 1.80 Unrestricted Area Boundary W 1460 2.11e-06 2.07e-09 1.20 Unrestricted Area Boundary WNW 1400 2.49e-06 2.38e-09 2.50 Unrestricted Area Boundary NW 1400 2.05e-06 2.13e-09 1.70 Unrestricted Area Boundary NNW 1460 2.68e-06 3.08e-09 1.60 Nearest Resident N 2134 2.84e-06 4.21e-09 1.50 Nearest Resident NNE 3600 2.69e-06 4.41e-09 1.80 Nearest Resident NE 3353 3.84e-06 3.22e-09 2.20 Nearest Resident ENE 2414 6.26e-06 3.83e-09 1.90 Nearest Resident E 3268 3.97e-06 2.14e-09 1.70 Nearest Resident ESE 4416 2.64e-06 1.46e-09 1.90 Nearest Resident SE 1372 9.66e-06 8.16e-09 1.50 Nearest Resident SSE 1524 4.18e-06 5.56e-09 1.40 Nearest Resident S 1585 3.91e-06 8.42e-09 1.80 Nearest Resident SSW 1979 2.76e-06 6.64e-09 1.90 Nearest Resident SW 4230 1.15e-06 1.43e-09 2.00 Nearest Resident WSW 1829 3.61e-06 4.03e-09 1.70 Nearest Resident W 2896 7.30e-07 6.01e-10 1.10 Nearest Resident WNW 1646 2.26e-06 2.12e-09 2.90 Nearest Resident NW 2061 1.03e-06 9.95e-10 1.50 Nearest Resident NNW 4389 3.50e-07 2.97e-10 1.00 Nearest Garden N 7664 3.13e-07 3.00e-10 1.00 Nearest Garden NNE 6173 1.06e-06 1.42e-09 1.50 Nearest Garden NE 3353 3.84e-06 3.22e-09 2.20 Nearest Garden ENE 4927 2.01e-06 9.39e-10 1.60 Nearest Garden E 6372 1.35e-06 5.42e-10 1.40 Nearest Garden ESE 4758 2.26e-06 1.21e-09 1.80 Nearest Garden SE 4633 1.58e-06 8.97e-10 1.30 Nearest Garden SSE 7454 3.73e-07 2.80e-10 1.10 Nearest Garden S 2254 2.50e-06 4.94e-09 1.90

FSAR Ta le 11 3 Data On Points Of Interest Near Watts Bar Nuclear Plant Page 2 of 2 Sector Distance Chi-over D-over-Q Terrain ilk

( eters) (s/m 3) (1/m 2) Adjustment Feeding Factor Factor Nearest Garden SSW 1979 2.76e-06 6.64e-09 1.90 Nearest Garden SW 8100 4.28e-07 4.03e-10 1.80 Nearest Garden WSW 4667 8.70e-07 7.11e-10 1.50 Nearest Garden W 5120 3.03e-07 2.03e-10 1.00 Nearest Garden WNW 5909 1.72e-07 1.05e-10 1.30 Nearest Garden NW 3170 4.13e-06 3.50e-10 1.10 Nearest Garden NNW 4602 3.28e-07 2.74e-10 1.00 ilk Cow ESE 6706 1.35e-06 6.18e-10 1.70 0.65 ilk Cow SSW 2286 2.24e-06 5.20e-09 1.90 0.65 ilk Cow SSW 3353 1.36e-06 2.84e-09 2.00 0.65

FSAR Ta le 11 3 1 Watts Bar Nuclear Plant Indi idual Doses From Gaseous Effluents For 1 Unit it out TPC Effluent Pathway Guideline Location Dose Noble Gases J Air dose 10 mrad aximum Exposed 0.801 mrad/yr Individual1 E Air dose 20 mrad aximum Exposed 2.710 mrad/yr Individual1 Total body 5 mrem aximum 0.571 mrem/yr Residence2,3 Iodines/ Skin 15 mrem aximum 1.540 mrem/yr Particulate Residence2,3 Bone 15 mrem aximum Real 9.15 mrem/yr (critical organ) Pathway4 Breakdown of Iodine/Particulate Doses (mrem/yr)

Total Vegetable 6.57 Ingestion Inhalation 0.0704 Ground Contamination 0.0947 Submersion 0.130 Beef Ingestion5 2.28 Total 9.145 mrem/yr Guidelines are defined in Appendix I to 10 CFR Part 50.

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

2 Dose from air submersion.

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

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

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

FSAR Ta le 11 3 11 Summar of Population Doses THYROID Infant Child Teen Adult Total Submersion 1.26e-02 1.41e-01 1.28e-01 5.57e-01 8.38e-01 Ground 2.31e-03 2.59e-02 2.36e-02 1.03e-01 1.54e-01 Inhalation 6.62e-02 1.24e 00 6.64e-01 2.36e 00 4.33e-00 Cow ilk 3.22e-01 1.57e 00 6.63e-01 1.25e 00 3.81e 00 Ingestion Beef Ingestion 0.00e 00 3.17e-01 1.59e-01 8.04e-01 1.28e 00 Vegetable 0.00e 00 1.04e 00 4.16e-01 1.09e 00 2.55e 00 Ingestion Total man-rem 4.04e-01 4.34e 00 2.05e 00 6.17e 00 1.30e 01 TOTAL BODY Infant Child Teen Adult Total Submersion 1.26e-02 1.41e-01 1.28e-01 5.57e-01 8.38e-01 Ground 2.31e-03 2.59e-02 2.36e-02 1.03e-01 1.54e-01 Inhalation 3.93e-03 1.05e-01 6.65e-02 2.76e-01 4.52e-01 Cow ilk 1.04e-01 5.73e-01 2.17e-01 3.85e-01 1.28e 00 Ingestion Beef Ingestion 0.00e 00 3.06e-01 1.53e-01 7.74e-01 1.23e 00 Vegetable 0.00e 00 1.05e 00 4.40e-01 1.21e 00 2.70e 00 Ingestion Total man-rem 1.23e-01 2.20e 00 1.03e 00 3.31e 00 6.66e 00

Completion and peration of Watts Bar Nuclear Plant Unit 2 FSEIS Ta le 3 1 Receptors from Actual Land Use Sur e Results Used for Potential Gaseous Releases From WBN Unit 2 Receptor Receptor Distance Sector Num er T pe meters

1. Nearest Resident N 2134

2. Nearest Resident NNE 3600

3. Nearest Resident NE 3353

4. Nearest Resident ENE 2414

5. Nearest Resident E 3268

6. Nearest Resident ESE 4416

7. Nearest Resident SE 1372

8. Nearest Resident SSE 1524

9. Nearest Resident S 1585

10. Nearest Resident SSW 1979

11. Nearest Resident SW 4230

12. Nearest Resident WSW 1829

13. Nearest Resident W 2896

14. Nearest Resident WNW 1646

15. Nearest Resident NW 2061

16. Nearest Resident NNW 4389

17. Nearest Garden N 7664

18. Nearest Garden NNE 6173

19. Nearest Garden NE 3353

20. Nearest Garden ENE 4927

21. Nearest Garden E 6372

22. Nearest Garden ESE 4758

23. Nearest Garden SE 4633

24. Nearest Garden SSE 7454

25. Nearest Garden S 2254

26. Nearest Garden SSW 1979

27. Nearest Garden SW 8100

28. Nearest Garden WSW 4667

29. Nearest Garden W 5120

30. Nearest Garden WNW 5909

31. Nearest Garden NW 3170

32. Nearest Garden NNW 4602

33. ilk Cow ESE 6706

34. ilk Cow SSW 2286

35. ilk Cow SSW 3353 86 Final Supplemental Environmental Impact Statement

Chapter 3 FSEIS Ta le 3 2 WBN Total annual Gaseous disc arge Per Operating Unit curies ear reactor Containment Au iliar Tur ine Nuclide Total Building Building Building r-85m 3.72E 00 4.53E 00 1.23E 00 9.48E 00 r-85 6.69E 02 7.05E 00 1.86E 00 6.78E 02 r-87 4.48E-01 4.27E 00 1.09E 00 5.81E 00 r-88 3.10E 00 7.95E 00 2.13E 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-41 3.40E 01 0.00E 00 0.00E 00 3.40E 01 Br-84 8.16E-07 5.02E-02 4.81E-04 5.07E-02 I-131 6.74E-03 1.39E-01 7.08E-03 1.53E-01 I-132 1.36E-04 6.56E-01 1.70E-02 6.73E-01 I-133 2.36E-03 4.35E-01 2.03E-02 4.57E-01 I-134 4.26E-05 1.06E 00 1.47E-02 1.07E 00 I-135 8.80E-04 8.10E-01 3.13E-02 8.42E-01

-3 1.39E 02 0.00E 00 0.00E 00 1.39E 02

-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 n-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 r-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 Ru-103 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 3.95E-05 C-14 2.80E 00 4.50E 00 0.00E 00 7.30E 00 Final 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 Ta le 3 21 WBN Doses From Gaseous Effluent for Unit 2 Wit out Tritium Production for Year 2 Effluent Pat a Guideline Location Dose aximum Exposed Noble Gases  Air dose 10 mrad 0.801 mrad/year Individual1 aximum Exposed

 Air dose 20 mrad 2.710 mrad/year Individual1 Total body 5 mrem aximum Residence2,3 0.571 mrem/year Iodines/

Skin 15 mrem aximum Residence2,3 1.540 mrem/year Particulate Bone 9.15 mrem/year 15 mrem aximum Real Pathway4 (critical organ)

Breakdown of Iodine/Particulate Doses (mrem/yr)

Total Vegetable Ingestion 6.57 Inhalation 0.0704 Ground Contamination 0.0947 Submersion 0.130 Beef Ingestion5 2.28 Total 9.145 Guidelines are defined in Appendix I to 10 CFR Part 50.

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

2 Dose from air submersion.

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

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

5 aximum 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, and 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

Enclosure 1, 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 TVAs 2/25/2011 letter (Reference 4),

FSEIS Table 3-16, FSAR Tables 11.2-5 and 11.2-7)

E cerpt from TVA Letter to NRC dated Fe ruar 2 2 11 Liquid Source Term Ta le from Response to NRC Question 3c Single Unit Liquid Single Unit Steam Generator Single Unit Totals Nuclide Rad aste Ci r Blo do n Ci r Ci r Br-84 1.65E-04 5.23E-04 6.88E-04 I-131 2.63E-02 1.14E 00 1.16E 00 I-132 1.32E-02 1.08E-01 1.21E-01 I-133 5.29E-02 8.57E-01 9.10E-01 I-134 6.26E-03 2.65E-02 3.28E-02 I-135 4.75E-02 4.22E-01 4.70E-01 Rb-88 6.89E-03 7.84E-04 7.68E-03 Cs-134 2.93E-02 1.68E-01 1.98E-01 Cs-136 2.55E-03 1.72E-02 1.98E-02 Cs-137 4.03E-02 2.21E-01 2.61E-01 Na-24 1.86E-02 0.0E 00 1.86E-02 Cr-51 7.03E-03 9.27E-02 9.98E-02 n-54 4.99E-03 5.10E-02 5.59E-02 Fe-55 8.09E-03 0.0E 00 8.09E-03 Fe-59 2.42E-03 9.05E-03 1.15E-02 Co-58 2.20E-02 1.44E-01 1.66E-01 Co-60 1.44E-02 1.72E-02 3.16E-02 n-65 3.82E-04 0.0E 00 3.82E-04 Sr-89 1.92E-04 4.33E-03 4.52E-03 Sr-90 2.20E-05 3.88E-04 4.10E-04 Sr-91 2.84E-04 2.18E-03 2.47E-03

-91m 1.68E-04 0.0E 00 1.68E-04

-91 9.00E-05 3.00E-04 3.90E-04

-93 1.27E-03 0.0E 00 1.27E-03 r-95 1.39E-03 1.20E-02 1.34E-02 Nb-95 2.10E-03 8.98E-03 1.11E-02 o-99 4.20E-03 9.95E-02 1.04E-01 Tc-99m 3.35E-03 0.0E 00 3.35E-03 Ru-103 5.88E-03 0.0E 00 5.88E-03 Ru-106 7.63E-02 0.0E 00 7.63E-02 Te-129m 1.41E-04 0.0E 00 1.41E-04 Te-129 7.30E-04 0.0E 00 7.30E-04 Te-131m 8.05E-04 0.0E 00 8.05E-04 Te-131 2.03E-04 0.0E 00 2.03E-04 Te-132 1.11E-03 2.93E-02 3.05E-02 Ba-140 1.02E-02 3.48E-01 3.58E-01 La-140 1.62E-02 4.98E-01 5.14E-01 Ce-141 3.41E-04 0.0E 00 3.41E-04 Ce-143 1.53E-03 0.0E 00 1.53E-03 Ce-144 6.84E-03 1.26E-01 1.33E-01 Np-239 1.37E-03 0.0E 00 1.37E-03

-3 1.25E 03 0.0E 00 1.25E 03 Totals o 3 E 1 E E H3 Totals H 12 E 3 E 12 E 3 3

FSEIS Ta le 3 1 WBN Total Annual Disc arge Liquid Waste Processing S stem for T o Unit Operation 1 Unit 1 Unit 1 Unit 2 Unit Nuclide LRW1 SGB2 Totals 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 n-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 n-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

-91m 1.68E-04 0.0E 00 1.68E-04 3.37E-04

-91 9.00E-05 3.00E-04 3.90E-04 7.80E-04

-93 1.27E-03 0.0E 00 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 0.0E 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

FSEIS Ta le 3 1 continued 1 Unit 1 Unit 1 Unit 2 Unit Nuclide LRW1 SGB2 Totals 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

-3 1.25E 03 0.0E 00 1.25E 03 2.51E 03

-3 (TPC) 3.33E 03 0.0E 00 3.33E 03 4.58E 03 Totals o H 3 3 E 1 E E Totals H 3 12 E 3 12 E 3 2 2E 3 Total H 3 3 33E 3 3 33E 3 E 3 TPC3 1

Liquid Radwaste 2

Steam Generator Blowdown 3

Tritium Production Core (single unit)

FSAR Ta le 11 2 Total Annual Disc arge Liquid Waste Processing S stem Annual Disc arge 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, T ER PERATI NAL DES EXPECTED PERATI N D obile Demineralizer D DF CVCS DF SGB processed SGB processed LRW SGB with Column 6 by CD by CD and D No SGB no CD process and Column 7 Br-84 1000 50 0.0003696 0.000165534 1.65E-04 5.23E-04 6.88E-04 I-131 1000 50 0.471244 0.0267889 2.63E-02 1.14E 00 1.16E 00 I-132 1000 50 0.055475 0.01319732 1.32E-02 1.08E-01 1.21E-01 I-133 1000 50 0.388058 0.0531932 5.29E-02 8.57E-01 9.10E-02 I-134 1000 50 0.0166222 0.00627256 6.26E-03 2.65E-02 3.26E-03 I-135 1000 50 0.212508 0.047673 4.75E-02 4.22E-01 4.70E-01 Rb-88 1000 2 0.0071992 0.006893007 6.89E-03 7.84E-04 7.68E-03 Cs-134 1000 2 0.095136 0.02934186 2.93E-02 1.68E-01 1.98E-01 Cs-136 1000 2 0.0092913 0.00255804 2.55E-03 1.72E-02 1.98E-02 Cs-137 1000 2 0.126735 0.04035147 4.03E-02 2.21E-01 2.61E-01 Na-24 1000 50 0.089752 0.01867315 1.86E-02 0.00E 00 1.86E-02 Cr-51 1000 50 0.0432857 0.00706196 7.03E-03 9.27E-02 9.98E-02 n-54 1000 50 0.0249083 0.0050082 4.99E-03 5.10E-02 5.59E-02 Fe-55 1000 50 0.0232248 0.00810991 8.09E-03 0.00E 00 8.09E-03 Fe-59 1000 50 0.0059574 0.002422938 2.42E-03 9.05E-03 1.15E-02 Co-58 100 50 0.078189 0.0225906 2.20E-02 1.44E-01 1.66E-01 Co-60 1000 50 0.021121 0.014406681 1.44E-02 1.72E-02 3.16E-02 n-65 1000 50 0.0065754 0.000388573 3.82E-04 0.00E 00 3.82E-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, OTHER OPERATIONAL MODES EXPECTED OPERATION MD = Mobile Demineralizer 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-04 4.33E-03 4.52E-03 Sr-90 1000 50 0.0001736 2.21026E-05 2.20E-05 3.88E-04 4.10E-04 Sr-91 1000 50 0.0011378 0.000284704 2.84E-04 2.18E-03 2.47E-03 Y-91m 1000 50 0.0006694 0.000168895 1.68E-04 0.00E+00 1.68E-04 Y-91 1000 50 0.0002072 9.00858E-05 9.00E-05 3.00E-04 3.90E-04 Y-93 1000 50 0.0051829 0.001273833 1.27E-03 0.00E+00 1.27E-03 Zr-95 1000 50 0.0060943 0.001395024 1.39E-03 1.20E-02 1.34E-02 Nb-95 1000 50 0.0056138 0.002108301 2.10E-03 8.98E-03 1.11E-02 Mo-99 1000 50 0.0430858 0.00423469 4.20E-03 9.95E-02 1.04E-01 Te-99m 1000 50 0.0386898 0.00338514 3.35E-03 0.00E+00 3.35E-03 Ru-103 1000 50 0.0975742 0.00597589 5.88E-03 0.00E+00 5.88E-03 Ru-106 1000 50 1.184324 0.077432 7.63E-02 0.00E+00 7.63E-02 Te-129m 1000 50 0.0023849 0.000143146 1.41E-04 0.00E+00 1.41E-04 Te-129 1000 50 0.0030182 0.000732508 7.30E-04 0.00E+00 7.30E-04 Te-131m 1000 50 0.0056795 0.000809335 8.05E-04 0.00E+00 8.05E-04 Te-131 1000 50 0.0011229 0.00020385 2.03E-04 0.00E+00 2.03E-04 Te-132 1000 50 0.0125817 0.00112321 1.11E-03 2.93E-02 3.05E-02 Ba-140 1000 50 0.1461456 0.0103815 1.02E-02 3.48E-01 3.58E-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 7 Column 8 CD = Condensate Polishing Demineralizer, OTHER OPERATIONAL MODES EXPECTED OPERATION MD = Mobile Demineralizer 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-02 4.98E-01 5.14E-01 Ce-141 1000 50 0.0021085 0.000342306 3.41E-04 0.00E+00 3.41E-04 Ce-143 1000 50 0.0114277 0.00153622 1.53E-03 0.00E+00 1.53E-03 Ce-144 1000 50 0.0560926 0.00689185 6.84E-03 1.26E-01 1.33E-01 Np-239 1000 50 0.0135434 0.00138559 1.37E-03 0.00E+00 1.37E-03 H3 (TPC) 1 1 1252.80 (3326.4) 1252.80 (3326.4) 1257.64 (3326.4)

Unplanned Releases**

0.16 0.16 0.16 0.16 Total (w/o H3) 3.5252328 0.4416449 0.438 4.402 2 4.84 0.598 w/unplanned 3.685 0.602 5.000 Total (w/H3) 1256.33 (3329.93) 1253.24 (3326.84) 1257.64 (3331.24) w/unplanned 1256.49 (3330.09) 1253.40 (3327.00) 1257.80 (3331.40)

FSAR Ta le 11 2 Total Annual Disc arge Liquid Waste Processing S stem Annual Disc arge 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 L ST TB cond. demin/ D DF CVCS DF x D obile Demineralizer (Processes Tanks, CVCS) x DF Decontamination Factor x CVCS DF Decontamination Factor of CVCS prior to treatment with D.

x 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 ((A B/C)/D) E F/ G Column 5 ((A B/C)/D) E F/ /D G Column 6 ((A B/C)/D) E F G Column 7 Column 8 ((A B/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 Condensate Demineralizer 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 Ta le 11 2 Watts Bar Nuclear Plant Doses from Liquid Effluents For Year 2 Indi idual Dose mrem Adult Bone GI Tract Thyroid Liver idney Lung Skin Total Body 0.56 0.132 0.88 0.96 0.352 0.136 0.031 0.72 Teen Bone GI Tract Thyroid Liver idney Lung Skin Total Body 0.60 0.104 0.80 1.00 0.356 0.152 0.031 0.44 C ild Bone GI Tract Thyroid Liver idney Lung Skin Total Body 0.76 0.06 0.92 0.88 0.312 0.128 0.031 0.188 Infant Bone GI Tract Thyroid Liver idney Lung Skin Total Body 0.036 0.033 0.264 0.036 0.034 0.032 0.031 0.032 Population Dose Person rem Total Bod Bone GI Tract Thyroid Liver idney Lung Skin 1.619 1.761 1.420 15.336 2.130 1.392 1.037 0.315

Enclosure 2 Response to FSAR Chapter 11 and FSEIS Chapter 3 Request For Additional Information FSAR Chapter 11 and FSEIS Chapter 3 Changes - Summary of Proposed Changes to FSAR and FSEIS Text and Tables - Proposed Markups for FSAR Chapter 11, Text and Tables - Proposed Clean Copy of FSAR Sections 11.1, 11.2 and 11.3 - Proposed Markups for FSEIS Chapter 3 - Proposed Clean Copy of FSEIS Chapter 3

Enclosure 2, 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.

REFERENCES

1. 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 Factors The 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 F/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 TVA s justification for use of a straight-line dispersion model without adjustment factors in the calculation of annual average atmospheric dispersion (F/Q) values presented in the draft Watts Bar ffsite Dose Calculation anual ( DC ) Ref. 1 . The NRC presented two options (1) adopt F/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 F/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 (F/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 TVAs GELC code with results from the ES PUFF II model. ES PUFF II is a regional scale, variable trajectory, Gaussian puff model. ES PUFF 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 ES PUFF II model.

TVA will continue to use the methodology described in TVA Report TVA/ NRED/A WR--87/24 Ref. 2 . GELC will continue to be used with terrain adjustment factors based on comparison to ES PUFF 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/A WR-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 11 1 2

1. 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 11 1

1. 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 11 2 and Ta les 11 2 11 2 a 11 2 and 11 2 d The 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 11 2 1

1. 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 11 3

1. 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 11 3

1. Clarification has been added to describe the basis for Table 11.3-7c (the basis is ANSI N18.1-1984).

FSAR Ta le 11 3

1. 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 Ta le 11 3 c

1. 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 11 3

1. 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.

Ta le 11 3

1. TVA verified the validity of the land census used in FSAR Table 11.3-8.

2. The distance, F/Q and D/Q were revised to be consistent with the Terrain Adjustment Factor determined using the methodology established in TVA/ NRED/A WR--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 11 3

1. 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, F/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 11 3 1 1

1. 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 11 3 1 2

1. 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.

Ta le 11 3

1. This table has been revised to ensure consistency with other sections of the FSAR and the FSEIS. Population dose calculations have been revised.

Ta le 11 3 1

1. The individual doses listed in Table 11.3-10 were determined using each nuclides 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.

Ta le 11 3 11

1. This table has been revised to describe the results of TVAs estimate of the radiological impact to regional population groups in the year 2040 from the normal operation of the Watts Bar Nuclear Plant.

FSEIS Ta le 3 1

1. 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 Ta le 3 2

1. FSEIS Table 3-20 was revised to use the source term associated with Continuous Filtered Containment Vent.

FSEIS Ta le 3 21

1. The doses were revised to incorporate the latest parameters including use of updated Feeding Factors and Terrain Adjustment Factors.

FSEIS Ta le 3 22

1. Table 3-22 has been revised to reflect the comparison of Annual Releases from Unit 1 and Unit

Enclosure 2, Attachment 2 Response to FSAR Chapter 11 and FSEIS, Chapter 3 Request For Additional Information Proposed Markups for FSAR Chapter 11, Text and Tables

WATTS BAR W P-1 3 B = boron concentration reduction rate by eed and bleed, ppm per sec.

 = remo al e iciency o puri ication cycle or nuclide

 = radioacti e decay constant I = escape rate coe icient or di usion into coolant t = elapsed time (seconds) since the beginning o cycle subscripts C = re ers to core w = re ers to coolant i = re ers to parent nuclide

= re ers to daughter 11.1.1.2 olume Control Tan istorical Design Acti ity Table 11.1-3 lists the acti ities in the olume control tan using the assumptions summarized in Table 11.1-1.

11.1.1.3 Pressuri er istorical Design Acti ity The acti ities in the pressurizer are separated between the li uid and the steam phase and the results obtained are gi en in Table 11.1-4 using the assumptions summarized in Table 11.1-1.

11.1.1. aseous Waste Processing System istorical Design Acti ities The acti ities to be ound in the Gaseous Waste Processing System are gi en in Table 11.1-5.

11.1.1.5 Secondary Coolant istorical Design Acti ities The secondary cleanup system design acti ities used or shielding design calculations are discussed in Subsection 12.2.1.5.

11.1.2 Realistic odel for Radioacti ities in Systems and Com onents This section and associated Tables 11.1-6 and 11.1-7 present results which supersede the calculations in the pre ious 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 a ailable in a orm that could permeate through the TPBAR cladding. Howe er, it is assumed that while operating with a Tritium Production Core (TPC), some o the tritium in entory in the TPBARs may permeate the cladding 11.1-2 Insert SOURCE TERMS (Unit 1 only)

WATTS BAR W P-1 3 (4) Au iliary Building Ventilation System (5) Turbine Building Ventilation System (6) Steam Generator Blowdown System Estimates or the release o radioacti e materials rom sources 1 through 5 (abo e) are presented in Section 11.3.7. The release paths and transport mechanism or these sources o radioacti e material are also presented in Section 11.3.8.

The Steam Generator Blowdown System (SGBS) is another source o li uid radioacti e material that is not normally considered part o the radioacti e 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 e aluating the radiological conse uences o li uid releases rom steam generator blowdowns is the path to the ri er ia the cooling tower blowdown line. This route is used primarily during startups, when non-radioacti e impurity le els are higher than normal and when SGBS is bypassing the condensate demineralizers. The normal route or the blowdown li uid 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 ri er is monitored or radioacti ity as speci ied in Section 11.4. An alarm in the Main Control Room alerts the operator o an increasing radioacti ity le el in the discharge. I the radiation setpoint is e ceeded, the blowdown discharge is automatically di erted to the condensate demineralizers. The basis or the setpoint is presented in Section 11.4.

References (1) ANSI/ANS-18.1-1984, Radioacti e 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 Corporation, Pittsburgh, Pa. 15230, April 1974.

(3) WCAP-7664, R1 Radiation Analysis Design Manual Loop Plant ,

October 1972.

Replace the two sentences with the following sentence:

"This route is used primarily during periods when there is no significant primary to secondary leakage."

11.1-4 SOURCE TERMS

WATTS BAR W P-1 3 11.2. . .2 Descri tion The TB drains are not normally radioacti e.

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 Deminerali er System Drains The Condensate Polishing Demineralizer System (CPDS) area is ser iced by separate loor and e uipment drains. The drains or CPDS are routed to the Condensate Demineralizer sump where they are pumped to the Neutralization Tan (NT). These drains ha e a potential to be low-le el radioacti e during periods o primary to secondary lea age. The NT is pro ided with the capability o ad usting pH, and i the in entory is not radioacti e or less than 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 in entory is abo e dischargeable limits. Any radioacti e 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 radioacti e and non-radioacti e conditions.

11.2. . .2.2 Other Turbine uilding Drainage Drainage 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 e uipment 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 gra ity directly to the yard holding pond.

Replace Section 11.2. . .2.3 Oil and Oily Water Drainage 11.2.6.5 with the Oil is drained directly to drums or tan truc s or reuse or remo al rom the plant.

insert from Oily the water drains are urnished in the Turbine Building and are routed to thefollowing oil sump page.

which is located in the low point o the Turbine Building. Oil may be accumulated in the sump until a su icient amount is collected to be pumped into tan truc s or o site disposal.

11.2. .5 stimated Total Liquid Releases The potential releases ha e been e aluated as indicated in the abo e sections. The e pected li uid 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 gi en 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 e ceeding the 5 Ci/yr limit in 10 CFR 50, Appendi I. Column 7 o Table 11.2-5 indicates that the total release, including 11.2-18 U WASTE S STEMS

Replace Section 11.2.6.5 with the WATTS BAR insert from the W P-1 3 following page.

untreated steam generator blow down, is signi icantly 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. Howe er, column 7 does include other releases rom waste holdup tan s 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 ma imum concentration o 3.65E-5 uCi/cc gross gamma during the release and no other Condensate Demineralizer waste is processed during the release. Howe er, column 8 does include other releases rom waste holdup tan s which are treated using the Mobile Demineralizers.

Tables 11.2-5a, 11.2-5b, 11.2-5c, and 11.2-5d describe li uid releases or 1 ailed uel or both treated and untreated waste relati e to the re uirements o 10 CFR 20.1302(b). The sum o er 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 li uid is not processed by the Mobile Demineralizers. This mode o operation is not normally used since the C/ECL alue e ceeds the re uirements o 10 CFR 20.1302(b). The bul o the release is due to the untreated condensate resin regeneration waste. In order to pre ent e ceeding 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 concentrations are shown in Table 11.2-5b and are less than the limits speci ied 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. Howe er, these releases do include other releases rom waste holdup tan s 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 ma imum concentration o 3.65E-5 uCi/cc gross gamma during the release and no other Condensate Demineralizer waste is processed during the release. Howe er, these releases do include other releases rom waste holdup tan s which are treated using the Mobile Demineralizers.

Based on the abo e, the releases rom the plant are in accordance with the design ob ecti es as outlined in Section 11.2.1 and the O site Dose Calculation Manual.

11.2. R L AS PO TS All radioacti e li uid 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.

U WASTE S STEMS 11.2-19

Replace Section 11.2.6.5 with following two pages:

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

Irrespecti e o the speci ic modes described, the annual releases are re uired to be e ual to or less than the limits pro ided in the ODCM, Appendi I and 10CFR 20.

Table 11.2-5 pro ides the total annual discharge rom the li uid waste processing system or our di erent le els o processing prior to discharge. The annual discharge or Unit 2 is e pected to be similar to Unit 1 with the e ception 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 pro ide conser atism as discussed in NUREG-0017. The discussions to ollow are based on the luid uantities and acti ities speci ied in Table 11.2-1.

11.2. .5.1 ected ormal Plant O eration The e pected plant alignment and the our resultant release paths are as ollows x CVCS letdown waste processed by the CVCS demineralizers and then by the mobile demineralizer.

x The reactor coolant drain tan , the tritiated drain collector tan , and the loor drain collector tan discharges and processed using the mobile demineralizer x Li uid releases rom the Laundry and Hot Shower Drain Tan and the Turbine Building drains can be released without processing by mobile demineralizer.

This combination o abo e three paths is called li uid radwaste.

x 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 pro ides the li uid radwaste source term. Column 7 pro ides the source term or steam generator blowdown assuming an annual untreated SG Blowdown concentration o 3.65 E-5 uCI/cc. Concentrations abo e this alue cannot be released continuously on an annual basis without additional processing. Unit 1 currently operates without the condensate demineralizers in ser ice. The condensate demineralizers will not be utilized unless signi icant primary to secondary lea age occurs.

Operating e perience has shown that annual releases are below the alues shown in Column 8 and thus that processing o SG Blowdown is not e pected to be re uired. There is no condensate demineralizer blowdown or bac washing when the plant is operating under this set o conditions. SG Blowdown concentrations abo e 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 e pected li uid 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. Tables 11.2-5c and 11.2-5d describe li uid releases or 1 ailed uel or both treated and untreated waste relati e to the re uirements o 10 CFR 20.1302(b). Table 11.2- 5d shows releases remain within the 10CFR

20 limits i the steam generator blow down concentration is restricted to a ma imum 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 x CVCS letdown waste processed by the CVCS demineralizers and then by the mobile demineralizer.

x The reactor coolant drain tan , the tritiated drain collector tan , and the loor drain collector tan discharges and processed using the mobile demineralizer x Condensate Demineralizer Flow including SG Blowdown processed the condensate demineralizer x Li uid 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 ollowing x CVCS letdown waste processed by the CVCS demineralizers and then by the mobile demineralizer.

x The reactor coolant drain tan , the tritiated drain collector tan , and the loor drain collector tan discharges and processed using the mobile demineralizer x Condensate Demineralizer Flow including SG Blowdown processed by the condensate demineralizer with additional processing by the mobile demineralizer.

x Li uid releases rom the Laundry and Hot Shower Drain Tan and the Turbine Building drains can be released without processing by mobile demineralizer.

The e pected li uid 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 li uid releases or 1 ailed uel or both treated and untreated waste relati e to the re uirements o 10 CFR 20.1302(b). The sum o er 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 li uid is not processed by the Mobile Demineralizers. In order to pre ent e ceeding 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 concentrations are shown in Table 11.2-5b and are less than the limits speci ied in 10 CFR 20.1302(b).

Based on the abo e, the releases rom the plant are in accordance with the design ob ecti es as outlined in Section 11.2.1 and the O site Dose Calculation Manual.

WATTS BAR W P-1 3 11.2. D LUT O FACTORS The dosimetry calculations or drin ing water are based on the assumption that the li uid e luent will be mi ed with 10 o the ri er low between the point o discharge and Tennessee Ri er 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. ST AT D DOS S FRO RAD O UCL D S L U D FFLU TS Doses rom the ingestion o water, rom the consumption o ish, and rom shoreline recreation are calculated or e posures to radionuclides routinely released in li uid e luents.

11.2. .1 Assum tions and Calculational ethods Internal doses are calculated using methods outlined in NRC Regulatory Guide 1.109, Re ision 1, October 1977. This model is used or estimating the doses to bone, gastro-intestinal (G.I.) tract, thyroid, li er, idney, lung, s in, and total body o man rom ingestion o water, consumption o ish, and rom e ternal e posures due to recreational acti ities. Population doses are estimated or the year 2040 based on the populations gi en in Table 2.1-12.

(1) Doses to Man rom the Ingestion o Water Replace with Data listed in Table 11.2-6 or public water supplies is used to calculate dose 2000 public water commitments rom the consumption o Tennessee Ri er water. The 2040 supply populations populations or the water supplies are estimated by multiplying the 1990 by a population populations by a population growth actor o 1.24. This actor is the ratio o growth factor of the 2040 population (Table 2.1-12) to the 1990 population. It is assumed that 1.42. the plant e luent is mi ed with one-tenth o the ri er 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 Replace with is assumed.

2000 population Dilution is calculated using a erage annual low data or the Tennessee Ri er (Table 2.1-8). as measured during the 69-year period 1899-1968. The a erage low past the site is appro imately 28,000 t3/sec.

Radioacti e decay between the time o inta e in a water system and the time o consumption is handled in accordance with Regulatory Guide 1.109.

Ma imum and a erage consumption rates are those recommended by Regulatory Guide 1.109.

Due to a lac o de initi e data, no credit is ta en or remo al o acti ity rom the water through absorption on solids and sedimentation, by deposition in the biomass, or by processing within water treatment systems.

11.2-20 U WASTE S STEMS

Replace with Insert A Table 11.2-5 Total Annual Discharge Liquid Waste Processing System*

11.2-34 Annual Discharge (Ci) After Processing Total Releases Per Unit (TPC Unit 1 Only)***

(Page 1 of 3)

Column 1 Column 2 Column 3 Column 4 Column 5 Column 6 Column 7 Column 8 WATTS BAR CD = Condensate Polishing Demineralizer, MD = Mobile Demineralizer MD DF CVCS DF w/o w/CD no CD no CD no CD CD process by MD processing by MD processing process, SGB process, SGB rel=LLD rel=ma Br-84 1000 50 0.0003696 0.000165534 0.00220833 0.00016533 0.0001653 I-131 1000 50 0.471244 0.0267889 4.475344 0.026344 0.026344 I-132 1000 50 0.055475 0.01319732 0.436355 0.013155 0.013155 I-133 1000 50 0.388058 0.0531932 3.404858 0.052858 0.052858 I-134 1000 50 0.0166222 0.00627256 0.1098622 0.0062622 0.0062622 I-135 1000 50 0.212508 0.047673 1.697508 0.047508 0.047508 Rb-88 1000 2 0.0071992 0.006893007 0.0075057 0.0068927 0.0068927 Cs-134 1000 2 0.095136 0.02934186 0.160996 0.029276 0.029276 Cs-136 1000 2 0.0092913 0.00255804 0.0160313 0.0025513 0.0025513 Cs-137 1000 2 0.126735 0.04035147 0.213205 0.040265 0.040265 Na-24 1000 50 0.089752 0.01867315 0.730102 0.018602 0.018602 Cr-51 1000 50 0.0432857 0.00706196 0.3696257 0.0070257 0.0070257 Mn-54 1000 50 0.0249083 0.0050082 0.20418828 0.00498828 0.0049883 Fe-55 1000 50 0.0232248 0.00810991 0.15939478 0.00809478 0.0080948 U

Fe-59 1000 50 0.0059574 0.002422938 0.0377994 0.0024194 0.0024194 Co-58 100 50 0.078189 0.0225906 0.583629 0.022029 0.022029 W

Co-60 1000 50 0.021121 0.014406681 0.08160996 0.01439996 0.0144 WASTE S STEMS Zn-65 1000 50 0.0065754 0.000388573 0.06231238 0.00038238 0.0003824 P-1 3

Replace with Insert B Table 11.2-5 Total Annual Discharge Liquid Waste Processing System*

U 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 WATTS BAR WASTE S STEMS CD = Condensate Polishing Demineralizer, MD = Mobile Demineralizer MD DF CVCS DF w/o w/CD no CD no CD no CD CD process by MD processing by MD processing process, SGB process, SGB rel=LLD rel=ma Sr-89 1000 50 0.0018825 0.000193215 0.01710152 0.00019152 0.0001915 Sr-90 1000 50 0.0001736 2.21026E-05 0.00153795 2.1951E-05 2.195E-05 Sr-91 1000 50 0.0011378 0.000284704 0.00882285 0.00028385 0.0002839 Y-91m 1000 50 0.0006694 0.000168895 0.00517839 0.00016839 0.0001684 Y-91 1000 50 0.0002072 9.00858E-05 0.00126197 8.9969E-09 8.997E-05 Y-93 1000 50 0.0051829 0.001273833 0.04039992 0.00126992 0.0012699 Zr-95 1000 50 0.0060943 0.001395024 0.04843032 0.00139032 0.0013903 Nb-95 1000 50 0.0056138 0.002108301 0.03719479 0.00210479 0.0021048 Mo-99 1000 50 0.0430858 0.00423469 0.3930958 0.0041958 0.0041958 Te-99m 1000 50 0.0386898 0.00338514 0.3567498 0.0033498 0.0033498 Ru-103 1000 50 0.0975742 0.00597589 0.9227842 0.0058842 0.0058842 Ru-106 1000 50 1.184324 0.077432 11.156324 0.076324 0.076324 Te-129m 1000 50 0.0023849 0.000143146 0.0225809 0.0001409 0.0001409 Te-129 1000 50 0.0030182 0.000732508 0.02361022 0.00073022 0.0007302 Te-131m 1000 50 0.0056795 0.000809335 0.04955446 0.00080446 0.0008045 Te-131 1000 50 0.0011229 0.00020385 0.00940293 0.00020293 0.0002029 Te-132 1000 50 0.0125817 0.00112321 0.11581174 0.00111174 0.0011117 W Ba-140 1000 50 0.1461456 0.0103815 1.3692456 0.0102456 0.0102456 11.2-35 P-1 3

Replace with Insert C Table 11.2-5 Total Annual Discharge Liquid Waste Processing System*

11.2-36 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 Column 8 WATTS BAR CD = Condensate Polishing Demineralizer, MD = Mobile Demineralizer MD DF CVCS DF w/o w/CD no CD no CD no CD CD process by MD processing by MD processing process, SGB process, SGB rel=LLD rel=ma La-140 1000 50 0.2108406 0.0164352 1.9622406 0.0162406 0.0162406 Ce-141 1000 50 0.0021085 0.000342306 0.01802054 0.00034054 0.0003405 Ce-143 1000 50 0.0114277 0.00153622 0.10054572 0.00152572 0.0015257 Ce-144 1000 50 0.0560926 0.00689185 0.4993426 0.0068426 0.0068426 Np-239 1000 50 0.0135434 0.00138559 0.12307342 0.00137342 0.0013734 H-3 1 1 1252.80 (3326.4) 1252.80 (3326.4) 1252.80 (3326.4) 1252.80 (3326.4) 1252.80 (3326.4)

(TPC) unplanned 0.16 0.16 0.16 0.16 0.16 SGBD contribution 0.06 4.402 ****

total (w/o H3) 3.5252328 0.4416449 30.0348453 0.50 4.84 w/unplanned 3.685 0.602 30.195 0.658 5.000 total (w/H3) 1256.33 (3329.93) 1253.24 (3326.84) 1282.83 (3356.43) 1253.30 (3326.90) 1257.64 (3331.24) w/unplanned 1256.49 (3330.09) 1253.40 (3327.00) 1283.00 (3356.60) 1253.46 (3327.06) 1257.80 (3331.40)

U W

WASTE S STEMS P-1 3

Insert A 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 1 of 3)

Column 1 Column 2 Column 3 Column 4 Column 5 Column 6 Column 7 Column 8 WATTS BAR CD = Condensate Polishing Demineralizer, OTHER OPERATIONAL MODES EXPECTED OPERATION LIQUID WASTE SYSTEMS MD = Mobile Demineralizer MD DF CVCS DF SGB processed SGB processed by LRW SGB with no CD 6 Column 6 and by CD CD and MD No SGB process Column 7 Br-84 1000 50 0.0003696 0.000165534 1.65E-04 5.23E-04 6.88E-04 I-131 1000 50 0.471244 0.0267889 2.63E-02 1.14E+00 1.16E+00 I-132 1000 50 0.055475 0.01319732 1.32E-02 1.32E-0 1.08E-01 1.21E-01 I-133 1000 50 0.388058 0.0531932 5.29E-02 8.57E-01 9.10E-01 I-134 1000 50 0.0166222 0.00627256 6.26E-03 2.65E-02 3.28E-02 I-135 1000 50 0.212508 0.047673 4.75E-02 4.22E-01 4.70E-01 Rb-88 1000 2 0.0071992 0.006893007 6.89E-03 7.84E-04 7.68E-03 Cs-134 1000 2 0.095136 0.02934186 2.93E-02 1.68E-01 1.98E-01 Cs-136 1000 2 0.0092913 0.00255804 2.55E-03 1.72E-02 1.98E-02 Cs-137 1000 2 0.126735 0.04035147 4.03E-02 2.21E-01 2.61E-01 Na-24 1000 50 0.089752 0.01867315 1.86E-02 0.00E+00 1.86E-02 Cr-51 1000 50 0.0432857 0.00706196 7.03E-03 9.27E-02 9.98E-02 Mn-54 1000 50 0.0249083 0.0050082 4.99E-03 5.10E-02 5.59E-02 Fe-55 1000 50 0.0232248 0.00810991 8.09E-03 0.00E+00 8.09E-03 Fe-59 1000 50 0.0059574 0.002422938 2.42E-03 9.05E-03 1.15E-02 Co-58 100 50 0.078189 0.0225906 2.20E-02 1.44E-01 1.66E-01 Co-60 1000 50 0.021121 0.014406681 1.44E-02 1.72E-02 3.16E-02 Zn-65 1000 50 0.0065754 0.000388573 3.82E-04 0.0E+00 3.82E-04 11.2-35

Insert B Table 11.2-5 Total Annual Discharge Liquid Waste Processing System*

11.2-36 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 WATTS BAR CD = Condensate Polishing Demineralizer, OTHER OPERATIONAL MODES EXPECTED OPERATION MD = Mobile Demineralizer MD DF CVCS DF SGB processed SGB processed by LRW SGB with no CD 6 Column 6 and by CD CD and MD No SGB process Column 7 Sr-89 1000 50 0.0018825 0.000193215 1.92E-04 4.33E-03 4.52E-03 Sr-90 1000 50 0.0001736 2.21026E-05 2.20E-05 3.88E-04 4.10E-04 Sr-91 1000 50 0.0011378 0.000284704 2.84E-04 2.18E-03 2.47E-03 Y-91m 1000 50 0.0006694 0.000168895 1.68E-04 0.00E+00 1.68E-04 Y-91 1000 50 0.0002072 9.00858E-05 9.00E-05 3.00E-04 3.90E-04 Y-93 1000 50 0.0051829 0.001273833 1.27E-03 0.00E+00 1.27E-03 Zr-95 1000 50 0.0060943 0.001395024 1.39E-03 1.20E-02 1.34E-02 Nb-95 1000 50 0.0056138 0.002108301 2.10E-03 8.98E-03 1.11E-02 Mo-99 1000 50 0.0430858 0.00423469 4.20E-03 9.95E-02 1.04E-01 Tc-99m Te-99m 1000 50 0.0386898 0.00338514 3.35E-03 0.00E+00 3.35E-03 Ru-103 1000 50 0.0975742 0.00597589 5.88E-03 0.00E+00 5.88E-03 Ru-106 1000 50 1.184324 0.077432 7.63E-02 0.00E+00 7.63E-02 Tc-129 1000 50 0.0023849 0.000143146 1.41E-04 0.00E+00 1.41E-04 Te-129 1000 50 0.0030182 0.000732508 7.30E-04 0.00E+00 7.30E-04 Te-131m 1000 50 0.0056795 0.000809335 8.05E-04 0.00E+00 8.05E-04 Te-131 1000 50 0.0011229 0.00020385 2.03E-04 0.00E+00 2.03E-04 Te-132 1000 50 0.0125817 0.00112321 1.11E-03 2.93E-02 3.05E-02 Ba-140 1000 50 0.1461456 0.0103815 1.02E-02 3.48E-01 3.58E-01 LIQUID WASTE SYSTEMS

Insert C 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 Column 8 WATTS BAR CD = Condensate Polishing Demineralizer, OTHER OPERATIONAL MODES EXPECTED OPERATION MD = Mobile Demineralizer LIQUID WASTE SYSTEMS MD DF CVCS DF SGB processed SGB processed by LRW SGB with no CD 6 Column 6 and by CD CD and MD No SGB process Column 7 La-140 1000 50 0.2108406 0.0164352 1.62E-02 4.98E-01 5.14E-01 Ce-141 1000 50 0.0021085 0.000342306 3.41E-04 0.00E+00 3.41E-04 Ce-143 1000 50 0.0114277 0.00153622 1.53E-03 0.00E+00 1.53E-03 Ce-144 1000 50 0.0560926 0.00689185 6.84E-03 1.26E-01 1.33E-01 Np-239 1000 50 0.0135434 0.00138559 1.37E-03 0.00E+00 1.37E-03 H-3 1 1 1252.80 (3326.4) 1252.80 (3326.4) 1257.64 (3326.4)

(TPC)

Unplanned Unplanne Releases ** 0.16 0.

0.16 0.16 0.1 0.16 0.16 total (w/o H3) 3.5252328 0.4416449 0.438 4.402 4.84 w/unplanned 3.685 0.602 0.598 5.000 total (w/H3) 1256.33 (3329.93) 1253.24 (3326.84) 1257.64 (3331.24) w/unplanned 1256.49 (3330.09) 1253.40 (3327.00) 1257.80 (3331.40) 11.2-37

WATTS BAR W P-1 3 Replace with Insert D Table 11.2-5 Total Annual Discharge Liquid Waste Processing System*

Annual Discharge (Ci) After Processing Total Releases Per Unit (TPC Unit 1 Only)***

Notes

• The 0.16 Ci/yr is the unplanned release.

• • MD = Mobile Demineralizer (Processes Tan s, 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 CVCS DF

• • • • This calculated alue is based on an a erage o 365 days but does not represent a constraint on the plant since the actual alue or indi idual releases may be greater. Howe er, 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 1 Source term isotopes Column 2 Decontamination actors or the Mobile Demineralizer Column 3 CVCS Demineralizer decontamination actors Column 4 ((A+B/C)/D) + E + F/H + G Column 5 ((A+B/C)/D) + E + F/H1D + G Column 6 ((A+B/C)/D) + E + F + G Column 7 ((A+B/C)/D)+ E + G + I Column 8 ((A+B/C)/D) + E + G +

(See below de inition or items A thru A (Ci/yr) = Reactor Coolant Drain Tan + Tritiated Drain Collector Tan + Floor Drain Collector Tan B (Ci/yr) = Chemical Volume Control System (CVCS) Letdown C = CVCS Demineralizer decontamination actor D = Mobi le 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 = Condensate Demineralizer decontamination actors (2 or Rb-88, 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 e ual 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/yr U WASTE S STEMS 11.2-37

Insert D 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 CVCS DF x MD = Mobile Demineralizer (Processes Tan s, CVCS) x DF = Decontamination Factor x CVCS DF = Decontamination Factor o CVCS prior to treatment with MD.

x 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 Demineralizer Column 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 de inition or items A thru A (Ci/yr) = Reactor Coolant Drain Tan + Tritiated Drain Collector Tan + Floor Drain Collector Tan B (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 = Condensate Demineralizer 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 a erage o 365 days but does not represent a constraint on the plant since the actual alue or indi idual releases may be greater.

Howe er, the total o all yearly releases must remain 5 Ci.

Delete Table WATTS BAR W P-1 3 Table 11.2-5c no CD rocess S D at LLD ith 2 g m dilution other release aths at design limit A S Scaled to liquid liquid Ci yr . Ci des ansi Ci yr uCi cc 1 CFR2 C CL Br-84 0.00016533 7.122E-06 2.50 0.00042045 1.06E-11 4.0E-04 2.642E-08 I-131 0.026344 1.551E-02 52.41 1.39622267 3.51E-08 1.0E-06 0.0350911 I-132 0.013155 1.475E-03 4.00 0.05409534 1.36E-09 1.0E-04 1.36E-05 I-133 0.052858 1.169E-02 26.85 1.43069229 3.60E-08 7.0E-06 0.0051368 I-134 0.0062622 3.612E-04 1.65 0.01068347 2.69E-10 4.0E-04 6.713E-07 I-135 0.047508 5.752E-03 7.91 0.38171474 9.59E-09 3.0E-05 0.0003198 Rb-88 0.0068927 1.069E-05 18.14 0.12502534 3.14E-09 4.0E-04 7.856E-06 Cs-134 0.029276 2.296E-03 40.60 1.19076688 2.99E-08 9.0E-07 0.0332526 Cs-136 0.0025513 2.350E-04 165.20 0.42170523 1.06E-08 6.0E-06 0.0017664 Cs-137 0.040265 3.014E-03 153.22 6.17231989 1.55E-07 1.0E-06 0.155128 Cr-51 0.0070257 1.264E-03 0.29 0.00331144 8.32E-11 5.0E-04 1.665E-07 Mn-54 0.00498828 6.944E-04 0.47 0.00304012 7.64E-11 3.0E-05 2.547E-06 Fe-59 0.0024194 1.233E-04 3.48 0.0085453 2.15E-10 1.0E-05 2.148E-05 Co-58 0.022029 1.958E-03 5.37 0.12029542 3.02E-09 2.0E-05 0.0001512 Co-60 0.01439996 2.343E-04 1.38 0.02010522 5.05E-10 3.0E-06 0.0001684 Sr-89 0.000191524 5.895E-05 22.45 0.00435847 1.10E-10 8.0E-06 1.369E-05 Sr-90 0.000021951 5.285E-06 13.49 0.00030145 7.58E-12 5.0E-07 1.515E-05 Sr-91 0.00028385 2.977E-05 1.86 0.00055851 1.40E-11 2.0E-05 7.018E-07 Y-90 0 0.000E+00 15.87 0 0.00E+00 7.0E-06 0 Y-91 8.99686E-05 4.086E-06 1115.17 0.1003347 2.52E-09 8.0E-06 0.0003152 Zr-95 0.00139032 1.640E-04 1.71 0.00253771 6.38E-11 2.0E-05 3.189E-06 Nb-95 0.002104792 1.223E-04 2.34 0.0050454 1.27E-10 3.0E-05 4.227E-06 Mo-99 0.0041958 1.356E-03 785.19 3.29583576 8.28E-08 2.0E-05 0.0041417 Te-132 0.00111174 3.999E-04 145.25 0.16188165 4.07E-09 9.0E-06 0.0004521 Ba-140 0.0102456 4.738E-03 0.31 0.00795345 2.00E-10 8.0E-06 2.499E-05 La-140 0.0162406 6.784E-03 0.06 0.00770681 1.94E-10 9.0E-06 2.152E-05 Ce-144 0.0068426 1.717E-03 0.08 0.00226954 5.70E-11 3.0E-06 1.901E-05 Pr-144 0 0.000E+00 0.08 0 0.00E+00 6.0E-04 0 H-3 1252.80 1 1252.80 3.15E-05 1.0E-03 0.0314864 H-3 (TPC) 3326.40 1 3326.40 8.36E-05 1.0E-03 0.0836019 Total 0.2675585 Total (TPC) 0.319674 Note 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).

11.2-40 U WASTE S STEMS

WATTS BAR W P-1 3 11.3. .3 ected aseous Waste Processing System Releases Gaseous 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 blan eting system. The gas decay tan capacity permits at least 60 days decay or waste gases be ore discharge during normal operation.

The uantities and isotopic concentration o gases discharged rom the GWPS ha e been estimated. The analysis is based on input sources to the GWPS per NUREG 0017, modi ied to re lect WBN plant-speci ic parameters.

The e pected gaseous releases in curies per year per reactor unit are gi en in Table 11.3-5.

11.3. . Releases from entilation Systems A detailed re iew o the entire plant has been made to ascertain those items that could possibly contribute to airborne radioacti e releases.

During normal plant operations, airborne noble gases and/or iodines can originate rom reactor coolant lea age, e uipment drains, enting and sampling, secondary side lea age, condenser air e ector and gland seal condenser e hausts, and GWPS lea age.

The assumptions used to estimate the annual uantity o radioacti e gaseous e luents are gi en 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.

Replace with "7" 11.3. .5 stimated Total Releases The estimated releases listed in Table 11.3-7c ha e been used in calculating the site boundary doses as shown in Table 11.3-10. Table 11.3-7a is the e pected 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 e pected gases released or 1 ailed uel with continuous iltered containment ent, and Table 11.3-7c or appro imately 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 ob ecti es 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 Replace with "based on ANSI N18.1-1984" Gaseous radioacti e wastes are released to the atmosphere through ents located on the Shield Building, Au iliary Building, Turbine Building, and Ser ice Building. A brie description, including unction and location o each type ent, is presented below.

ASEOUS WASTE S STEMS 11.3-7

WATTS BAR W P-1 2 No. 4 - Replace with:

Turbine Building Vents Shield uilding ent Gaseous wastes from the condenser are discharged through the condenser vacuum Wastevent.

exhaust gases Therom containment vent, which is a purge and 12-inch the waste diameter pipe,gas decay tanats approximately discharges are discharged theto760-foot the en ironment through level. Under normal a Shield Building operating ent. Each conditions Shield Building the discharge haswill flow rate onetypically ent.

The ent is o be less than 45 cfm.rectangular cross section (dimension - 2 eet by 7 eet 6 inches) and discharges appro imately 130 eet abo e ground le el. The location o the Reactor Building entsventilation Non-radioactive is shown in airthe e uipment from is exhausted layoutthe drawings, Turbine Figure Building1.2-1.

throughThethe location o theBuilding Turbine Shield Building in relation vents. There to the site are eighteen is shown vents at theon the main 755-foot plant level andgeneral twentyplan, vents Figure 2.1-5. All releases rom the Shield Building ent e cept containment purge air at the 824-foot level (roof level). The effluent flow rates vary for each type of vent.

e haust monitor discharges are passed through HEPA ilters and charcoal adsorbers Generally, the normal flow rates through a typical vent at the 755-foot level is 22,888 cfm prior to release. The e luent discharge rate through the ent is ariable occasionally, and the flow rates through typical vent at the 824-foot level is 28,500 cfm. The general during containment purge, the rate may approach the alue which is listed in Figure arrangement of vents on the Turbine Building is shown on Figure 1.2-1. The turbine 9.4-28. The low path or waste gases e hausted through the ent rom the waste gas building is shown on the main plant general plan, Figure 2.1-5.

decay tan s is shown in Figure 11.3-1.

Au iliary uilding ent Waste gases in the Au iliary Building are discharged through the Au iliary Building e haust ent. In addition, containment atmosphere is continuously ented, during normal operation or pressure control, into the annulus a ter it is iltered through HEPA and charcoal ilters, and subse uently, discharged into the Au iliary Building e haust ent. The ent is o the chimney type ha ing a rectangular cross section o 10 by 30 eet. The top o the ent is located atop the Au iliary Building and discharges appro imately 106 eet abo e grade. Under normal operating conditions, gases are continuously discharged through the ent. E luent low rates can be near 224,000 c m when two Au iliary Building general e haust ans and one uel-handling area e haust an are operating at ull capacity. Under accident conditions, the Au iliary Building is isolated, and the Au iliary Building gas treatment system (ABGTS) is used to treat gaseous e luents. When in ser ice, the ABGTS discharges to the Shield Building e haust ent. The location o the Au iliary Building e haust ent is shown in the e uipment layout diagram, Figure 1.2-1. The Au iliary Building is shown on the main plant general plan, Figure 2.1-5.

Turbine uilding ents Ventilation air is e hausted rom the Turbine Building through the Turbine Building ents. There are eighteen ents at the 755- oot le el and twenty ents at the 824- oot le el (roo le el). The e luent low rates ary or each type o ent. Generally, the normal low rates through a typical ent at the 755- oot le el is 22,888 c m and the low rates through typical ent at the 824- oot le el is 28,500 c m. 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 ent Gaseous wastes rom the condenser are discharged through the condenser acuum e haust ent. The ent, which is a 12-inch diameter pipe, discharges at appro imately the 760- oot le el. Under normal operating conditions the discharge low rate will typically be less than 45 c m.

11.3-8 ASEOUS WASTE S STEMS

WATTS BAR W P-1 3 Insert the following: "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 Ser ice uildingeffectsent due to the river valley location of the plant."

Radiologically monitored potentially radioacti e waste gases rom the radiochemical laboratory and the titration room are e hausted through HEPA ilters ia a common duct which discharges to the common Ser ice Building roo e haust plenum. E haust air rom the general area discharges to the common Ser ice Building roo e haust plenum. Separate ents rom the common roo e haust plenum discharge to atmosphere appro imately 24 eet abo e grade. The Ser ice Building is shown on the site plot plan, Figure 2.1-5.

Replace with "batch" 11.3. Atmos heric Dilution Calculations o atmospheric transport, dispersion, and ground deposition are based on the straight-line air low model discussed in NRC Regulatory Guide 1.111 (Re ision 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 Au iliary Building (AB) ents are treated as ground le el. The ground le el oint re uency distribution ( FD) is gi en in Section 2.3. Air concentrations and deposition rates were calculated considering radioacti e decay and buildup during transit. Plume depletion was calculated using the igures pro ided in Regulatory Guide 1.111.

Estimates o normalized concentrations (X/ ) and normalized deposition rates (D/ )

Insert the following asorparagraph gaseous releases lead-in:at"Table points where 11.3-8potential providesdose thepathways receptor elocations ist are listed for in Table 11.3-8.

performing the dose assessments in this chapter. The data is based on the 2007 land use survey. The TAF, X/Q, 11.3.1 and D/Q stimated for each Doses fromreceptor are calculated Radionuclides for the locations in aseous ffluentsbased on this survey. The TAF presented in Table 11.3-8 were developed on the same basis that Indi iduals are e posed to gaseous e luents ia the ollowing pathways (1) e ternal was used for Unit 1 licensing. Meteorology data from the 1986 to 2005 time period was radiation rom radioacti ity in the air and on the ground (2) inhalation and (3) ingestion used in the developmento bee of, the X/Qs and egetables, D/Qs."

and mil . No other additional e posure pathway has been identi ied which would contribute 10 or more to either indi idual or population doses.

Delete 11.3.1 .1 Assum tions and Calculational ethods Replace with "2007" E ternal air e posures are e aluated at points o potential ma imum e posure (i.e.,

points at the unrestricted area boundary). E ternal s in and total body e posures are e aluated at nearby residences. The dose to the critical organ rom radioiodines, tritium (Unit 1 only) and particulates is calculated or real pathways e isting at the site during a land use sur ey conducted in 1994.

To e aluate the potential critical organ dose, mil animals and nearest gardens were identi ied by a detailed sur ey within i e miles o the plant (Table 11.3-8). In ormation on grazing seasons and eeding regimes are re lected in the eeding actor. The eeding actor is the raction o the year an animal grazes on pasture. During the 1994 land use sur ey, there was one mil cow location identi ied in which in ormation regarding the eeding regime or the animals, and the ages o onsite consumers o the mil could not be established. Because no speci ic in ormation is nown, it is conser ati ely assumed that the eeding actor or that location is e ual to the worst-ASEOUS WASTE S STEMS 11.3-9 Replace with insert from next page

WATTS BAR W P-1 3 case eeding actor identi ied 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 speci ic data on bee animals were not a ailable, the nearest bee animal was assumed to be at the point o ma imum o site e posure. 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 household. TVA assumes that enough meat is produced in each sector annulus to supply the needs o that region. Watts Bar pro ected population distribution or the year 2040 is gi en in Table 11.3-9.

Doses are calculated using the dose actors and methodology contained in NRC Regulatory Guide 1.109 with certain e ceptions as ollows (1) Inhalation doses are based on the a erage indi iduals inhalation rates ound in ICRP Publication 23 o 1,400 5,500 8,000 and 8,100 m3/year or in ant, child, teen, and adult, respecti ely.

(2) The mil ingestion pathway has been modeled to include speci ic in ormation on grazing periods or mil animals obtained rom a detailed arm sur ey. A eeding actor (FF) has been de ined as that raction o total eed inta e 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 radioacti ity in stored eed are ad usted to re lect radioacti e decay during the ma imum assumed storage period o 180 days by the actor Insert the following here and onto the preceding page: "The calculation assumes feeding factor of 0.65 for all cow receptors in the 2007 LUS. The value is taken from Figure 2.2 in NUREG/

CR-4653 "GASPAR II - Technical Reference and User Guide," 1987 that provides the growing 180 season across the US. The value chosen 1 is on the high 1end - e for p -the O i 180 middle Tennessee Valley.

180 ³ support The LUS and publicly available information--------

- exp - O t d t = ----------------------------------------

i that this is a conservative - feeding factor.

180O i Supplemental feed is assumed to be grown 0 in the vicinity of Watts Bar and have the same nuclide source as the pasture."

This actor replaces the actor e p (-i th) in e uation C-10 o Regulatory Guide 1.109.

(3) The stored egetable and bee ingestion pathways ha e been modeled to re lect more accurately the actual dietary characteristics o indi iduals. For stored egetables the assumption is made that home grown stored egetables are consumed when resh egetables are not a ailable, i.e.,

during the 9 months o all, winter, and spring. Rather than use a constant 11.3-10 ASEOUS WASTE S STEMS

WATTS BAR W P-1 3 Replace with "11.3-11 and 11.3-12" Category Ages (A)* Fraction Teen 13 A 19 0.153 Adult 19 A 0.665

• e.g., someone who is 1 year, 11 months is an in ant, while someone who is e actly two years old is a child.

Tables 11.3-10 and 11.3-11 pro ide the doses estimated or indi iduals and the population within 50 miles o the plant site.

Replace with "1,500,000" 11.3.1 .2 Summary of Annual Po ulation Doses TVA has estimated the radiological impact to regional 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 bac ground to indi iduals within the United States ranges rom appro imately 100 mrem to 250 mrem per year. The annual total body dose due to bac ground or a population o about 1,100,000 persons e pected to li e within a 50 mile radius o the Watts Bar Nuclear Plant in the year 2040 is calculated to be appro imately 154,000 man-rem assuming 140 mrem/year/indi idual. By comparison, the same population (e cluding onsite radiation wor ers) will recei e a total body dose o appro imately 3.85 man-rem rom e luents. Based on these results, TVA concludes that the normal operation o the Watts Bar Nuclear Plant will present minimal ris to the health and sa ety o the public.

R F R C S Replace with "210,000" None Replace with "6.66" Insert with "TVA assumes that enough fresh vegetables are produced at each residence to supply annual consumption by all members of that household. TVA assumes that enough meat is produced in each sector annulus to supply the needs of that region. Watts Bar projected population distribution for the year 2040 is given in Table 11.3-9. Vegetable ingestion is the critical pathway."

11.3-12 ASE US WASTE SYSTEMS

WATTS BAR W P-1 3 Table 11.3- Radioacti e 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 Core based on 3480 MWt)

2. Primary and secondary side coolant and steam acti ities are based on NUREG-0017 and ha e been plant ad usted or WBN speci ic parameters.

3. RCS water parameters Volume = 11,375 t3 Replace with "ANSI N18.1" Press. = 2250 psia Temp. = 588.2 F Replace with "WGDT" Spec. Vol. = 0.02265 t3/lb

4. Containment releases are iltered through a HEPA and charcoal ilter with minimum iltration e iciencies o 99 and 70 , respecti ely.

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 airborne atmosphere.

6. WCDT releases are based on a 173 t3/day ( STP) input o RCS coolant o gas to the waste gas disposal system and a WGDT holdup time o 60 days.

7. Au iliary Building (AB) entilation noble gas source terms are based on a 160 lb/day release o RCS coolant acti ity 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. Re ueling Area iodine releases are based on 0.16 Ci/yr per Ci/gm o RCS or 300 days and 0.3 Ci/yr per Ci/gm or 65 days.

10. Turbine Building (TB) entilation noble gas source 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 300 days and 1400 Ci/yr per Ci/gm or 65 days.

12. Condenser acuum e haust noble gas source terms are based on a steam lowrate to the condenser o 8.5E6 lb/hr at secondary steam acti ities.

13. Condenser acuum e haust iodine source terms are based on a 3500 Ci/yr per Ci/gm o secondary steam released to the condenser acuum e haust.

14. Steam generator blowdown lash tan source terms are based on a ma imum steam generator blowdown low o 12.5 gpm/steam generator. Iodines are urther reduced in the o gases 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 the 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 a ailable or release ia gaseous pathways.

17. Total particulate releases are ta en directly rom Table 2-17 o NUREG-0017. Since these alues are prior to treatment, the releases rom the Containment Building either through the purge air, or containment ent ilters, are reduced by applying a HEPA iltration actor o 0.01 (99 e iciency).

ASE US WASTE SYSTEMS 11.3-19

WATTS BAR W P-1 3 Table 11.3- Radioacti e aseous ffluent Parameters (Page 2 of 2)

18. 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 (e iciency o 99 ) and charcoal (e iciency 70 ) ilter prior to release.

20. NUREG-0017 suggests 22 containment purges a year during power operation, and 2 purges during re ueling. Howe er, one purge e ery two wee s will be used in the calculation. In addition, continuous containment ent with 100 c m will be e aluated.

Replace with "A continuous filtered containment vent of 100 cfm is the expected normal release and is evaluated. A separate evaluation assuming one purge every two weeks will be performed. NUREG-0017 suggests 22 containment purges a year during power operation, and 2 purges during refueling."

11.3-20 ASE US WASTE SYSTEMS

WATTS BAR W P-1 3 ANSI N18.1-1984 Table 11.3- c Total Releases (y 1 failed fuel in Ci yr), ith Continuous Filtered Containment ent (Sheet 1 of 1)

Table based on operation o one unit Contain.(1) Au . Turbine Total Nuclide Building Building Building r-85m 3.72E+00 4.53E+00 1.23E+00 9.48E+00 r-85 6.69E+02 7.05E+00 1.86E+00 6.78E+02 r-87 4.48E-01 4.27E+00 1.09E+00 5.81E+00 r-88 3.10E+00 7.95E+00 2.13E+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-41 3.40E+01 0.00E+00 0.00E+00 3.40E+01 Br-84 8.16E-07 5.02E-02 4.81E-04 5.07E-02 I-131 6.74E-03 1.39E-01 7.08E-03 1.53E-01 I-132 1.36E-04 6.56E-01 1.70E-02 6.73E-01 I-133 2.36E-03 4.35E-01 2.03E-02 4.57E-01 I-134 4.26E-05 1.06E+00 1.47E-02 1.07E+00 I-135 8.80E-04 8.10E-01 3.13E-02 8.42E-01 H-3 1.39E+02 0.00E+00 0.00E+00 1.39E+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 Ru-103 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 3.95E-05 C-14 2.80E+00 4.50E+00 0.00E+00 7.30E+00 (TPC) Tritium alues or a Tritium Production Core (Unit 1 only)

Delete 11.3-26 ASE US WASTE SYSTEMS

WATTS BAR W P-1 3 Table 11.3- Data On Points Of nterest ear Watts ar uclear Plant (Page 1 of 2)

Chi-o er- D-o er- Terrain il Distance (s m 3) (1 m 2) Ad ustment Feeding Sector ( eters) Factor Factor Unrestricted Area Boundary N 1550 5.12e-06 8.13e-09 1.70 Unrestricted Area Boundary NNE 1980 6.35e-06 1.23e-08 1.80 Unrestricted Area Boundary NE 1580 1.05e-05 1.10e-08 2.10 Unrestricted Area Boundary ENE 1370 1.23e-05 8.77e-09 1.70 Unrestricted Area Boundary E 1280 1.37e-05 9.66e-09 1.60 Unrestricted Area Boundary ESE 1250 1.43e-05 1.16e-08 1.80 Unrestricted Area Boundary SE 1250 1.11e-05 9.49e-09 1.50 Unrestricted Area Boundary SSE 1250 6.04e-06 8.21e-09 1.50 Unrestricted Area Boundary S 1340 5.33e-06 1.17e-08 1.90 Unrestricted Area Boundary SSW 1550 4.14e-06 1.05e-08 2.00 Unrestricted Area Boundary SW 1670 4.46e-06 7.34e-09 2.10 Unrestricted Area Boundary WSW 1430 5.47e-06 6.37e-09 1.80 Replace with "Nearest Garden" Unrestricted Area Boundary W NE1460 3353 3.84e-06 2.11e-06 3.22e-09 2.07e-09 1.20 2.20 Replace with "Nearest Unrestricted Garden" Area Boundary WNW E1400 6372 1.35e-06 2.49e-06 5.42e-10 2.38e-09 2.50 1.40 Replace with "Nearest Unrestricted Garden" Area Boundary NW ESE 1400 4758 2.26e-06 2.05e-06 1.21e-09 2.13e-09 1.70 1.80 Replace with "Nearest Garden" Unrestricted Area Boundary NNW SSE 1460 7454 3.73e-07 2.68e-06 2.80e-10 3.08e-09 1.60 1.10 Resident N 2134 2.84e-06 4.21e-09 1.50 Resident NNE 3600 2.69e-06 4.41e-09 1.80 Resident NE 3353 3.84e-06 3.22e-09 2.20 Resident ENE 2414 6.26e-06 3.83e-09 1.90 Resident E 3268 3.97e-06 2.14e-09 1.70 Resident ESE 4416 2.64e-06 1.46e-09 1.90 Resident SE 1372 9.66e-06 8.16e-09 1.50 Insert Resident SSE 1524 4.18e-06 5.56e-09 1.40 "Nearest" in Resident S 1585 3.91e-06 8.42e-09 1.80 front of each Resident SSW 1979 2.76e-06 6.64e-09 1.90 listing. Resident SW 4230 1.15e-06 1.43e-09 2.00 Resident WSW 1829 3.61e-06 4.03e-09 1.70 Resident W 2896 7.30e-07 6.01e-10 1.10 Resident WNW 1646 2.26e-06 2.12e-09 2.90 Resident NW 2061 1.03e-06 9.95e-10 1.50 Resident NNW 4389 3.50e-07 2.97e-10 1.00 Garden N 7664 3.13e-07 3.00e-10 1.00 Garden NNE 6173 1.06e-06 1.42e-09 1.50 Garden NE 3829 3.06e-06 2.44e-09 2.10 Garden ENE 4927 2.01e-06 9.39e-10 1.60 Garden E 4991 1.99e-06 9.02e-10 1.50 Garden ESE 6096 1.63e-06 7.77e-10 1.80 Garden SE 4633 1.58e-06 8.97e-10 1.30 Garden SSE 7454 4.74e-07 3.57e-10 1.40 Garden S 2254 2.50e-06 4.94e-09 1.90 ASE US WASTE SYSTEMS 11.3-27

WATTS BAR W P-1 3 Table 11.3- Data On Points Of nterest ear Watts ar uclear Plant (Page 2 of 2)

Chi-o er- D-o er- Terrain il Distance (s m 3) (1 m 2) Ad ustment Feeding Sector ( eters) Factor Factor Garden SSW 8100 2.79e-07 4.16e-10 1.40 Garden SW 8100 4.28e-07 4.03e-10 1.80 Garden WSW 4667 9.86e-07 8.06e-10 1.70 Garden W 5120 3.33e-07 2.23e-10 1.10 Garden WNW 5909 1.85e-07 1.13e-10 1.40 Garden NW 3170 5.63e-07 4.78e-10 1.50 Garden NNW 4698 3.18e-07 2.64e-10 1.00 Mil Cow ESE 6096 1.63e-06 7.77e-10 1.80 0.25 Mil Cow ESE 6706 1.35e-06 6.18e-10 1.70 0.03 Mil Cow SSW 2286 2.24e-06 5.20e-09 1.90 0.05 Mil Cow SSW 3353 1.36e-06 2.84e-09 2.00 0.33 Replace with "Nearest Garden" SSW 1979 2.76e-06 6.64e-09 1.90 Replace with "Nearest Garden" SW 8100 4.28e-07 4.03e-10 1.80 Replace with "Nearest Garden" WSW 4667 8.70e-07 7.11e-10 1.50 Replace with "Nearest Garden" W 5120 3.03e-07 2.03e-10 1.00 Replace with "Nearest Garden" WNW 5909 1.72e-07 1.05e-10 1.30 Replace with "Nearest Garden" NW 3170 4.13e-06 3.50e-10 1.10 Replace with "Nearest Garden" NNW 4602 3.28e-07 2.74e-10 1.00 Milk Cow ESE 6706 1.35e-06 6.18e-10 1.70 0.65 Milk Cow SSW 2286 2.24e-06 5.20e-09 1.90 0.65 Milk Cow SSW 3353 1.36e-06 2.84e-09 2.00 0.65 11.3-28 ASE US WASTE SYSTEMS

Table 11.3- Pro ected 2 Po ulation Distribution Within 5 iles Of Watts ar uclear Plant Po ulation Within ach Sector lement Distance From Site ( iles)

-1 1-2 2-3 3- -5 5-1 1 -2 2 -3 3 - -5 0 111 32 47 135 893 2071 2166 3453 4040 0 25 25 76 43 796 8591 19187 9342 1194 0 0 130 208 130 861 3381 19210 30623 54111 WATTS BAR 0 2 55 53 78 252 2445 9497 38457 136395 S 0 2 7 53 38 482 9716 8837 10649 17404 ASE US WASTE SYSTEMS S 0 2 4 47 58 591 4514 12085 3420 300 SS 0 0 16 35 29 505 17835 10818 3969 3756 S 12 23 3 27 24 714 4018 8056 3899 6362 SSW 0 54 14 24 257 1368 1141 34699 40812 11522 SW 0 34 7 19 32 739 5653 17523 25829 117868 WSW 0 0 5 2 0 519 6490 9411 68565 125338 W 0 10 40 38 30 1281 10369 2091 7134 6571 W W 2 5 19 59 65 837 965 5337 2839 2035 W 5 30 10 140 121 244 1461 2925 3440 17598 W 0 10 111 113 387 2279 314 7266 7004 9802 Total 0 0 62 87 98 2081 874 18279 4784 2983 19 308 540 1028 1525 14442 79838 187387 264219 517279 Replace with attached revised W

table 11.3-29 P-1 2

Table 11.3-Pro ected 2 Po ulation Distribution Within 5 iles of Watts ar uclear Plant Po ulation 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 New Data for Table 11.3.9

WATTS BAR W P-1 3 Replace with "Bone" Table 11.3-1 Watts ar uclear Plant- ndi idual Doses From aseous ffluents (For 1 Unit ithout TPC)

E luent Pathway Guideline* Location Dose Noble Gases  Air dose 10 mrad Ma imum E posed 0.801 mrad/yr Indi idual1

 Air dose 20 mrad Ma imum E posed 2.710 mrad/yr Replace Indi idual1 with Total body 5 mrem Ma imum Residence2,3 0.571 mrem/yr 9.15 S in 15 mrem Ma imum Residence2,3 1.540 mrem/yr Iodines/ Thyroid 15 mrem Ma imum Real 2.715 mrem/yr Particulates (critical organ) Pathway4 Replace with rea do n of odine Particulate Doses (mrem yr) Replace with Total Vegetable Ingestion Cow Mil with "6.57 Feeding Factor o 0.33 2.44 Inhalation 0.174 0.0704 Ground Contamination 0.0405 0.0947 Submersion 0.0603 0.130 Bee Ingestion1 0.0 Total Replace with "5" 2.7148 2.28 Guidelines are de ined in Appendi I to 10 CFR Part 50.

9.145 mrem/yr" 1

Ma imum e posure point is at 1250 meters in the SE sector. Replace with 2

Dose rom air submersion.

"ESE" 3

Ma imum e posed residence is at 1372 meters in the SE sector.

4 Ma imum e posed indi idual is an in ant at 3353 meters in the SSW sector.

Replace with "1979" Replace with "a child" Insert the following: "5Maximum dose location for all receptors is 1250 meters in the ESE sector."

11.3-30 ASE US WASTE SYSTEMS

WATTS BAR W P-1 3 Table 11.3-11 Summary Of Po ulation Doses T RO D In ant Child Teen Adult Total Submersion 8.28E-02 1.59E-01 1.44E-01 6.28E-01 9.45E-01 Ground 3.11E-03 3.49E-02 3.17E-02 1.38E-01 2.08E-01 Inhalation 7.45E-02 1.39E-00 7.44E-01 2.64E+00 4.85E+00 Cow Mil Ingestion 4.09E-01 1.98E-00 8.42E-01 1.60E-00 4.83E+00 Bee Ingestion 0.00E+00 3.52E-01 1.77E-01 8.93E-01 1.42E-00 Vegetable Ingestion 0.00E+00 1.18E-00 4.76E-01 1.26E-01 2.92E+00 Total man-rem 5.01E-01 5.10E+00 2.42E+00 7.15E+00 1.52E+01 TOTAL OD In ant Child Teen Adult Total Submersion 1.42E-02 1.59E-01 1.44E-01 6.28E-01 9.45E-01 Ground 3.11E-03 3.49E-02 3.17E-02 1.38E-01 2.08E-01 Inhalation 4.28E-03 1.14E-01 7.23E-02 2.99E-01 4.90E-01 Cow Mil Ingestion 1.14E-01 6.30E-01 2.39E-01 4.25E-01 1.41E-00 Bee Ingestion 0.00E+00 3.36E-01 1.69E-01 8.52E-01 1.36E-00 Vegetable Ingestion 0.00E+00 1.20E-00 5.08E-01 1.42E-00 3.12E+00 Total man-rem 1.36E-01 2.47E+00 1.16E-00 3.76E+00 7.53E+00 Replace with information provided by the following page ASE US WASTE SYSTEMS 11.3-31

Table 11.3-11 Summary of Population Doses THYROID I Tee A T S e 1 e-0 1 1e-01 1 8e-01 e-01 8 8e-01 G 1e-0 e-0 e-0 1 0 e-01 1 e-01 I e-0 1 e 00 e-01 e 00 e-00 I e e-01 1 e 00 e-01 1 e 00 81e 00 Bee I e 0 00e 00 1 e-01 1 e-01 8 0 e-01 1 8e 00 e e eI e 0 00e 00 1 0 e 00 1 e-01 1 0 e 00 e 00 T -e 0 e-01 e 00 0 e 00 1 e 00 1 0e 01 TOTAL BODY I Tee A T S e 1 e-0 1 1e-01 1 8e-01 e-01 8 8e-01 G 1e-0 e-0 e-0 1 0 e-01 1 e-01 I e-0 1 0 e-01 e-0 e-01 e-01 I e 1 0 e-01 e-01 1 e-01 8 e-01 1 8e 00 Bee I e 0 00e 00 0 e-01 1 e-01 e-01 1 e 00 e e eI e 0 00e 00 1 0 e 00 0e-01 1 1e 00 0e 00 T -e 1 e-01 0e 00 1 0 e 00 1e 00 e 00 Use this data to replace information in preceding table.

Enclosure 2, 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

WATTS BAR

11. RAD OACT WAST A A T 11.1 SOURC T R S The ission product in entory in the reactor core and the di usion to the uel pellet/cladding gap are presented in Section 15.1.7.

11.1.1 istorical Design odel for Radioacti ities in Systems and Com onents This section and associated Tables 11.1-1 through 11.1-5 present results o the original Westinghouse Design Calculations using methodology in Re erences 2 and 3 . The results are presented as bac ground 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 Acti ity The parameters used in the calculation o the reactor coolant ission product design in entories together with the pertinent in ormation concerning the design reactor coolant cleanup low rate and demineralizer e ecti eness, 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 de ecti e uel rods are assumed to be present at the initial core loading and to be uni ormly distributed throughout the core thus, the ission product escape rate coe icient are based upon a erage uel temperature.

For uel ailure and burnup e perience, see Section 4.2.1.3.3.

The ission product acti ities in the reactor coolant during operation with small cladding de ects ( uel rods containing pin-holes or ine crac s) are computed using the ollowing di erential e uations or parent nuclides in the coolant dN wi

---

= DQ i N c - § O i + RK i + --------------------* N wi B

dt i © B o - tBc¹ or daughter nuclides in the coolant dN w

---

= DQ N c - § O --------------------* N w B

RK O i N wi dt © B o - tB ¹ symbols N = nuclide concentration D = clad de ects, as a raction o rated core thermal power being generated by rods with clad de ects R = puri ication low, coolant system olumes per sec.

Bo = initial boron concentration, ppm S UR E TERMS 11.1-1

WATTS BAR B = boron concentration reduction rate by eed and bleed, ppm per sec.

 = remo al e iciency o puri ication cycle or nuclide

 = radioacti e decay constant I = escape rate coe icient or di usion into coolant t = elapsed time (seconds) since the beginning o cycle subscripts C = re ers to core w = re ers to coolant i = re ers to parent nuclide

= re ers to daughter 11.1.1.2 olume Control Tan istorical Design Acti ity Table 11.1-3 lists the acti ities in the olume control tan using the assumptions summarized in Table 11.1-1.

11.1.1.3 Pressuri er istorical Design Acti ity The acti ities in the pressurizer are separated between the li uid and the steam phase and the results obtained are gi en in Table 11.1-4 using the assumptions summarized in Table 11.1-1.

11.1.1. aseous Waste Processing System istorical Design Acti ities The acti ities to be ound in the Gaseous Waste Processing System are gi en in Table 11.1-5.

11.1.1.5 Secondary Coolant istorical Design Acti ities The secondary cleanup system design acti ities used or shielding design calculations are discussed in Subsection 12.2.1.5.

11.1.2 Realistic odel for Radioacti ities in Systems and Com onents This section and associated Tables 11.1-6 and 11.1-7 present results which supersede the calculations in the pre ious 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 a ailable in a orm that could permeate through the TPBAR cladding. Howe er, it is assumed that while operating with a Tritium Production Core (TPC), some o the tritium in entory in the TPBARs may permeate the 11.1-2 S UR E TERMS

WATTS 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 ma imum number o TPBARs is 2,304 Ci/year into the Reactor Coolant System.

The parameters used to describe Watts Bar are gi en in Table 11.1-6 together with the nominal alues gi en in ANS-18.1-1984. In order to obtain primary coolant acti ities, the correction ormula rom ANSI/ANS-18.1-1984 1 , was applied to the acti ities listed in Re erence 1 . Secondary side water and steam acti ities were similarly obtained rom the alues gi en in Re erence 1 .

The speci ic acti ities or primary and secondary sides are calculated by ANSI/ANS-18.1-1984 1 methodology and gi en in Table 11.1-7.

11.1.3 Plant Lea age As a necessary part o the e ort to reduce e luent o radioacti e li uid wastes, Westinghouse sur eyed arious PWR acilities which are in operation, to identi y design and operating problems in luencing reactor coolant and nonreactor grade lea age and hence the load on a waste processing system. Li uid lea age sources ha e been identi ied primarily in connection with pump sha t seals and al e stem lea age.

Where pac ed glands are pro ided, lea age may be anticipated, while mechanical sha t seals pro ide essentially zero lea age. Val e stem lea age was e perienced where the originally speci ied pac ing was used. A combination o a graphite ilament yarn pac ing sandwiched with asbestos sheet pac ing is used with impro ed results in se eral plants. For Watts Bar the ma ority o the al es used are diaphragm al es.

This type o al e pro ides positi e control stem lea age and is suitable or use as an isolation al e as well as a throttling al e.

E pected lea age rates o li uids to be treated in the li uid waste processing system are summarized in Table 11.2-1.

Total plant li uid and gaseous releases are discussed in Subsections 11.2.6 and 11.3.7, respecti ely.

11.1. Additional Sources During normal operation, the sources o radioacti e material not normally considered part o the radioacti e waste system are as ollows (1) Containment Purging System (2) Turbine Gland Sealing System (3) Main Condenser E acuation System S UR E TERMS 11.1-3

WATTS BAR (4) Au iliary Building Ventilation System (5) Turbine Building Ventilation System (6) Steam Generator Blowdown System Estimates or the release o radioacti e materials rom sources 1 through 5 (abo e) are presented in Section 11.3.7. The release paths and transport mechanism or these sources o radioacti e material are also presented in Section 11.3.8.

The Steam Generator Blowdown System (SGBS) is another source o li uid radioacti e material that is not normally considered part o the radioacti e 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 e aluating the radiological conse uences o li uid releases rom steam generator blowdowns is the path to the ri er ia the cooling tower blowdown line. This route is used primarily during periods when there is no signi icant primary to secondary lea age. The discharge to the ri er is monitored or radioacti ity as speci ied in Section 11.4. An alarm in the Main Control Room alerts the operator o an increasing radioacti ity le el in the discharge.

I the radiation setpoint is e ceeded, the blowdown discharge is automatically di erted to the condensate demineralizers. The basis or the setpoint is presented in Section 11.4.

References (1) ANSI/ANS-18.1-1984, Radioacti e 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 Corporation, Pittsburgh, Pa. 15230, April 1974.

(3) WCAP-7664, R1 Radiation Analysis Design Manual Loop Plant ,

October 1972.

11.1-4 S UR E TERMS

WATTS BAR Table 11.1-1 Parameters Used n The Calculation of Reactor Coolant Fission and Corrosion Product istorical Design Acti ities (Page 1 of 2)

1. Core thermal power, MWt 3565

2. Clad de ects, as a percent o rated core thermal power being generated by rods with clad de ects 1.0

3. Reactor coolant li uid olume, t3 11,781

4. Reactor coolant ull power a erage temperature, F 588

5. Puri ication low rate (normal) gpm 75

6. E ecti e cation demineralizer low, gpm 7.5

7. Volume control tan olumes a.Vapor, t3 240 b.Li uid, t3 160

8. Fission product escape rate coe icients

• a.Noble gas isotopes, sec-1 6.5 10-8 b.Br, I and Cs isotopes, sec-1 1.3 10-8 c.Te isotopes, sec-1 1.0 10-9 d.Mo isotopes, sec-1 2.0 10-9 e.Sr and Ba isotopes, sec-1 1.0 10-11

.Y, La, Ce, Pr isotopes, sec -1 1.6 10-12

9. Mi ed bed demineralizer decontamination actors a.Noble gases and Cs-134, 136, 137 Y-90, 91 and Mo-99 1.0 b.All other isotopes including corrosion products 10.0

10. Cation bed demineralized decontamination actor or Cs-134, 136, 137, Y-90, 91, Mo-99 10.0

• Escape rate coe icients are based on uel de ect tests per ormed at the Sa ton Reactor.

E perience at two plants operating with uel rod de ects has eri ied the listed escape rate coe icients.

S UR E TERMS 11.1-5

WATTS BAR Table 11.1-1 Parameters Used n The Calculation of Reactor Coolant Fission and Corrosion Product istorical Design Acti ities (Page 2 of 2)

11. Volume control tan noble gas stripping ractions Stri ing Fraction soto e r-85 2.3 X 10-5 r-85m 2.7 X 10-1 r-87 6.0 X 10-1 r-88 4.3 X 10-1 Xe-131m 7.1 X 10-3 Xe-133 1.6 X 10-2 Xe-133m 3.7 X 10-2 Xe-135 1.8 X 10-1 Xe-135m 8.0 X 10-1 Xe-138 1.0

12. Boron concentration and reduction rates

a. Bo (initial cycle) 860 B (initial cycle) 3.0 ppm/day

b. Bo (e uilibrium cycle) 1200 ppm B (e uilibrium cycle) 4.0 ppm/day

13. Pressurizer olumes

a. Vapor 720 t3

b. Li uid 1080 t3

14. Spray line low 1.0 gpm

15. Pressurizer stripping ractions

a. Noble gases 1.0

b. All other elements 0 11.1-6 S UR E TERMS

WATTS BAR Table 11.1-2 Reactor Coolant quilibrium Fission And Corrosion Product istorical Design Acti ities soto e Acti ity Ci gm Br-84 4.2 10-2 Rb-88 3.7 Rb-89 1.0 10-1 Sr-89 3.8 10-3 Sr-90 1.1 10-4 Sr-91 1.9 10-3 Y-90 1.3 10-4 Y-91 5.5 10-3 Y-92 7.3 10-4 Zr-95 6.7 10-4 Nb-95 6.4 10-4 Mo-99 5.3 I-131 2.5 I-132 9.0 10-1 I-133 4.0 I-134 5.6 10-1 I-135 2.2 Te-132 2.6 10-1 Te-134 2.9 10-2 Cs-134 2.1 10-1 Cs-136 1.4 10-1 Cs-137 1.0 Cs-138 9.5 10-1 Ba-140 4.2 10-3 La-140 1.5 10-3 Ce-144 2.7 10-4 Pr-144 2.7 10-4 r-85 4.7 (Pea )

r-85m 2.2 r-87 1.2 r-88 3.7 Xe-131m 1.9 Xe-133 2.88 102 Xe-133m 3.2 Xe-135 6.3 Xe-135m 1.9 10-1 Xe-138 6.8 10-1 Mn-54* 7.7 10-4 Mn-56* 2.9 10-2 Co-58* 2.5 10-2 Co-60* 7.4 10-4 Fe-59* 1.0 10-3 Cr-51* 9.3 10-4

• Corrosion Product acti ities based on acti ity le els measured at operating reactors.

S UR E TERMS 11.1-7

WATTS BAR Table 11.1-3 quilibrium olume Control Tan istorical Design Acti ities

( ased on arameters gi en in Table 11.1-1) soto e a or acti ity (Curies) r-85 7.6 r-85m 5.6 101 r-87 2.2 101 r-88 1.1 102 Xe-131m 8.8 101 Xe-133 1.4 104 Xe-133m 1.5 102 Xe-135 2.5 102 Xe-135m less than 1 Xe-138 4.6 Liquid acti ity (Curies)

I-131 1.1 I-132 0.41 I-133 1.8 I-134 0.26 I-135 1.0 11.1-8 S UR E TERMS

WATTS BAR Table 11.1- Pressuri er istorical Design Acti ities a or acti ity soto e ( Ci cc) r-85 5.1 101 r-85m 1.0 10-1 r-87 1.8 10-2 r-88 1.2 10-1 Xe-131m 4.7 Xe-133 3.6 102 Xe-133m 1.8 Xe-135 6.5 10-1 Xe-135m 5.0 10-4 Xe-138 2.2 10-3 Liquid acti ity

( Ci gm)

Rb-88 1.1 10-2 Mo-99 2.2 I-131 1.6 I-132 2.0 10-2 I-133 0.7 I-134 5.5 10-3 I-135 0.14 Cs-137 1.3 Cs-138 5.5 10-3 S UR E TERMS 11.1-9

WATTS BAR Table 11.1-5 istorical Design n entory n The aseous Waste Processing System Single Unit Acti ity*

soto e (Curies) r-85 4.4 103**

r-85m 6.2 102 r-87 3.3 102 r-88 1.1 103 Xe-131m 5.7 102 Xe-133 8.7 104 Xe-133m 9.7 102 Xe-135 1.9 103 Xe-135m 4.8 101 Xe-138 1.8 102

• For two units, the acti ities are doubled

• • Represents the in entory o r-85 released to the reactor coolant during one year o ull power operation. The remaining isotopes are e uilibrium alues.

11.1-10 S UR E TERMS

Table 11.1- Parameters Used To Describe The Reactor Coolant System Realistic asis ominal A S-1 .1- 1 W Symbol Units Assum tion Analysis Assum tion S UR E TERMS Thermal power P MWt 3400 3582 WATTS BAR Steam low rate FS lb/hr 1.5E+07 1.5E+07 Weight o water in all reactor WP lb 5.5E+05 5.4E+05 coolant system Weight o water in all steam WS lb 4.50E+05 3.48E+05 generators Reactor coolant letdown low rate FD lb/hr 3.7E+04 3.7E+04 (puri ication)

Reactor coolant letdown low rate FB lb/hr 500 845 (yearly a erage or boron control)

Steam generator blowdown low FBD lb/hr 7.50E+04 3.00E+04 (a erage total)

Fraction o radioacti ity in NBD - 1.0 1.0 blowdown stream which is not returned to the secondary coolant system Flow through the puri ication FA lb/hr 3.7E+03 3.7E+03 system cation demineralizer Ratio o condensate demineralizer NC - 0.0 0.55 low rate to the total steam low rate Fraction o the noble gas Y - 0.0 0.0 acti ity in the letdown stream which is not returned to the reactor coolant system (not including the boron reco ery system) 11.1-11

WATTS BAR Table 11.1- S ecific Acti ities n Princi al Fluid Streams Realistic asis (Ci gm)

(Page 1 of 2)

Reactor Secondary Coolant soto e Coolant Water Steam Class 1 oble ases r-85m 1.71E-01 0.00E+00 3.63E-08 r-85 2.66E-01 0.00E+00 5.51E-08 r-87 1.61E-01 0.00E+00 3.22E-08 r-88 3.00E-01 0.00E+00 6.31E-08 Xe-131m 6.54E-01 0.00E+00 1.34E-07 Xe-133m 7.17E-02 0.00E+00 1.54E-08 Xe-133 2.53E+00 0.00E+00 5.25E-07 Xe-135m 1.39E-01 0.00E+00 2.90E-08 Xe-135 9.04E-01 0.00E+00 1.91E-07 Xe-137 3.65E-02 0.00E+00 7.62E-09 Xe-138 1.29E-01 0.00E+00 2.68E-08 Class 2 alogens Br-84 1.72E-02 9.56E-08 9.56E-10 I-131 4.77E-02 1.41E-06 1.41E-08 I-132 2.25E-01 3.37E-06 3.37E-08 I-133 1.49E-01 4.03E-06 4.03E-08 I-134 3.64E-01 2.93E-06 2.93E-08 I-135 2.78E-01 6.19E-06 6.19E-08 Class 3 Cs, Rb Rb-88 2.04E-01 7.36E-07 3.61E-09 Cs-134 7.39E-03 4.58E-07 2.36E-09 Cs-136 9.08E-04 5.56E-08 2.78E-10 Cs-137 9.79E-03 6.11E-07 3.05E-09 Class Water Acti ation Products N-16 4.00E+01 1.29E-06 1.29E-07 Class 5 Tritium H-3 1.00E+00 1.00E-03 1.00E-03 11.1-12 S UR E TERMS

WATTS BAR Table 11.1- S ecific Acti ities n Princi al Fluid Streams Realistic asis (Ci gm)

(Page 2 of 2)

Class Other soto es Na-24 4.99E-02 1.86E-06 9.30E-09 Cr-51 3.26E-03 1.56E-07 7.56E-10 Mn-54 1.68E-03 7.80E-08 3.96E-10 Fe-55 1.26E-03 5.88E-08 3.00E-10 Fe-59 3.16E-04 1.44E-08 7.32E-11 Co-58 4.84E-03 2.28E-07 1.13E-09 Co-60 5.58E-04 2.64E-08 1.32E-10 Zn-65 5.37E-04 2.52E-08 1.20E-10 Sr-89 1.47E-04 6.84E-09 3.48E-11 Sr-90 1.26E-05 5.88E-10 3.00E-12 Sr-91 1.02E-03 3.52E-08 1.76E-10 Y-90 1.26E-05 5.88E-10 3.00E-12 Y-91m 4.93E-04 4.34E-09 2.17E-11 Y-91 5.47E-06 2.52E-10 1.32E-12 Y-93 4.46E-03 1.50E-07 7.65E-10 Zr-95 4.10E-04 1.92E-08 9.48E-11 Nb-95 2.95E-04 1.32E-08 6.84E-11 Mo-99 6.75E-03 3.03E-07 1.45E-09 Tc-99m 5.01E-03 1.40E-07 7.27E-10 Ru-103 7.89E-03 3.72E-07 1.92E-09 Ru-106 9.47E-02 4.44E-06 2.16E-08 Rh-103 7.89E-03 3.72E-07 1.92E-09 Rh-106 9.47E-02 4.44E-06 2.16E-08 Ag-110m 1.37E-03 6.36E-08 3.24E-10 Te-129m 2.00E-04 9.36E-09 4.68E-11 Te-129 2.57E-02 2.96E-07 1.48E-09 Te-131m 1.59E-03 6.60E-08 3.30E-10 Te-131 8.26E-03 3.97E-08 2.05E-10 Te-132 1.79E-03 7.98E-08 3.99E-10 Ba-137m 9.79E-03 6.11E-07 3.05E-09 Ba-140 1.37E-02 6.25E-07 3.12E-09 La-140 2.64E-02 1.13E-06 5.60E-09 Ce-141 1.58E-04 7.32E-09 3.72E-11 Ce-143 2.96E-03 1.22E-07 6.23E-10 Ce-144 4.21E-03 1.92E-07 9.83E-10 Pr-143 2.96E-03 1.22E-07 6.23E-10 Pr-144 4.21E-03 1.92E-07 9.83E-10 W-187 2.65E-03 1.07E-07 5.40E-10 Np-239 2.32E-03 1.02E-07 5.09E-10 S UR E TERMS 11.1-13

WATTS BAR THIS PAGE INTENTIONALLY BLAN 11.1-14 S UR E TERMS

WATTS BAR 11.2 L U D WAST S ST S 11.2.1 D S O CT S The Li uid Waste Processing System is designed to recei e, segregate, process, and discharge li uid wastes. The system design considers potential personnel e posure and assures that uantities o radioacti e releases to the en ironment are as low as reasonably achie able. Under normal plant operation, the acti ity rom radionuclides lea ing 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, e en assuming e uipment aults which could occur with moderate re uency, including uel cladding de ects and ailures o up to two TPBARs (Unit 1 only) in combination with such occurrences as (1) Steam Generator tube lea s (2) Mal unction in Li uid Waste Processing System (3) E cessi e lea age in Reactor Coolant System E uipment (4) E cessi e lea age in Au iliary System E uipment The e pected annual acti ity releases (by isotope) are presented in Subsection 11.2.6, and the estimated doses are presented in Subsection 11.2.9.

11.2.2 S ST S D SCR PT O S The Li uid Waste Processing System collects and processes potentially radioacti e wastes or release to the ri er. Pro isions are made to sample and analyze luids be ore 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 li uid releases is pro ided by analyses o nown olumes o waste. The system is shown on the Mechanical Flow Diagram (Figure 11.2-1.)

The radioacti e li uids discharged rom the Reactor Coolant System are processed by either the Chemical and Volume Control System (CVCS) holdup tan s or Tritiated Drain Collector Tan (TDCT). E pected olumes to be processed by the Waste Processing System are gi en in Table 11.2-1.

The li uid Waste Processing System (WPS) consists o two main sub-systems processing tritiated and non-tritiated water. A system is pro ided 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 Au iliary Building. Mal unction o the system actuates an alarm in the Au iliary Building and a common alarm in the main control room (MCR). All li uid WPS e uipment is located LIQUID WASTE SYSTEMS 11.2-1

WATTS BAR in or near the Au iliary Building, e cept or the reactor coolant drain tan and drain tan pumps containment pit sump and pumps Reactor Building loor and e uipment drain sump and pumps Reactor Building loor and e uipment drain poc et sump and pumps, which are located in the Reactor Building. A mobile demineralizer system is located and operated in the waste pac aging area.

Fluid is sampled and analyzed to determine uantities o radioacti ity, with an isotopic brea down, i necessary, be ore processing or disposal is attempted.

At least two al es must be manually opened to permit discharge o li uid to the en ironment. One o these al es is normally loc ed closed. A control al e trips closed on a high e luent radioacti ity le el signal. Controls are pro ided to pre ent discharge without ade uate dilution.

The li uid waste processing system is partly shared by the two units. Howe er, e cept or its containment isolation unction, the system ser es no primary sa ety unction and the sa ety o either unit is not a ected by such sharing. Li uid waste is processed, as necessary, through a mobile demineralizer.

The Li uid 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 e uipment drain poc et sump with two pumps, and the Reactor Building loor and e uipment drain sump with two pumps. All o this e uipment is located inside the containment o each unit.

Shared Com onents The ollowing shared e uipment is located inside the Au iliary 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 tan s and two pumps a chemical drain tan and pump two laundry and hot shower tan s and pump a spent resin storage tan a cas decontamination collector tan with two pumps and two ilters monitor tan with two pumps Au iliary Building loor and e uipment drain sump and pumps one tritiated e uipment drain sump with two pumps Au iliary Building passi e sump a mobile demineralizer system, and the associated piping, al es and instrumentation.

The ollowing shared components are located in the Turbine Building or recei ing, processing, and trans erring wastes rom the regeneration o condensate demineralizers high crud tan s, 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 pac aging area or recei ing and processing li uid radwaste rom the loor drain and tritiated drain collector tan s a mobile demineralizer system, including cation and anion ion e change resins, pre ilter, associated pumps, a endor supplied mobile demineralizer spent resin storage container, and associated piping and al es.

11.2-2 LIQUID WASTE SYSTEMS

WATTS BAR Se aration of Tritiated and on-Tritiated Liquids Waste li uids are normally separated into tritiated and non-tritiated li uids. Waste li uids which are high in tritium content (reactor coolant lea o /lea age) 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 li uids are processed or release to the ri er.

Tritiated Water Processing Tritiated water is processed or discharge to the ri er. The water enters the li uid waste disposal system rom e uipment lea s and drains, al e lea o s, pump seal lea o s, tan o er lows, and other tritiated and aerated water sources.

The e uipment pro ided 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 e uipment drain sump and pumps the Reactor Building loor and e uipment drain poc et sump tritiated e uipment drain sump, pumps and ilter. The primary unction o the tritiated drain collector tan is to pro ide su icient surge capacity or the waste processing e uipment. The waste is primarily processed by the mobile demineralizer system.

on-Tritiated Water Processing Non-tritiated water is processed or discharge to the ri er. The sources include loor drains, e uipment drains containing non-tritiated water, certain sample room and radiochemical laboratory drains, laundry and hot shower drains and other non-tritiated sources. The e uipment pro ided in this subsystem consists o pumps and ilter laundry and hot shower tan s and pump laundry tan bas et strainer waste condensate tan s, pumps and ilter mobile demineralizer chemical drain tan and pump the Au iliary Building loor and e uipment drain sump and pumps the Additional E uipment Building loor and e uipment drain sump and pumps.

Li uids entering the loor drain collector tan are normally rom low acti ity sources and are normally processed through a mobile demineralizer system.

The laundry and hot shower drains normally need no treatment or remo al o radioacti ity. This water is collected in the laundry and hot shower drain tan s. The in entory o these tan s may be discharged directly to the cooling tower blowdown ( ia the laundry tan strainer) or may be trans erred to either the waste condensate tan s or the cas decontamination collector tan or to the monitor tan or the FDCT ( ia the laundry tan strainer) be ore inal discharge to the cooling tower blowdown. Prior to discharge, a sample is ta en and analyzed in accordance with plant procedures that implement the ODCM re uirements, and the water is discharged i the acti ity le el is below ODCM limits.

The blowdown rom the steam generators is routed to the CPDS or the hotwell (re er to Subsection 10.4.8) or discharged directly to the cooling tower blowdown line.

Spent regenerant waste rom the CPDS is addressed below.

LIQUID WASTE SYSTEMS 11.2-3

WATTS BAR obile Deminerali er System Processing of Tritiated and on-Tritiated Waste Flow rom both the tritiated and nontritiated tan s 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 tan s are discharged as described in the two pre ious sections or processed urther, as necessary, to meet ODCM limits. The Mobile Demineralizer System remo es most soluble and suspended radioacti e materials rom the waste stream ia ion e change and iltration. Once the resin and ilter media is e pended, the spent resin is sluiced to either a liner or disposal or a Rad-Vault to accumulate enough resin or o -site disposal. The spent resin is dewatered to meet the disposal site criteria.The ilters are stored in an appropriate container.

Laboratory Sam le Waste Processing The chemical drain tan recei es inputs rom the laboratory and the decontamination room. I the radioacti ity le el 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 en ironment. I analysis shows that there are no chemicals present which would be harm ul to the demineralizer, the li uid is sent to the FDCT or processing. The tan contents may also be sent to the waste pac aging area or solidi ication i re uired.

Processing of Waste from Regeneration of Condensate Polishing Deminerali er Wastes produced in the regeneration o the CPDS are processed or discharge or reuse. The high crud tan s contain high crud, low conducti ity waste (containing no regeneration chemicals) which are iltered and discharged when the radioacti e le el does not e ceed ODCM limits. When limits are e ceeded, the high crud, low conducti ity waste may be processed by the mobile demineralizer. The high crud tan s may also contain regeneration chemicals i additional capacity is re uired. The tan would normally be processed by a endor i it contains regeneration chemicals . The neutralization and non-reclaimable waste tan s contain low crud, high conducti ity waste which is neutralized. I it contains radioacti e material abo e ODCM limits, it is processed by a endor.

S ent Resin Processing Spent resins are processed in accordance with Section 11.5.

11.2.3 S ST D S 11.2.3.1 Com onent Design A summary o principal design parameters are gi en in Table 11.2-2. Design codes or the components o the Li uid Waste Processing System are gi en in Chapter 3.

Materials o the Li uid Waste Processing System are selected to meet the material re uirements 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 pro ided with ent and drain connections. The mobile waste 11.2-4 LIQUID WASTE SYSTEMS

WATTS BAR demineralizer system is constructed to the applicable parts o Regulatory Guide 1.143, Re ision 1, 1979.

Reactor Coolant Drain Tan (RCDT) and Pum s The reactor coolant drain tan (one tan per unit) collects clean reactor coolant type water rom inside the reactor containment. Two pumps per unit are pro ided to trans er the li uid rom the drain tan to the Chemical and Volume Control System holdup tan s and to trans er water rom the re ueling canal to the re ueling water storage tan or tritiated drain collector tan . The ma imum load on the pumps occurs when the pressurizer relie tan drains and the e cess letdown low are imposed simultaneously or when the re ueling canal is being drained. The normal load on the pumps is a small uantity, mainly rom lea o s, although the e cess letdown low can be e pected or relati ely long periods o time during plant heatup.

Chemical Drain Tan and Pum The shared chemical drain tan recei es radioacti e wastes rom the radiochemical laboratory drains and rom the decontamination room. The pump is pro ided to trans er the tan contents to the waste pac aging area or solidi ication, CTB line, or the FDCT.

Tritiated qui ment Drain Sum and Pum s Tritiated E uipment Drain Sump and Pumps collect and transport tritiated li uid wastes rom e uipment and lower ele ation drains, which cannot drain by gra ity to the tritiated drain collector tan . Two pumps are urnished to trans er the li uid collected to the tritiated drain collector tan . The sump ents to the building e haust system.

Tritiated Drain Collector Tan (TDCT) and Pum s The shared tan collects radioacti e li uids rom the primary plant which may contain tritiated water, boric acid and ission products. The primary unction o the tan is to pro ide su icient surge capacity or the waste processing system. Pump A is pro ided to trans er the tan contents to the mobile waste demineralizer system or condensate demineralizer waste e aporator. Pump B is pro ided, as a spare, to also trans er the tan contents.

Floor Drain Collector Tan (FDCT) and Pum s The tan retains primarily non-reactor grade type luids and some non-recyclable reactor grade water rom certain drains in the Au iliary Building. The tan is e uipped with three pumps. The tan contents may be sent through the FDCT discharge ilters.

The li uids are processed through the mobile waste demineralizers and then collected in either the cas decontamination collector tan (CDCT) or the monitor tan . A ter the li uids are collected in one o these tan s, the contents are recirculated, mi ed, sampled, and analyzed. I the radioacti ity is within the discharge limits, the li uids are routed to the cooling tower blowdown or discharge.

LIQUID WASTE SYSTEMS 11.2-5

WATTS BAR Laundry and ot Sho er Tan s and Pum The laundry and hot shower tan s collect wastes rom the radiologically controlled access area drains and hot shower drains. A pump is used to trans er the li uid. A recirculation line is pro ided to permit mi ing the contents o the isolated tan be ore ta ing samples or acti ity analysis i the tan is to be discharged directly to the CTB.

I the acti ity le el is within discharge limits, the contents may be routed through the laundry bas et strainer and discharged ia the CTB or the CDCT. I the acti ity le el is abo e discharge limits, the contents are routed to the FDCT or routing to the mobile waste demineralizer or processing.

S ent Resin Storage Tan This tan is supplied or the storage o used demineralizer resins. Resin is held in this tan to allow or decay o short-li ed isotopes and to allow accumulation o enough resin or shipment. A layer o water is maintained o er the resins to pre ent degradation due to decay heat (see Section 11.5).

Filters Table 11.2-2 lists the standard ilters re uired, their nominal ratings, and the material o the ilter media. The TDCT, FDCT, waste condensate tan , and CDCT ilters may be remo ed and reinstalled as necessary to pre ent crud traps and particles rom building up in the piping.

The methods employed to change ilters and screens are dependent on acti ity le els.

I the radiation le el o the ilter is low enough, it is changed manually. I acti ity le els do not permit manual change, the spent cartridge is remo ed remotely with temporary shielding to reduce personnel e posure. The spent cartridge is placed in a shielded container or transport and storage prior to pac aging or shipment.

onitor Tan and Cas Decontamination Collector Tan (CDCT)

The Monitor Tan and the CDCT are used as release tan s or li uid disposal. These tan s recei e processed li uid rom either the loor drain collector tan , the tritiated drain collector tan , or the CVCS hold up tan s ia the mobile demineralizer. The CDCT may also recei e li uid directly rom the laundry and hot shower tan s.

The CDCT may also recei e water rom the spent uel shipping cas drain. The contents are pumped to the cooling tower discharge line ia the radwaste line i the acti ity is su iciently low, and to the loor drain collector tan or returned to the mobile demineralizer or processing i the acti ity is too high or discharge.

onitor Tan Pum and Cas Decontamination Pum Two pumps are pro ided or each tan to recirculate and pump li uid. The CDCT processes the li uid through the cas decontamination ilter to the waste discharge line. Normally, only one pump is used.

11.2-6 LIQUID WASTE SYSTEMS

WATTS BAR Waste Condensate Tan s The waste condensate tan s are a ailable or additional capacity to process e luent li uid rom the laundry and hot shower drain tan s. Each o three tan s are discharged to the waste condensate pumps. These tan are not normally used or Unit 1 or Unit 2 operation.

Waste Condensate Pum s Two waste condensate pumps are a ailable to recei e li uid rom the waste condensate tan s. This li uid may be processed to the CTB i it is below the ODCM limits. The discharge can be recirculated bac to the waste condensate tan s, to the monitor tan , or to the cas decontamination collector tan .

Condensate Polishing Deminerali er Waste Processing qui ment igh Crud

( C) Tan s These tan s collect high crud, low conducti ity waste produced during the bac wash phase o condensate polishing demineralizer regeneration. The high crud, low conducti ity 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 (a ter iltration) is ery near condensate uality and is discharged only i permissible discharge concentrations are not e ceeded. The high crud tan s may also contain regenerati e chemicals i additional capacity is re uired.

The tan would normally then be processed by a endor.

igh Crud Pum s Two pumps are pro ided to circulate the contents o the high crud tan s 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-Filters Three 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 ser ice. The third ilter which is on standby and isolated may be placed in ser ice while changing out the clogged ilters. Each essel has pressure gauges upstream and downstream o the ilters.

eutrali ation Tan This tan collects spent regenerant chemicals and rinses rom CPDS regeneration (low crud, high conducti ity waste) miscellaneous waste rom the condensate polishing demineralizer sump and has the capability to recei e and neutralize waste rom the cation and anion regeneration tan s. Sul uric acid or sodium hydro ide is typically added to ad ust the pH. The tan contents are circulated during pH ad ustment. A ter neutralization to a desired pH alue, the tan contents are either processed to the non-reclaimable waste tan or discharged to the en ironment.

LIQUID WASTE SYSTEMS 11.2-7

WATTS BAR eutrali ation Tan Pum s Two pumps are pro ided to circulate the contents o the neutralization tan s and to trans er the contents to the non-reclaimable waste tan or pump them to the en ironment. Normally, only one pump is used.

on-Reclaimable Waste Tan This tan recei es neutralized waste rom the neutralization tan . The tan contents are routed to discharge i the radioacti ity content is su iciently low. I not, the contents are processed by a endor.

on-Reclaimable Waste Pum s Two pumps are pro ided 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 al es The design code or the al es is ASME III Class 3 or ANS Sa ety Class 2b or 3 or Class 2 or ANS Sa ety Class 2a and ANSI B31.1, ANSI B16.5 or MSS-SP-66 or Non-Nuclear Sa ety (NNS) al es. The al es in the li uid waste processing system are stainless steel. The ma ority o the al es in ol ed are diaphragm al es. This type o al e pro ides positi e control o stem lea age and is suitable or use as an isolation al e or in throttling ser ice. In se eral instances, globe al es are substituted or diaphragm al es because o their ability to control low o er a wider range.

Val es are supplied or isolation o each ma or e uipment item or maintenance, to direct and control the low o waste through the system and or isolation o tan s or decay.

For the purpose o containment isolation, trip al es are installed.

Liquid Waste Dis osal Pi ing The piping design code is ASME III Class 3 or ANS Sa ety Class 2b or 3 or Class 2 or ANS Sa ety Class 2a and ANSI B31.1 or NNS. The piping is normally austenitic stainless steel and the piping oints are normally welded, e cept where langed connections are used at pump, al e and instrument connections to acilitate remo al or maintenance.

Facilities for enting and Draining Normally pro isions ha e been made or enting and draining e uipment which may re uire maintenance during the plant li e. Vents and drains are normally pro ided either on the components themsel es or in the pipe lines between the isolation al es.

In general, each pipe line and component ent and drain is pro ided with a al e plus a bac -up lea age barrier o either a blan lange or a threaded screw cap.

11.2-8 LIQUID WASTE SYSTEMS

WATTS BAR obile Waste Deminerali ation System The mobile waste demineralization system (MWDS) consists o se eral essels with an associated pumping s id and le el control system. The MWDS normally processes li uids at a eed rate o appro imately 40 gpm. Howe er, during pea low rates, the MWDS may process higher low rates (appro imately 140 gpm). The essel headers ha e in luent and e luent isolation al es and all piping is welded with long radius bends. Demineralizer essels are operated inside shielding in the waste pac aging 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, Re ision 1, 1979.

The MWDS pro ides in-line processing o li uid radwaste through iltration and demineralization. The MWDS recei es both tritiated li uid (the tritiated drain collector tan , high crud low conducti ity waste, and CVCS holdup tan ) and nontritiated li uids (the loor drain collector tan ). Processed water rom the MWDS is sent to either the monitor tan or the CDCT or release to the ri er.

The li uid radwaste is processed through ion e change and iltration which remo e soluble and suspended radioacti e materials rom the waste streams. The irst essel is normally loaded with a ilter media, such as acti ated carbon, to pro ide initial iltration o the radwaste. This ilter medium remo es solids, cobalt isotopes, e isting in the orm o colloidal-sized suspended solids and cleaning agents, and other chemicals that can be remo ed by absorption o the acti ated carbon. A mechanical ilter loaded with ilter cartridges can be used or iltration. This conditions the radwaste or treatment in the subse uent tan s.

The subse uent demineralizer tan s contain beds (anions and cations) o ion-e change resins, which remo e the soluble constituents o the waste stream. Once the resin and ilter media is e pended, the resin is remo ed 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 e uipment 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 speci ic treatment steps and e uipment used can also ary somewhat rom endor to endor.

11.2.3.2 nstrumentation Design The Waste Disposal System panel, which is located in the Au illary Building, contains some o the controls and indications necessary to operate the system. Other controls and indicators are mounted near the e uipment.

Alarms are shown separately on the WPS panel.

Most pumps are protected against loss o suction pressure by a control setpoint on the le el instrumentation or the respecti e essels eeding the pumps.

LIQUID WASTE SYSTEMS 11.2-9

WATTS BAR Pressure indicators upstream and downstream o ilters pro ide local indications o pressure drops across each component. The radioacti e e luent release monitoring instrumentation is described in Section 11.4.

11.2. O erating Procedure The e uipment installed to reduce the acti ity o radioacti e e luents is maintained in good operating order and is operated to as low as reasonably achie able criteria, as stated in the ODCM. In order to assure that these conditions are met, administrati e controls are e ercised on o erall operation o the system pre enti e maintenance is utilized to ensure e uipment is in optimum condition and applicable industry e perience and endor in ormation a ailable is used in planning or operation at Watts Bar Nuclear Plant.

Administrati e controls are e ercised through the use o instructions co ering such areas as al e alignment or arious operations, e uipment operating instructions, and other instructions pertinent to the proper operation o the processing e uipment.

Discharge permits are utilized to assure proper procedures are ollowed in sampling and analyzing any radioacti e li uid to be discharged and in assuring proper al e alignments and other operating conditions be ore a release. These permits are signed and eri ied by those personnel per orming the analysis and appro ing the release.

Pre enti e maintenance is per ormed in accordance with appro ed plant maintenance program procedures de eloped, considering applicable operating and maintenance e perience as well as endor in ormation.

Operation o the Li uid Waste Processing System is essentially the same during all phases o normal reactor plant operation the only di erences are in the load on the system. The ollowing sections discuss the operation o the system in per orming its arious unctions. In this discussion, the term normal operation should be ta en to mean all phases o operation e cept operation under emergency or accident conditions. The Li uid Waste Processing System s only primary sa ety unction is containment isolation.

Liquid Waste Processing ormal O eration During normal plant operation the system processes li uid rom the ollowing sources (1) E uipment drains and lea s (2) Radioacti e chemical laboratory drains (3) Radioacti e laundry and shower drains (4) Decontamination area drains (5) Demineralizer lushing, bac washing and regeneration o resin 11.2-10 LIQUID WASTE SYSTEMS

WATTS BAR (6) Sampling system The system also collects and trans ers li uids 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) E cess letdown during startup (5) Accumulators (6) Val e and reactor essel lange lea o s

( ) Re ueling canal drains The li uid lows to the reactor coolant drain tan and is discharged directly to the CVCS holdup tan s by the reactor coolant drain pumps which are operated automatically by a le el controller in the tan . These pumps can also return water rom the re ueling ca ity to the re ueling water storage tan . There 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 le el to be controlled. The pumps can also be operated manually to control the tan le el.

Where possible, waste li uids drain to the waste disposal system and tritiated drain collector tan s by gra ity low.

Se aration of Tritiated and on-tritiated Liquids Waste li uids which are high in tritium content are routed to the tritiated drain collector tan , while li uids low in tritium content are routed to the loor drain collector tan . The tritiated and non-tritiated li uids are processed or release to the ri er.

Tritiated Water Tritiated water enters the li uid waste disposal system ia e uipment lea s and drains, al e lea o s, pump seal lea o s, tan o er lows, and other tritiated and aerated water sources.

The tritiated li uids rom e uipment lea s and drains, and al e lea -o s 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 le el to be controlled. The pumps can also be operated manually.

LIQUID WASTE SYSTEMS 11.2-11

WATTS BAR The li uid collected in the tritiated drain collector tan contains boric acid and ission product acti ity. The li uid collected is normally demineralized by the mobile waste demineralizer and is then analyzed and discharged to the ri er.

on-Tritiated Water Non-tritiated water sources include loor drains, e uipment drains containing non-tritiated water, certain sample room and radiochemical laboratory drains, laundry and hot shower drains and other non-tritiated sources.

The li uids entering the loor drain collector tan are primarily rom low acti ity sources.

The li uid collected is normally demineralized by the mobile waste demineralizer and is then analyzed and discharged to the ri er.

Laundry and ot Sho er Drains One o the two laundry and hot shower tan s is al ed to recei e waste at all times.

When one tan is illed, it is al ed out and the other tan is al ed in. The ull tan is then aligned with the laundry pump to mi the waste by recirculation. A sample is ta en (i re uired) rom a local sample connection to determine what subse uent handling o the waste li uid is re uired. Normally no treatment is re uired or remo al o radioacti ity. This water is trans erred to either CTB or FDCT or to CDCT or to the waste condensate tan s or to the monitor tan (all ia the laundry tan s strainer). A sample is ta en and, a ter analysis, the water is discharged in accordance with the ODCM limits.

Laboratory Sam les Laboratory 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 le el is manual, with the e ception that the pump is shut o automatically on low tan le el.

Low acti ity drains rom the laboratory, such as lush water, are normally routed to the loor drain collector tan . E cess tritiated samples not contaminated by chemicals during analysis are normally directed to the tritiated drain collector tan .

Shi ing Cas Drains Li uid in this area is drained to the CDCT. The li uid is e pected to be low enough in radioacti ity content that it can be discharged without processing. Following analysis, the li uid is discharged. In the unli ely e ent that the radioacti ity le el is such that urther processing is re uired, the li uid may be trans erred to the loor drain collector tan or returned to the Mobile Waste Demineralizer System or urther processing.

Condensate Polishing Deminerali er Waste The 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 described in this section.

11.2-12 LIQUID WASTE SYSTEMS

WATTS BAR The CPDS regeneration subsystem is designed to separate wastes into two ractions

- one, a high-crud, low-conducti ity li uid and the other, a low-crud, high-conducti ity li uid. These ractions are collected in separate tan s. The irst raction results rom bac wash 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 Conducti ity ( CLC) Waste The high-crud waste is normally low in conducti ity. This waste is processed in e uipment located in the Turbine Building. The slurry is iltered in the HC pre- ilter or HC ilter. The iltrate radioacti ity is low enough to achie e ade uate 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 bac washed and the li uid is routed to the HC tan .

Treatment of Lo -Crud, igh-Conducti ity (LC C) Waste The LCHC wastes, consisting o the spent regeneration chemicals is neutralized in a neutralizer tan and may be trans erred to a non-reclaimable waste tan . The li uid is normally processed by a endor i the radioacti ity is abo e the ODCM limit. Howe er, the li uid is circulated and sampled prior to processing. I the radioacti ity le el is below permissible discharge le els, it may be discharged directly without urther treatment.

Discharge of Regeneration Wastes Waste li uids rom the CPDS regeneration that are to be discharged are sampled and analyzed as re uired per the ODCM to ensure that the acti ity le el complies with re uirements stated in the ODCM. The discharge line rom the Turbine Building e tends to the cooling tower blowdown line, and includes a loc ed-closed al e, a radiation monitor, and a radiation-controlled al e. 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 inade uate dilution low.

S ent Resin andling This 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 solidi ied by an o site contractor.

C CS Resin Sluicing Spent resins are initially luidized by bac lushing with primary water. The bac lush 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 co er, o er the resin. The LIQUID WASTE SYSTEMS 11.2-13

WATTS BAR al es are then realigned or normal process operation. A negligible amount, i any, o resin is e pected to remain in a demineralizer a ter lushing, as the demineralizers are completely lushable.

Refueling Operation o the Li uid Waste Processing System is the same during re ueling as during normal operation. When re ueling is complete, the water remaining in the re ueling canal ollowing normal drain-down by the Residual Heat Remo al System is drained to the reactor coolant drain tan and pumped bac to the re ueling water storage tan with the reactor coolant drain tan pumps. The pumps normally operate in the automatic mode during this operation. Since there is o ygen in the re ueling water, the drain tan is isolated rom the ent header during this trans er and the tan is ented to the containment atmosphere. It is necessary to purge the tan with nitrogen be ore connecting it bac to the ent header.

Faults of oderate Frequency The system is designed to handle the occurrence o e uipment aults o moderate re uency such as (1) Mal unction in the Li uid Waste Processing System Mal unction in this system could include such things as pump or al e ailures. Because o pump standardization throughout the system, a spare pump can be used to replace most pumps in the system. There is su icient surge capacity in the system to accommodate waste until the ailures can be i ed and normal plant operation resumed.

(2) E cessi e Lea age in Reactor Coolant System E uipment The system is designed to handle a one gpm reactor coolant lea in addition to the e pected lea age during normal operation. Operation o the system is almost the same as or normal operation e cept 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 e cept or the increased load on the system. Abnormal li uid olumes o reactor coolant resulting rom e cessi e reactor coolant or au iliary building e uipment lea age (1 gpm) can also be accommodated by the loor drain collector tan and processed by the non-tritiated system. Val e and pump lea o s 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 ri er.

(3) E cessi e Lea age in Au iliary System E uipment Lea age o this type could include water rom steam side lea s inside the containment which are collected in the Reactor Building loor and e uipment drain sump. Although the sump pump discharge is normally routed to the 11.2-14 LIQUID WASTE SYSTEMS

WATTS BAR tritiated drain collector tan , the low can be di erted to the loor drain collector tan upon disco ery o a lea . Other sources could be component cooling water lea s, essential raw cooling water lea s, and secondary side lea s. This water enters the loor drain collector tan and will be processed and discharged as during normal operation.

(4) Steam Generator Tube Lea s During periods o operation with uel de ects, coincident with steam generator tube lea s, radioacti e li uid is discharged ia the steam generator blowdown system. The releases rom the secondary side will be within the ODCM limits.

Releases of Waste Release o radioacti e li uid out o the Li uid Waste Processing System is rom the waste condensate tan s, 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 ri er through the di user pipes. Li uid wastes rom the condensate polishing demineralizer system are released rom the high-crud tan s, 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 di user in order to maintain the solids in the water at an acceptable le el.

Release o the radioacti e li uids rom the li uid waste system is made only a ter laboratory analysis o the tan contents. I the acti ity is not below ODCM limits, the li uid 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 loc ed closed manual al e and a remotely operated control al e, interloc ed with a radiation monitor and a low element in the cooling tower blowdown line. This assures that su icient dilution low is a ailable or the discharge o radioacti e li uids. The minimum dilution low re uired or discharge o radioacti ity into the cooling tower blowdown lines (CTBL) is 20,000 gpm.

A similar arrangement is pro ided or wastes discharged rom the condensate polishing demineralizer system. A radiation monitor on this system and a low element on the cooling tower blowdown are interloc ed with a low control al e in the system discharge line. Release o wastes is automatically stopped by either a high radiation signal or a signal which indicates that inade uate dilution low is a ailable. The CPDS and SGB may be released with the CTB low less than 20,000 gpm pro ided the sum o the E luent Concentration Limit (ECL) ractions (release concentrations/10 CFR 20 ECLs) or all isotopes released is less than or e ual to 10 as re uired by the Technical Speci ications and ODCM, and pro ided such releases are controlled and limited such that the 10 CFR 50, Appendi I limits are not e ceeded.

LIQUID WASTE SYSTEMS 11.2-15

WATTS BAR The steam generator blowdown system also may discharge radioacti e li uid. Li uid waste rom this system is not collected in tan s or treatment, but is continuously monitored or radioacti ity and may discharge to the cooling tower blowdown, or recirculated to the condensate system upstream o the condensate demineralizers.

Re er to Section 10.4.8 or a description o the steam generator blowdown system operation.

The turbine building sump collects li uid entering the turbine building loor drain system. When the sump is nearly ull (appro imate usable capacity o 30,000 gallons),

the li uid is pumped to either the low olume waste treatment (LVWT) pond or the yard holding pond. Water in the ponds drains by gra ity to the ri er ia the cooling tower blowdown line to the di users. I high concentrations o chemicals are present, it may be pumped to the lined or unlined chemical holdup ponds or treatment be ore release per the NPDES Permit.

Station lac out The Li uid Waste Processing System (e cept or containment isolation) does not normally operate during a blac out. I necessary, e uipment with diesel bac up power can be manually connected to the emergency power sources when they become a ailable.

Loss-of-Coolant Accident The Li uid Waste Processing System (e cept or containment isolation) is not re uired to operate during, or immediately ollowing, a loss-o -coolant accident. E uipment may be started manually as re uired.

O erating erience Deminerali ers Operational data on CPDS decontamination actors (DF) is deri ed rom NUREG 0017, Re ision 1 Re . 1 . The DF or MWDS was supplied by a endor.

11.2.5 P RFOR A C T STS Initial per ormance tests were per ormed to eri y the operability o the components, instrumentation and control e uipment and applicable alarms and control setpoints.

The speci ic ob ecti es were to demonstrate the ollowing (1) Pumps are capable o producing low rate and head as re uired.

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

(3) Instrumentation, controllers, and alarms operate satis actorily to maintain le els, pressures, and low rates and indicates, records, and alarms, as re uired.

11.2-16 LIQUID WASTE SYSTEMS

WATTS BAR (4) Sampling points are a ailable or sampling.

During reactor operation, the system is used at all times and hence is under sur eillance. Data is ta en periodically (i applicable) or use in determining decontamination actors o demineralizers.

11.2. ST AT D R L AS S 11.2. .1 RC Requirements The ollowing documents ha e been issued to pro ide regulations and guidelines or release o radioacti e li uids (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 erience The li uid releases are highly dependent upon administrati e acti ities which control the use o water or decontamination, e uipment and loor rinsing and other uses in the controlled areas.

Operating plants ha e reported li uid discharges as shown in Table 11.2-3.

11.2. .3 ected Liquid Waste Processing System Releases The uantities and isotopic concentration in li uids assumed discharged to the li uid waste processing system, and hence the releases to the en ironment, are highly dependent upon the operation o the plant. The radionuclide concentrations and calculated doses are the principal ocus o treatment acti ities. 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 li uid waste processing system, and realistic estimation o the potential input sources. Hence, the results are representati e o typical releases rom the Watts Bar li uid 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 pro ected tritium permeation rom 2,304 TPBARs (Unit 1 only).

The associated releases in curies per year per nuclide are gi en in Table 11.2-5.

The li uid waste processing system is assumed to operate as described in Subsection 11.2.4.

11.2. . Turbine uilding (T ) Drains 11.2. . .1 Pur ose The TB drainage system is designed to remo e li uid drainage in the Turbine Building.

LIQUID WASTE SYSTEMS 11.2-17

WATTS BAR 11.2. . .2 Descri tion The TB drains are not normally radioacti e.

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 Deminerali er System Drains The Condensate Polishing Demineralizer System (CPDS) area is ser iced by separate loor and e uipment drains. The drains or CPDS are routed to the Condensate Demineralizer sump where they are pumped to the Neutralization Tan (NT). These drains ha e a potential to be low-le el radioacti e during periods o primary to secondary lea age. The NT is pro ided with the capability o ad usting pH, and i the in entory is not radioacti e or less than 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 in entory is abo e dischargeable limits. Any radioacti e 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 radioacti e and non-radioacti e conditions.

11.2. . .2.2 Other Turbine uilding Drainage Drainage 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 e uipment 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 gra ity directly to the yard holding pond.

11.2. . .2.3 Oil and Oily Water Drainage Oil is drained directly to drums or tan truc s or reuse or remo al 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 su icient amount is collected to be pumped into tan truc s or o site disposal.

11.2. .5 stimated Total Liquid Releases 10 CFR 50 Appendi I and 10 CFR 20 prescribe the allowable limits o radionuclide li uid releases rom Watts Bar. The O site Dose Calculation Manual is the process document that describes how releases are measured, monitored, controlled and reported. The li uid waste management system at Watts Bar can be operated in a ariety o con igurations depending on plant conditions and the amount and composition o radionuclides in the waste stream. Irrespecti e o the speci ic modes described, the annual releases are re uired to be e ual to or less than the limits pro ided in the ODCM, Appendi I and 10CFR 20.

11.2-18 LIQUID WASTE SYSTEMS

WATTS BAR Table 11.2-5 pro ides the total annual discharge rom the li uid waste processing system or our di erent le els o processing prior to discharge. The annual discharge or Unit 2 is e pected to be similar to Unit 1 with the e ception 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 pro ide additional conser atism as discussed in NUREG-0017. The discussions to ollow are based on the luid uantities and acti ities speci ied in Table 11.2-1.

11.2. .5.1 ected ormal Plant O eration The e pected plant alignment and the resultant our release paths are as ollows CVCS 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.

Li uid 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 abo e three paths is called li uid 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 pro ides the li uid radwaste source term. Column 7 pro ides the source term or steam generator blowdown assuming an annual untreated SG Blowdown concentration o 3.65 E-5 uCI/cc.

Concentrations abo e this alue cannot be released continuously on an annual basis without additional processing. Unit 1 currently operates without the condensate demineralizers in ser ice. The condensate demineralizers will not be utilized unless signi icant primary to secondary lea age occurs. Operating e perience has shown that annual releases are below the alues shown in Column 8 and thus that processing o SG Blowdown is not e pected to be re uired. There is no condensate demineralizer blowdown or bac washing when the plant is operating under this set o conditions. SG Blowdown concentrations abo e 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 e pected li uid 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 ma imum 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 LIQUID WASTE SYSTEMS 11.2-19

WATTS BAR CVCS 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.

Li uid 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 ollowing CVCS 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.

Li uid releases rom the Laundry and Hot Shower Drain Tan and the Turbine Building drains can be released without processing by mobile demineralizer.

The e pected li uid 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 li uid releases or 1 ailed uel or both treated and untreated waste relati e to the re uirements o 10 CFR 20.1302(b). The sum o er 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 li uid is not processed by the Mobile Demineralizers. In order to pre ent e ceeding 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 concentrations are shown in Table 11.2-5b and are less than the limits speci ied in 10 CFR 20.1302(b).

Based on the abo e, the releases rom the plant are in accordance with the design ob ecti es as outlined in Section 11.2.1 and the O site Dose Calculation Manual.

11.2. R L AS PO TS All radioacti e li uid 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.

11.2-20 LIQUID WASTE SYSTEMS

WATTS BAR 11.2. D LUT O FACTORS The dosimetry calculations or drin ing water are based on the assumption that the li uid e luent will be mi ed with 10 o the ri er low between the point o discharge and Tennessee Ri er 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. ST AT D DOS S FRO RAD O UCL D S L U D FFLU TS Doses rom the ingestion o water, rom the consumption o ish, and rom shoreline recreation are calculated or e posures to radionuclides routinely released in li uid e luents.

11.2. .1 Assum tions and Calculational ethods Internal doses are calculated using methods outlined in NRC Regulatory Guide 1.109, Re ision 1, October 1977. This model is used or estimating the doses to bone, gastro-intestinal (G.I.) tract, thyroid, li er, idney, lung, s in, and total body o man rom ingestion o water, consumption o ish, and rom e ternal e posures due to recreational acti ities. Population doses are estimated or the year 2040 based on the populations gi en in Table 2.1-12.

(1) Doses to Man rom the Ingestion o Water Data listed in Table 11.2-6 or public water supplies is used to calculate dose commitments rom the consumption o Tennessee Ri er 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 e luent is mi ed with one-tenth o the ri er 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 a erage annual low data or the Tennessee Ri er as measured during the 69-year period 1899-1968. The a erage low past the site is appro imately 28,000 t3/sec.

Radioacti e decay between the time o inta e in a water system and the time o consumption is handled in accordance with Regulatory Guide 1.109.

Ma imum and a erage consumption rates are those recommended by Regulatory Guide 1.109.

Due to a lac o de initi e data, no credit is ta en or remo al o acti ity rom the water through absorption on solids and sedimentation, by deposition in the biomass, or by processing within water treatment systems.

LIQUID WASTE SYSTEMS 11.2-21

WATTS BAR Internal doses, D, or an organ or a single radionuclide are calculated using the relation D = 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 acti ity o the radionuclide ta en into the body annually ia ingestion, (pCi).

(2) Dose to Man rom the Consumption o Fish Current estimates o the Tennessee Ri er ish har est are 3.04 lb/acre/year.

It is assumed that the rates will increase with the population e pansion, so the dose calculations are based on har ests o 3.77 lb/acre o ish in the year 2040. This is determined by multiplying the 1990 har est by the population growth actor. The Tennessee Ri er, within 50 miles downstream o WBN, is segmented into 4 regions (Table 11.2-6) in order to acilitate the calculations o ish har ests and radioacti ity concentrations. The radioacti ity le els in the ish rom each region are estimated by the product o an a erage acti ity 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 har est rom each portion o the ri er is consumed by humans.

Dose commitments are calculated with E uation 1, which is discussed or water ingestion in the pre ious section.

Calculations indicate that there would be no signi icant radiological impact rom human utilization o shell ish. Shell ish are not currently being har ested commercially in the Tennessee Ri er and consumption o shell ish by humans is assumed to be negligible.

(3) Doses to Man due to Shoreline Recreation Estimates o the doses rom shoreline recreation along the Tennessee Ri er are calculated or each radionuclide using the ollowing e uation D = RDCF C T (mrem),

where RDCF = The shoreline recreation dose commitment actor, mrem/hour per pCi/m2, rom Regulatory Guide 1.109, Table E-6.

T = e posure time, hours.

11.2-22 LIQUID WASTE SYSTEMS

WATTS BAR C = Concentration o the radionuclide in the sediment, pCi/m2 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 ffluents Radiation doses calculated or releases o radionuclides in li uid e luents during normal operation o the Watts Bar Nuclear Plant are summarized in Table 11.2-7. Li er tissues are e pected to recei e the greatest doses or the ma imum indi idual howe er, the thyroid tissues are e pected to recei e the greatest dose or the Tennessee Valley population.

REFERENCES (1) NUREG-0017, R1, Calculation o Releases o Radioacti e Materials in Gaseous and Li uid E luents rom Pressurized Water Reactors, a PWR-GALE Code, Published April, 1985.

LIQUID WASTE SYSTEMS 11.2-23

WATTS BAR Table 11.2-1 Liquid Waste Processing System Calculation asis (Page 1 of 2)

1. n uts (2 Units) 1.1 Reactor Coolant Drain Tan Tan Volume 350 gal/unit Input 40 gpd 14,600 gal/yr Acti ity 0.1 PCA Collection Time 24 hrs Processing Time neglected 1.2 Tritiated Drain Collector Tan Tan Volume 24,700 gal Input 2,980 gpd 1,087,000 gal/yr Acti ity See Section 3.0 Collection Time 24 hrs Processing Time 6 hrs 1.3 Floor Drain Collector Tan Tan Volume 23,000 gal Input 3,200 gpd 1,168,000 gal/yr Acti ity See Section 3.0 Collection Time 24 hrs Processing Time 6 hrs

1. C CS Letdo n Input 4,863 gpd 1,775,107 gal/yr Acti ity 1.0 PCA Collection Time 24 hrs Processing Time 6 hrs 1.5 Chemical Drain Tan Laundry and ot Sho er Tan Input 1080 gal/day (NUREG-0017 Table 1-3) 394,200 gal/yr Acti ity NUREG-0017 Table 2-27 Released without processing or decay

1. Condensate Polisher Regeneration Waste Input 6,800 gpd o waste (NUREG-0017 Table 1-3) 2,482,000 gal/yr Acti ity See Section 3.0

1. Steam enerator lo do n Input 60,000 lb/hr (365 days)

Acti ity See Section 3.0 11.2-24 LIQUID WASTE SYSTEMS

WATTS BAR Table 11.2-1 Liquid Waste Processing System Calculation asis (Page 2 of 2)

1. aseous Acti ity All noble gases ent to gaseous waste processing system. All halogens remain in li uid.

2. Processing 2.1 Decontamination Factors e cept mobile demineralizer system based on NUREG-0017 Re 1 Table 1-4 2.2 CVCS letdown irst processed through CVCS mi ed bed and cation demineralizers DF = 20 or Cs Rb DF = 100 or all others 2.3 All processing through mobile demineralizer system DF = 1000 or all isotopes e cept Cobalt 58 based on i e (5) beds. The irst is loaded with ion speci ic iltration media/acti ated carbon, ollowed by another ion speci ic media, a cation bed, and then two (2) mi ed beds in series.

Flow rate 40 gpm DF = 100 or Co58

3. Lea age1 a) Reactor coolant pump seal lea age, 20 gal/day 0.1 PCA b) Reactor containment cooling system, 500 gal/day 0.001 PCA2 2

c) Other lea s and drains, 10 gal/day 1.67 PCA d) Primary coolant e uipment drains, 80 gal/day 1.0 PCA2 e) Reactor coolant sampling, 200 gal/day 0.05 PCA2 f) Spent uel pit liner drains, 700 gal/day 0.001 PCA2 g) Au iliary Building loor drains, 200 gal/day 0.1 PCA3 h) Secondary system sampling, 1400 gal/day 1 PCA(o SSC)(Note NUREG-0017 uses 1E-4 PCA (RC), this calculation uses actual SSC acti ities, there ore PCA = 1 SSC)3 i) CVCS letdown ( ia holdup tan s), 845 lb/hr (2431.654 gal/day) 1 PCA

) Input into the condensate resin regeneration waste (with resin DF=2 or Cs, Rb, and DF=10 or others) collected o er a 6-day time period consisting o

1) 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).

l) LHST release ta en directly rom NUREG-0017 Table 2-27.

1. The lea age alues are or 1 Unit.

2. Normally processed to TDCT.

3. Normally processed to FDCT.

. Tabulated inputs are based on dual unit system use unless otherwise noted.

LIQUID WASTE SYSTEMS 11.2-25

WATTS BAR Table 11.2-2 Com onent Design Parameters*

(Page 1 of )

Reactor Coolant Drain Tan Number per unit 1 Type Horizontal Volume, gal 350 Design pressure, internal, psig 25 Design pressure, e ternal, psig 60 Design temperature, (F 267 Normal operating pressure, range, psig 0.5-2.0 Normal operating temperature range, (F 50-200 Material o construction Austenitic SS Reactor Coolant Drain Tan Pum s Number per unit 2 Type open ace horizontal, centri ugal Design low rate, gpm Pump A 50 Pump B 150 Design head, t 175 Design pressure, psig 150 Design temperature, (F 300 Re uired NPSH at design low, t Pump A 6 Pump B 6 Material, wetted sur aces Austenitic SS Chemical Drain Tan Number (shared) 1 Type Vertical Volume, gal 600 Design pressure Atmospheric Design temperature, (F 180 Normal operating pressure Atmospheric Normal operating temperature, (F 50-140 Material o construction Austenitic SS

• For design codes and sa ety classes see Section 3.2 11.2-26 LIQUID WASTE SYSTEMS

WATTS BAR Table 11.2-2 Com onent Design Parameters*

(Page 2 of )

Chemical Drain Pum Number (shared) 1 Type Horizontal, centri ugal, mechanical seal Design low rate, gpm 20 Design head, t 100 Design pressure, psig 150 Design temperature, (F 180 Re uired NPSH at design low, t 5 Material Austenitic SS Tritiated Drain Collector Tan Number (shared) 1 Type Horizontal Volume, gal 24,700 Design pressure, psig Atmospheric Design temperature, (F 180 Normal operating pressure Atmospheric Normal operating temperature, (F 50-140 Material o construction Austenitic SS Tritiated Drain Collector Tan Pum s Number (shared) 2 Type Horizontal, centri ugal, mechanical seal Pum A Pum Design lowrate, gpm 100 20 Design head, t 100 100 Design pressure, psig 150 150 Design temperature, (F 180 180 Re uired NPSH at design low, t 20 5 Material Austenitic SS Floor Drain Collector Tan Number (shared) 1 Type Horizontal Volume, gal 23,000 Design pressure Atmospheric Design temperature, (F 180 Normal operating pressure Atmospheric Normal operating temperature, (F 50-140 Material o construction Austenitic SS

• For design codes and sa ety classes see Section 3.2 LIQUID WASTE SYSTEMS 11.2-27

WATTS BAR Table 11.2-2 Com onent Design Parameters*

(Page 3 of )

Floor Drain Collector Tan Pum s Number (shared) 2 Type Horizontal, centri ugal, mechanical seal Pum A Pum Design low rate, gpm 100 20 Design head, t 110 100 Design pressure, psig 150 150 Design temperature, (F 180 180 Re uired NPSH at design low, t 15 5 Material Austenitic SS Waste Condensate Tan s Number (shared) 3 Type Vertical Volume, each, gal 1500 Design pressure Atmospheric Design temperature, (F 180 Normal operating pressure Atmospheric Material Austenitic SS Waste Condensate Pum s Number (shared) 2 Type Horizontal, centri ugal Design low rate, gpm 20 Design head, t 100 Design pressure, psig 150 Design temperature, (F 180 Material, wetted sur aces Austenitic SS Laundry and ot Sho er Tan s Number (shared) 2 Type Vertical Design temperature, (F 180 Design pressure Atmospheric Volume, gal 600 Material Stainless steel Laundry and ot Sho er Pum Number (shared) 1 Design temperature, (F 180 Design pressure, psig 150

• For design codes and sa ety classes see Section 3.2 11.2-28 LIQUID WASTE SYSTEMS

WATTS BAR Table 11.2-2 Com onent Design Parameters*

(Page of )

Laundry ot Sho er Pum (Cont d)

Design head, t 100 Design low, gpm 20 Material contacting luid Stainless steel Type Horizontal, centri-ugal, mechanical seal onitor Tan (shared)

Number 1 Capacity, gal. 20,462 Design pressure Atmospheric Design Temperature, F 200 Material Austenitic stainless steel onitor Tan Pum s (shared)

Number 2 Design pressure, psig 150 Design Temperature, F 200 Design low, gpm 150 Design head, t 200 Material Austenitic stainless steel Cas Decontamination Collector Tan Number (shared) 1 Volume, gal 15,000 Design pressure Atmospheric Design temperature, (F 180 Material Carbon steel Cas Decontamination Collector Tan Pum s Number (shared) 2 Flow rate, gpm 100 Design pressure, psig 150 Design temperature, (F 180 Material Stainless steel Cas Decontamination Collector Tan Filters Number (shared) 2 Flow rate, gpm 40 Design pressure, psig 200 Design temperature, (F 250 Material 304 stainless steel

• For design codes and sa ety classes see Section 3.2 LIQUID WASTE SYSTEMS 11.2-29

WATTS BAR Table 11.2-2 Com onent Design Parameters*

(Page 5 of )

S ent Resin Storage Tan Number (shared) 1 Type Vertical Volume, each, t3 300 Design pressure, psig 100 Design temperature, (F 180 Normal operating pressure, psig 0.5 - 15 Normal operating temperature Ambient Material o construction Austenitic SS TDCT and FDCT Discharge Filters, Waste Condensate Tan Filter, and Waste Condenser Filter**

Number (shared) 1 Type Disposable synthetic cartridge Design pressure, psig 200 Design temperature, (F 250 Flow rate, gpm 35 Pressure drop at 20 gpm, clean ilter, psi 5 Ma imum di erential pressure, 100 ouled, psi 20 Retention or 25-micron particles, 98 Materials Housing Stainless steel Filter element Nylon Laundry Tan as et Strainer Number (shared) 1 Type Per orated stainless steel sheet Design low rate, gpm 20 Design pressure, psig 150 Design temperature, (F 180 Diameter o per oration, in. 1/16 Pressure drop at design low when clean, psi 0.5 Radiation le els outside Negligible Material, wetted sur aces Austenitic SS

• For design codes and sa ety classes see Section 3.2

• • Other ilter media are allowed per endor technical manual i they are e ual or iner.

11.2-30 LIQUID WASTE SYSTEMS

WATTS BAR Table 11.2-2 Com onent Design Parameters*

(Page of )

FDCT Discharge Pum s Strainer Number 1 Design low rate, gpm 100 Design pressure, psig 150 Design temperature, (F 180 Diameter o per oration, in. 3/16 Pressure drop at design low when clean, psi 2 Material Stainless steel igh-Crud, Lo -Conducti ity Tan s Number (shared) 2 Volume o each tan , gal. 19,000 Design pressure Atmospheric Design temperature, (F 140 Material Rubber lined carbon steel igh-Crud, Lo -Conducti ity Pum s Number (shared) 2 Flow rate, gpm 150 Design pressure, psig 150 Design temperature, (F 140 Material Stainless steel Head, t. water 330

• For design codes and sa ety classes see Section 3.2 LIQUID WASTE SYSTEMS 11.2-31

WATTS BAR Table 11.2-2 Com onent Design Parameters*

(Page of )

igh-Crud Pre-Filters Number 3 Type Bag Filter Design pressure, psig 220 Design Temperature, (F 140 Flow rate, gpm 150 Material 304 Stainless steel igh-Crud, Lo -Conducti ity Filter Number (shared) 1 Type Etched Disc-type Design pressure, psig 375 Design temperature, (F 140 Flow rate, gpm 100 (dirty)

Ma imum di erential pressure, 100 ouled, psi 75 Materials Stainless steel eutrali ation Tan Number (shared) 1 Volume, gal 20,000 Design pressure Atmospheric Design temperature, (F 140 Material Rubber lined carbon steel Neutralization Pumps Number (shared) 2 Flow rate, gpm 100 Design pressure, psig 150 Design temperature, (F 140 Material Stainless steel Head, t. water 135 on-Reclaimable Waste Tan Number (shared) 1 Volume, gal 10,000 Design pressure Atmospheric Design temperature, (F 140 Material Rubber lined carbon steel

• For design codes and sa ety classes see Section 3.2 on-Reclaimable Waste Pum s Number (shared) 2 Flow rate, gpm 115 Design pressure, psig 150 Design temperature, (F 140 Material Nic el Alloy Head, t. water 300

• For design codes and sa ety classes see Section 3.2 11.2-32 LIQUID WASTE SYSTEMS

Table 11.2-3 Radioacti e Liquid Releases From Westinghouse Designed PWR Plants istorical nformation A g. Discharge Fraction A erage 2 Total Released Concentration 1 CFR 2 Plant ear Cladding Fuel Defects Curies Ci ml Concentration WATTS BAR Yan ee Rowe 1970 Stainless Steel Neg. 0.036 1.5 10-10 1.5 10-3 LIQUID WASTE SYSTEMS 1971 0.001 0.0034 1.25 10-12 1.25 10-5 1972 0.0013 4.7 10-12 4.71 10-5 Connecticut 1970 Stainless Steel 0.01 29.5 4.02 10-8 4.02 10-1 Yan ee 1971 0.03 5.85 7.75 10-9 7.75 10-2 1972 12.26 1.61 10-8 1.61 10-1 San Ono re 1970 Stainless Steel 0.007 3.41 6.1 10-9 6.1 10-2 1971 0.015 9.21 1.34 10-8 1.34 10-1 1972 28.5 4.11 10-8 4.1 10-1 R. E. Ginna 1970 Zircaloy 0.4 9.35 1.43 10-8 1.43 10-1 1971 0.26 0.96 1.45 10-9 1.45 10-2 1972 0.38 5.69 10-10 5.7 10-3 H. B. Robinson 2 1970 Zircaloy 1971 0.001 0.74 1.01 10-9 1.01 10-2 1972 0.39 5.57 10-10 5.6 10-3 Point Beach 1970 Zircaloy 1971 0.01 0.14 2.48 10-10 2.48 10-3 11.2-33 1972 1.53 2.68 10-9 2.7 10-2

WATTS BAR Table 11.2- Total Annual Discharge Liquid Waste Processing System* Prior to Treatment Combined Tan s (Ci yr)

(Au . ldg) C CS L ST Con. Demin. T Br-84 0.09825 1.84 2.043E-04 3.028E-05 I-131 8.21 153.7 0.0016 4.449E-01 1.346E-02 I-132 5.778 108.2 4.232E-02 5.213E-03 I-133 18.39 344.4 3.352E-01 2.758E-02 I-134 3.439 64.41 1.036E-02 1.535E-03 I-135 18.21 340.9 1.650E-01 2.248E-02 Rb-88 0.6522 12.22 3.065E-04 1.305E-04 Cs-134 1.325 24.8 0.011 6.586E-02 4.551E-03 Cs-136 0.1586 2.969 0.00037 6.740E-03 5.382E-04 Cs-137 1.756 32.87 0.016 8.647E-02 6.074E-03 Na-24 5.408 101.2 7.115E-02 1.117E-02 Cr-51 0.5775 10.81 0.0047 3.626E-02 1.532E-03 Mn-54 0.301 5.634 0.0038 1.992E-02 7.746E-04 Fe-55 0.2259 4.229 0.0072 1.513E-02 5.843E-04 Fe-59 0.05624 1.053 0.0022 3.538E-03 1.421E-04 Co-58 0.8639 16.17 0.0079 5.616E-02 2.256E-03 Co-60 0.1001 1.873 0.014 6.721E-03 2.624E-04 Zn-65 0.09618 1.8 6.193E-03 2.502E-04 Sr-89 0.02619 0.4902 0.000088 1.691E-03 6.753E-05 Sr-90 0.00226 0.0423 0.000013 1.516E-04 5.845E-06 Sr-91 0.08633 1.616 8.539E-04 1.652E-04 Y-91m 0.05313 0.9947 5.010E-04 9.537E-05 Y-91 0.001647 0.03083 0.000084 1.172E-04 3.705E-06 Y-93 0.3921 7.341 3.913E-03 7.310E-04 Zr-95 0.07314 1.369 0.0011 4.704E-03 1.898E-04 Nb-95 0.05311 0.9941 0.0019 3.509E-03 1.318E-04 Mo-99 1.071 20.04 0.00006 3.889E-02 2.664E-03 Tc-99m 0.9414 17.62 3.534E-02 2.056E-03 Ru-103 1.403 26.26 0.00029 9.169E-02 3.666E-03 Ru-106 16.97 317.7 0.0089 1.108E+00 4.410E-02 Te-129m 0.03551 0.6646 2.244E-03 9.210E-05 Te-129 0.3423 6.411 2.288E-03 2.597E-04 Te-131m 0.2189 4.098 4.875E-03 5.036E-04 Te-131 0.07575 1.418 9.200E-04 9.882E-05 Te-132 0.2891 5.412 1.147E-02 7.144E-04 Ba-140 2.392 44.78 0.00091 1.359E-01 6.048E-03 La-140 4.315 80.78 1.946E-01 1.031E-02 Ce-141 0.02804 0.5249 0.00023 1.768E-03 7.200E-05 Ce-143 0.417 7.806 9.902E-03 9.526E-04 Ce-144 0.7542 14.12 0.0039 4.925E-02 1.906E-03 Np-239 0.3604 6.746 1.217E-02 8.781E-04 Total 95.94 1796.34 0.086 3.09 0.17

• Per unit in accordance with 10CFR20, Appendi I.

11.2-34 LIQUID WASTE SYSTEMS

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 1 of 3)

Column 1 Column 2 Column 3 Column 4 Column 5 Column 6 Column 7 Column 8 WATTS BAR CD = Condensate Polishing Demineralizer, OTHER OPERATIONAL MODES EXPECTED OPERATION LIQUID WASTE SYSTEMS MD = Mobile Demineralizer MD DF CVCS DF SGB processed SGB processed by LRW SGB with no CD 6 Column 6 and by CD CD and MD No SGB process Column 7 Br-84 1000 50 0.0003696 0.000165534 1.65E-04 5.23E-04 6.88E-04 I-131 1000 50 0.471244 0.0267889 2.63E-02 1.14E+00 1.16E+00 I-132 1000 50 0.055475 0.01319732 1.32E-02 1.08E-01 1.21E-01 I-133 1000 50 0.388058 0.0531932 5.29E-02 8.57E-01 9.10E-01 I-134 1000 50 0.0166222 0.00627256 6.26E-03 2.65E-02 3.28E-02 I-135 1000 50 0.212508 0.047673 4.75E-02 4.22E-01 4.70E-01 Rb-88 1000 2 0.0071992 0.006893007 6.89E-03 7.84E-04 7.68E-03 Cs-134 1000 2 0.095136 0.02934186 2.93E-02 1.68E-01 1.98E-01 Cs-136 1000 2 0.0092913 0.00255804 2.55E-03 1.72E-02 1.98E-02 Cs-137 1000 2 0.126735 0.04035147 4.03E-02 2.21E-01 2.61E-01 Na-24 1000 50 0.089752 0.01867315 1.86E-02 0.00E+00 1.86E-02 Cr-51 1000 50 0.0432857 0.00706196 7.03E-03 9.27E-02 9.98E-02 Mn-54 1000 50 0.0249083 0.0050082 4.99E-03 5.10E-02 5.59E-02 Fe-55 1000 50 0.0232248 0.00810991 8.09E-03 0.00E+00 8.09E-03 Fe-59 1000 50 0.0059574 0.002422938 2.42E-03 9.05E-03 1.15E-02 Co-58 100 50 0.078189 0.0225906 2.20E-02 1.44E-01 1.66E-01 Co-60 1000 50 0.021121 0.014406681 1.44E-02 1.72E-02 3.16E-02 Zn-65 1000 50 0.0065754 0.000388573 3.82E-04 0.0E+00 3.82E-04 11.2-35

Table 11.2-5 Total Annual Discharge Liquid Waste Processing System 11.2-36 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 WATTS BAR CD = Condensate Polishing Demineralizer, OTHER OPERATIONAL MODES EXPECTED OPERATION MD = Mobile Demineralizer MD DF CVCS DF SGB processed SGB processed by LRW SGB with no CD 6 Column 6 and by CD CD and MD No SGB process Column 7 Sr-89 1000 50 0.0018825 0.000193215 1.92E-04 4.33E-03 4.52E-03 Sr-90 1000 50 0.0001736 2.21026E-05 2.20E-05 3.88E-04 4.10E-04 Sr-91 1000 50 0.0011378 0.000284704 2.84E-04 2.18E-03 2.47E-03 Y-91m 1000 50 0.0006694 0.000168895 1.68E-04 0.00E+00 1.68E-04 Y-91 1000 50 0.0002072 9.00858E-05 9.00E-05 3.00E-04 3.90E-04 Y-93 1000 50 0.0051829 0.001273833 1.27E-03 0.00E+00 1.27E-03 Zr-95 1000 50 0.0060943 0.001395024 1.39E-03 1.20E-02 1.34E-02 Nb-95 1000 50 0.0056138 0.002108301 2.10E-03 8.98E-03 1.11E-02 Mo-99 1000 50 0.0430858 0.00423469 4.20E-03 9.95E-02 1.04E-01 Tc-99m 1000 50 0.0386898 0.00338514 3.35E-03 0.00E+00 3.35E-03 Ru-103 1000 50 0.0975742 0.00597589 5.88E-03 0.00E+00 5.88E-03 Ru-106 1000 50 1.184324 0.077432 7.63E-02 0.00E+00 7.63E-02 Te-129m 1000 50 0.0023849 0.000143146 1.41E-04 0.00E+00 1.41E-04 Te-129 1000 50 0.0030182 0.000732508 7.30E-04 0.00E+00 7.30E-04 Te-131m 1000 50 0.0056795 0.000809335 8.05E-04 0.00E+00 8.05E-04 Te-131 1000 50 0.0011229 0.00020385 2.03E-04 0.00E+00 2.03E-04 Te-132 1000 50 0.0125817 0.00112321 1.11E-03 2.93E-02 3.05E-02 Ba-140 1000 50 0.1461456 0.0103815 1.02E-02 3.48E-01 3.58E-01 LIQUID WASTE SYSTEMS

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 Column 8 WATTS BAR CD = Condensate Polishing Demineralizer, OTHER OPERATIONAL MODES EXPECTED OPERATION MD = Mobile Demineralizer LIQUID WASTE SYSTEMS MD DF CVCS DF SGB processed SGB processed by LRW SGB with no CD 6 Column 6 and by CD CD and MD No SGB process Column 7 La-140 1000 50 0.2108406 0.0164352 1.62E-02 4.98E-01 5.14E-01 Ce-141 1000 50 0.0021085 0.000342306 3.41E-04 0.00E+00 3.41E-04 Ce-143 1000 50 0.0114277 0.00153622 1.53E-03 0.00E+00 1.53E-03 Ce-144 1000 50 0.0560926 0.00689185 6.84E-03 1.26E-01 1.33E-01 Np-239 1000 50 0.0135434 0.00138559 1.37E-03 0.00E+00 1.37E-03 H-3 1 1 1252.80 (3326.4) 1252.80 (3326.4) 1257.64 (3326.4)

(TPC)

Unplanned 0.16 0.16 0.16 0.16 total (w/o H3) 3.5252328 0.4416449 0.438 4.402 4.84 w/unplanned 3.685 0.602 0.598 5.000 total (w/H3) 1256.33 (3329.93) 1253.24 (3326.84) 1257.64 (3331.24) w/unplanned 1256.49 (3330.09) 1253.40 (3327.00) 1257.80 (3331.40) 11.2-37

WATTS BAR Table 11.2-5 Total Annual Discharge Liquid Waste Processing System*

Annual Discharge (Ci) After Processing Total 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 DF MD = Mobile Demineralizer (Processes Tan s, 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 the unplanned release rom NUREG-0017 Column 1 Source term isotopes Column 2 Decontamination actors or the Mobile Demineralizer Column 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 de inition or items A thru A (Ci/yr) = Reactor Coolant Drain Tan + Tritiated Drain Collector Tan + Floor Drain Collector Tan B (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 = Condensate Demineralizer 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 a erage o 365 days but does not represent a constraint on the plant since the actual alue or indi idual releases may be greater. Howe er, the total o all yearly releases must remain 5 Ci 11.2-38 LIQUID WASTE SYSTEMS

WATTS BAR Table 11.2-5a D S (FOR 1 FA L D FU L) L U D R L AS S CO C TRAT O ( FFLU T CO C TRAT O L T)

AS L DATA W T O PROC SS (Sheet 1 of 1)

. Rel. Des Design 1 CFR2 Ci yr Ratio Design Ci yr uCi cc CL C CL Br-84 3.696E-04 2.500E+00 9.241E-04 2.320E-11 4.000E-04 5.806E-08 I-131 4.712E-01 5.241E+01 2.470E+01 6.210E-07 1.000E-06 6.207E-01 I-132 5.548E-02 4.000E+00 2.219E-01 5.580E-09 1.000E-04 5.577E-05 I-133 3.881E-01 2.685E+01 1.042E+01 2.620E-07 7.000E-06 3.740E-02 I-134 1.662E-02 1.650E+00 2.740E-02 6.890E-10 4.000E-04 1.722E-06 I-135 2.125E-01 7.910E+00 1.682E+00 4.230E-08 3.000E-05 1.409E-03 Rb-88 7.199E-03 1.814E+01 1.306E-01 3.280E-09 4.000E-04 8.204E-06 Cs-134 9.514E-02 4.060E+01 3.862E+00 9.710E-08 9.000E-07 1.079E-01 Cs-136 9.291E-03 1.652E+02 1.535E+00 3.860E-05 6.000E-06 6.429E-03 Cs-137 1.267E-01 1.532E+02 1.942E+01 4.880E-07 1.000E-06 4.880E-01 Cr-51 4.329E-02 2.900E-01 1.261E-02 3.170E-10 5.000E-04 6.340E-07 Mn-54 2.491E-02 4.700E-01 1.171E-02 2.940E-10 3.000E-05 9.813E-06 Fe-59 5.957E-03 3.480E+00 2.074E-02 5.210E-10 1.000E-05 5.212E-05 Co-58 7.819E-02 5.370E+00 4.200E-01 1.060E-08 2.000E-05 5.278E-04 Co-60 2.112E-02 1.380E+00 2.915E-02 7.330E-10 3.000E-06 2.442E-04 Sr-89 1.883E-03 2.245E+01 4.226E-02 1.060E-09 8.000E-06 1.328E-04 Sr-90 1.736E-04 1.349E+01 2.342E-03 5.890E-11 5.000E-07 1.177E-04 Sr-91 1.138E-03 1.860E+00 2.119E-03 5.330E-11 2.000E-05 2.663E-06 Y-90 0.000E+00 1.567E+01 0.000E+00 0.000E+00 7.000E-06 0.000E+00 Y-91 2.072E-04 1.115E+03 2.310E-01 5.810E-09 8.000E-06 7.258E-04 Zr-95 6.094E-03 1.710E+00 1.040E-02 2.620E-10 2.000E-05 1.308E-05 Nb-95 5.614E-03 2.340E+00 1.313E-02 3.300E-10 3.000E-05 1.100E-05 Mo-99 4.309E-02 7.852E+02 3.383E+01 8.500E-07 2.000E-05 4.251E-02 Te-132 1.258E-02 1.453E+02 1.828E+00 4.590E-08 9.000E-06 5.103E-03 Ba-140 1.461E-01 3.100E-01 4.587E-02 1.150E-09 8.000E-06 1.441E-04 La-140 2.108E-01 6.000E-02 1.198E-02 3.010E-10 9.000E-06 3.345E-05 Ce-144 5.609E-02 8.000E-02 4.530E-03 1.140E-10 3.000E-06 3.795E-05 Pr-144 0.000E+00 8.000E-02 0.000E+00 0.000E+00 6.000E-04 0.000E+00 H-3 1.253E+03 1.000E+00 1.253E+03 3.150E-05 1.000E-03 3.149E-02 H-3 (TPC) 3.326E+03 1.000E+00 3.326E+03 8.360E-05 1.000E-03 8.360E-02 Total 1.3430832 Total (TPC) 1.3957987 Note The abo e numbers are based on one unit operation.

This Table is based on column 4 o Table 11.2-5 ratioed up to 1 ailed uel.

LIQUID WASTE SYSTEMS 11.2-39

WATTS BAR Table 11.2-5b D S (FOR 1 FA L D FU L) L U D R L AS S CO C TRAT O ( FFLU T CO C TRAT O L T)

WAST PROC SS D O L D RAL RS (Sheet 1 of 1)

. Rel. Des Design Design 1 CFR2 Ci yr Ratio Ci yr uCi cc CL C CL Br-84 1.655E-04 2.500E+00 4.138E-04 1.040E-11 4.000E-04 2.600E-08 I-131 2.679E-02 5.241E+01 1.404E+00 3.530E-08 1.000E-06 3.529E-02 I-132 1.320E-02 4.000E+00 5.279E-02 1.330E-09 1.000E-04 1.327E-05 I-133 5.319E-02 2.685E+01 1.428E+00 3.590E-08 7.000E-06 5.127E-03 I-134 6.273E-03 1.650E+00 1.034E-02 2.600E-10 4.000E-04 6.496E-07 I-135 4.767E-02 7.910E+00 3.773E-01 9.480E-09 3.000E-05 3.161E-04 Rb-88 6.893E-03 1.814E+01 1.250E-01 3.140E-09 4.000E-04 7.855E-06 Cs-134 2.934E-02 4.060E+01 1.191E+00 2.990E-08 9.000E-07 3.326E-02 Cs-136 2.558E-03 1.652E+02 4.226E-01 1.060E-08 6.000E-06 1.770E-03 Cs-137 4.035E-02 1.532E+02 6.183E+00 1.550E-07 1.000E-06 1.554E-01 Cr-51 7.062E-03 2.900E-01 2.058E-03 5.170E-11 5.000E-04 1.034E-07 Mn-54 5.008E-03 4.700E-01 2.355E-03 5.920E-11 3.000E-05 1.973E-06 Fe-59 2.423E-03 3.480E+00 8.434E-03 2.120E-10 1.000E-05 2.120E-05 Co-58 2.259E-02 5.370E+00 1.214E-01 3.050E-09 2.000E-05 1.525E-04 Co-60 1.441E-02 1.380E+00 1.988E-02 5.000E-10 3.000E-06 1.665E-04 Sr-89 1.932E-04 2.245E+01 4.337E-03 1.090E-10 8.000E-06 1.363E-05 Sr-90 2.210E-05 1.349E+01 2.982E-04 7.490E-12 5.000E-07 1.499E-05 Sr-91 2.847E-04 1.860E+00 5.303E-04 1.330E-11 2.000E-05 6.664E-07 Y-90 0.000E+00 1.587E+01 0.000E+00 0.000E+00 7.000E-06 0.000E+00 Y-91 9.009E-05 1.115E+03 1.005E-01 2.520E-09 8.000E-06 3.156E-04 Zr-95 1.395E-03 1.710E+00 2.382E-03 5.990E-11 2.000E-05 2.993E-06 Nb-95 2.108E-03 2.340E+00 4.931E-03 1.240E-10 3.000E-05 4.131E-06 Mo-99 4.235E-03 7.852E+02 3.325E+00 8.360E-08 2.000E-05 4.178E-03 Te-132 1.123E-03 1.453E+02 1.631E-01 4.100E-09 9.000E-06 4.556E-04 Ba-140 1.038E-02 3.100E-01 3.258E-03 8.190E-11 8.000E-06 1.024E-05 La-140 1.644E-02 6.000E-02 9.338E-04 2.350E-11 9.000E-06 2.608E-06 Ce-144 6.892E-03 8.000E-02 5.566E-04 1.400E-11 3.000E-06 4.663E-06 Pr-144 0.000E+00 8.000E-02 0.000E+00 0.000E+00 6.000E-04 0.000E+00 H-3 1.253E+03 1.000E+00 1.253E+03 3.150E-05 1.000E-03 3.149E-02 H-3 (TPC) 3.326E+03 1.000E+00 3.326E+03 8.360E-05 1.000E-03 8.360E-02 Total 2.680E-01 Total (TPC) 3.201E-01 Note The abo e calculations are or 1 unit operation.

This Table is based on column 5 o Table 11.2-5 ratioed up to 1 ailed uel.

11.2-40 LIQUID WASTE SYSTEMS

WATTS BAR Table 11.2-5c Deleted by Amendment LIQUID WASTE SYSTEMS 11.2-41

WATTS BAR Table 11.2-5d no CD rocess S D at ma Allo able Concentration ith 2 g m dilution Ci yr liquid liquid A S scaled to des des Ci yr . 2 Ci des ansi Ci yr uCi cc 1 CFR2 C CL Br-84 0.00016533 0.000522532 2.50 0.00093586 2.35E-11 4.0E-04 5.88E-08 I-131 0.026344 1.137908188 52.41 2.51862098 6.33E-08 1.0E-06 0.0633001 I-132 0.013155 0.108240671 4.00 0.16086067 4.04E-09 1.0E-04 4.043E-05 I-133 0.052858 0.857331591 26.85 2.2763383 5.72E-08 7.0E-06 0.008173 I-134 0.0062622 0.02649748 1.65 0.03681979 9.25E-10 4.0E-04 2.313E-06 I-135 0.047508 0.422015849 7.91 0.79797844 2.01E-08 3.0E-05 0.0006685 Rb-88 0.0068927 0.000783926 18.14 0.12579858 3.16E-09 4.0E-04 7.904E-06 Cs-134 0.029276 0.168448265 40.60 1.35691917 3.41E-08 9.0E-07 0.0378925 Cs-136 0.0025513 0.017238708 165.20 0.43870897 1.10E-08 6.0E-06 0.0018377 Cs-137 0.040265 0.221161881 153.22 6.3904673 1.61E-07 1.0E-06 0.1606107 Cr-51 0.0070257 0.09274118 0.29 0.09478855 2.38E-09 5.0E-04 4.765E-06 Mn-54 0.00498828 0.050948822 0.47 0.0532945 1.34E-09 3.0E-05 4.465E-05 Fe-59 0.0024194 0.009049043 3.48 0.017471 4.39E-10 1.0E-05 4.391E-05 Co-58 0.022029 0.143638849 5.37 0.26197645 6.58E-09 2.0E-05 0.0003292 Co-60 0.01439996 0.017190112 1.38 0.03706102 9.31E-10 3.0E-06 0.0003105 Sr-89 0.000191524 0.004325023 22.45 0.00862454 2.17E-10 8.0E-06 2.709E-05 Sr-90 0.000021951 0.000387743 13.49 0.00068391 1.72E-11 5.0E-07 3.438E-05 Sr-91 0.00028385 0.002183996 1.86 0.00271274 6.82E-11 2.0E-05 3.409E-06 Y-90 0 0 15.87 0 0.00E+00 7.0E-06 0 Y-91 8.99686E-05 0.000299759 1115.17 0.10063037 2.53E-09 8.0E-06 0.0003161 Zr-95 0.00139032 0.012031288 1.71 0.01440501 3.62E-10 2.0E-05 1.81E-05 Nb-95 0.002104792 0.00897487 2.34 0.01389794 3.49E-10 3.0E-05 1.164E-05 Mo-99 0.0041958 0.099467857 785.19 3.39394786 8.53E-08 2.0E-05 0.004265 Te-132 0.00111174 0.029336496 145.25 0.19081828 4.80E-09 9.0E-06 0.0005329 Ba-140 0.0102456 0.347587599 0.31 0.35080337 8.82E-09 8.0E-06 0.0011021 La-140 0.0162406 0.497722934 0.06 0.4986457 1.25E-08 9.0E-06 0.0013925 Ce-144 0.0068426 0.125965337 0.08 0.12651795 3.18E-09 3.0E-06 0.0010599 Pr-144 0 0 0.08 0 0.00E+00 6.0E-04 0 H-3 1252.80 1 1252.80 3.15E-05 1.0E-03 0.0314864 H-3 (TPC) 3326.40 1 3326.40 8.36E-05 1.0E-03 0.0836019 Total 0.3135157 Total (TPC) 0.3656312 Note This Table is based on column 8 o Table 11.2-5, ratioed up to 1 ailed uel with SGBD at ma imum allowable concentration o 3.65E-5 uCi/cc gross gamma) (TPC Unit 1 only).

11.2-42 LIQUID WASTE SYSTEMS

WATTS BAR Table 11.2- Tennessee Ri er Reaches Within 5 ile Radius Do nstream of W eginning nding Si e Recreation ame TR TR (acres) isits y Chic amauga La e below WBN 528.0 510.01 4799 120,986 Chic amauga La e abo e 510.01 484.0 22101 1,297,880 Se uoyah Nuclear Plant Chic amauga La e below 484.0 471.0 9889 7,421,905 Se uoyah Nuclear Plant Nic a ac La e (Part 1) 471.0 460.0 1799 284,000 TRM - Tennessee Ri er Mile 1

100 Mi ing Point Public Water Su lies Within 5 ile Radius Do nstream of W ame TR stimated 2 Po ulation Dayton, TN 504 19,170 East Side Utility, TN 473.0 49,700 Chattanooga, TN 465 237,048 Soddy-Daisy/Falling Water Utility District, TN 487 11,452 LIQUID WASTE SYSTEMS 11.2-43

WATTS BAR Table 11.2- Watts ar uclear Plant Doses From Liquid ffluents For ear 2 ndi idual Dose (mrem)

Adult Total Body Bone GI Tract Thyroid Li er idney Lung S in 0.72 0.56 0.132 0.88 0.96 0.352 0.136 0.031 Teen Total Body Bone GI Tract Thyroid Li er idney Lung S in 0.44 0.60 0.104 0.80 1.00 0.356 0.152 0.031 Child Total Body Bone GI Tract Thyroid Li er idney Lung S in 0.188 0.76 0.06 0.92 0.88 0.312 0.128 0.031 nfant Total Body Bone GI Tract Thyroid Li er idney Lung S in 0.032 0.036 0.033 0.264 0.036 0.034 0.032 0.031 Po ulation Dose (Person-rem)

Total ody Bone GI Tract Thyroid Li er idney Lung S in 1.619 1.761 1.420 15.336 2.130 1.392 1.037 0.315 11.2-44 LIQUID WASTE SYSTEMS

WATTS BAR 11.3 AS OUS WAST S ST S 11.3.1 Design ases The Gaseous Waste Processing System (GWPS) is designed to remo e 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 radioacti e gases and holdup in the nine waste gas decay tan s to reduce the concentration o radioisotopes in the released gases.

The plant gaseous e luent releases during normal operation o the plant are limited at the site boundary not to e ceed 10 CFR 50 Appendi I and 40 CFR 190 limits as speci ied in the O site Dose Calculation Manual (ODCM).

Although plant operating procedures, e uipment inspection, and pre enti e maintenance are per ormed during plant operations to minimize e uipment mal unction, o erall radioacti e release limits ha e been established as a basis or controlling plant discharges during operation with the occurrence o a combination o e uipment aults. A combination o e uipment aults which include operation with uel de ects and ailure o up to two TPBARs (Unit 1 only) in combination with such occurrences as (1) Steam generator tube lea s.

(2) Lea age in Li uid Waste Processing System.

(3) Lea age o Gaseous Waste Processing System.

(4) Lea age in Reactor Coolant System e uipment.

(5) Lea age in au iliary system e uipment.

The radioacti e releases rom the plant resulting rom e uipment aults o moderate re uency are within 10 CFR 50 Appendi I and 40 CFR 190 limits as speci ied in the ODCM.

11.3.2 S ST D SCR PT O S The GWPS consists o two waste gas compressor pac ages, nine waste gas decay tan s, au iliary ser ices, and the associated piping, al es and instrumentation. The e uipment ser es 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 gi es process parameters and system acti ities or ey locations in the system.

Table 11.3-5 gi es the e pected annual gaseous releases rom the GWPS.

ASE US WASTE SYSTEMS 11.3-1

WATTS BAR The bases used or estimating the system acti ities and gaseous releases are gi en in Table 11.3-3.

Gaseous wastes are recei ed rom the ollowing degassing o the reactor coolant and purging o the olume control tan prior to a cold shutdown, displacing o co er gases caused by li uid accumulation in the tan s connected to the ent header, purging o some e uipment, sampling and gas analyzer operation.

Au iliary Ser ices The au iliary ser ices portion o the GWPS consists o two automatic gas analyzers and its instrumentation, al es, and tubing, a nitrogen and a hydrogen supply mani old and the necessary instrumentation, al es, and piping.

One automatic se uential gas analyzer determines the uantity o o ygen in the gas space o the olume control tan , pressurizer relie tan , holdup tan s, gas decay tan s, reactor coolant drain tan , and spent resin storage tan and pro ides a local and main control room (MCR) alarm on 2 o ygen concentration (hi-alarm), and 4 concentration (hi-hi alarm). Hydrogen (H2) concentration may be monitored by the se uential analyzer. Howe er, the H2 concentration is assumed to e ceed the lower lammability limit. There ore, operator action or the se uential analyzer is based primarily on the O2 concentration. I the H2 concentration is low (i.e, less than or e ual to 4 ), this may be considered a mitigating actor when determining contingency actions or high or high-high O2 concentration. A second o ygen monitor is installed to continuously sample the discharge o the operating gas compressor. This monitor sounds an alarm at 2 o ygen (hi-alarm) and 4 o ygen (hi-hi alarm) in the MCR.

Operator action is relied upon to pre ent the ormation o a combustible gas mi ture in the GWPS. This is accomplished by reducing o ygen concentrations on a hi-alarm and suspending additions to the Waste Gas System and reducing o ygen concentrations on a hi-hi alarm. For the se uential analyzer on a hi-alarm, the operator determines the source o the high o ygen and reduces the o ygen concentration. For a se uential analyzer hi-hi alarm, the operator minimizes an increase in ent header pressure, suspends additions to the waste gas system, and reduces o ygen concentration.

As protection against an uncontrolled release o radioacti e materials rom the GWPS, grab sampling and analysis are per ormed when either the waste disposal system waste gas se uential or continuous o ygen analyzer is inoperable. Grab sampling and analysis are per ormed or the continuous analyzer only during periods o compressor operation or batch trans ers.

The nitrogen and hydrogen supply pac ages are designed to pro ide a supply o gas to the Nuclear Steam Supply System. Two headers are pro ided or each pac age one or operation and one or bac up. The pressure regulator (nitrogen only) in the bac up header is set slightly lower than that in the operating header. When the operating header is e hausted, its discharge pressure alls below the set pressure o the bac up header, which comes into ser ice automatically to ensure a continuous supply o nitrogen gas. An alarm alerts the operator that one header (nitrogen or hydrogen) is e hausted. A two header (low and high pressure) li uid nitrogen (N2) supply is pro ided to supplement the N2 pac age.

11.3-2 ASE US WASTE SYSTEMS

WATTS BAR Nitrogen is supplied or the ollowing spent resin storage tan , reactor coolant drain tan , pressurizer relie tan , olume control tan , waste gas decay tan s, and Chemical and Volume System (CVCS) holdup tan s. In addition, there is a truc ill connection in the nitrogen supply header or the direct illing o the sa ety in ection system accumulators. Ma eup nitrogen or the accumulators is supplied rom the pac age. Hydrogen is supplied or the olume control tan .

The design and material o al es and mani olds are the same as or the main GWPS.

11.3.3 S ST D S 11.3.3.1 Com onent Design The GWPS e uipment parameters are gi en in Table 11.3-1. For urther in ormation on design codes and sa ety classes see Section 3.2.

Waste as Com ressors The two waste gas compressors are pro ided or remo al 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 recei ing letdown low at the ma imum rate. The second unit is pro ided or bac up during pea load conditions, such as when degassing the reactor coolant or or ser ice when the irst unit is down or maintenance. Operation o the bac up unit can be controlled manually or automatically by ent header pressure. The compressors are o the water sealed centri ugal type and are pro ided with mechanical seals to minimize lea age.

Construction is o cast iron e ternal and bronze internals with a stainless steel sha t.

as Decay Tan s Nine tan s are pro ided to hold radioacti e waste gases or decay or contain nitrogen gas as and inert. This arrangement is ade uate or a plant operating with one percent uel de ects. Nine tan s are pro ided so that during normal operation, a minimum o 60 days are a ailable or decay. The 60 days de ine the design characteristics, not an operational parameter.

al es The al es handling gases are selected to minimize lea age.

Pi ing The piping or gaseous waste is typically carbon steel. All piping oints are welded e cept where langed connections are necessary or maintenance.

11.3.3.2 nstrumentation Design The system instrumentation is shown on Flow Diagrams and Electrical Control Diagrams, Figures 11.3-1 and 11.3-2. Ade uate instrumentation is pro ided to monitor appropriate system parameters.

ASE US WASTE SYSTEMS 11.3-3

WATTS BAR The instrumentation readout is located mainly on the Waste Processing System panel in the Au iliary Building. Some instruments ha e local readout at the e uipment 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 o ygen analyzer alarm on the waste gas compressor discharge is in the main control room. The continuous o ygen analyzer on the waste gas compressor is pro ided to alert the operator that o ygen is present, and to stop processing and manually switch to the standby gas decay tan .

An automatic se uential gas analyzer is pro ided to monitor o ygen concentrations.

The analyzer records the o ygen concentrations and alarms at high o ygen le el. The instrumentation diagram and sample collection points are shown in Figure 11.3-2.

Hydrogen (H2) concentration may be monitored by the se uential analyzer. Howe er, the H2 concentration is assumed to e ceed the lower lammability limit so that only O2 concentration is used to determine the need or operation action.

11.3. O erating Procedure E uipment installed to reduce radioacti e e luents to the minimum practicable le el will be maintained in good operating order and will be operated to the ma imum e tent practicable. In order to assure that these conditions are met, administrati e controls are e ercised on o erall operation o the system pre enti e maintenance is utilized to maintain e uipment in optimum condition and e perience a ailable rom similar plants is used in planning or operation at Watts Bar Nuclear Plant.

Administrati e controls are e ercised through the use o instructions co ering such areas as al e alignment or arious operations, e uipment operating instructions, and other instructions pertinent to the proper operation o the processing e uipment.

Discharge permit orms are utilized to assure proper procedures are ollowed and in assuring proper al e alignments and other operating conditions be ore a release.

These orms are signed and eri ied by those personnel per orming the analysis and appro ing the release.

Pre enti e maintenance is carried out on all e uipment as described in the plant s maintenance program.

Gaseous wastes are recei ed rom degassing o the reactor coolant, purging o VCT, and nitrogen rom the closed co er gas system. The components connected to the ent header are limited to those which normally contain no air or aerated li uids to pre ent ormation o a combustible mi ture o hydrogen and o ygen.

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 trans er gas between gas decay tan s.

11.3-4 ASE US WASTE SYSTEMS

WATTS BAR To compress gas into the gas decay tan s, the operator selects two tan s at the au iliary control panel, one to recei e gas, and one or standby. When the tan in ser ice 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 gas compressor is sampled automatically by the continuous gas analyzer as it is being trans erred to the tan being illed and an alarm alerts the operator to a high o ygen content. On high o ygen signal, the tan must be isolated and operator action is re uired to direct low to the standby tan and to select a new standby tan .

I it should become necessary to trans er gas rom one decay tan to another, the tan to be emptied is discharged to the holdup tan return line. The tan to recei e gas is opened to the inlet header and the return line pressure regulator setpoint is increased abo e setpoint. The return line isolation al e is closed and the crosso er between the return line and the compressor suction is opened. With this arrangement, gas is trans erred by the compressor which is in ser ice.

As the Chemical and Volume Control System holdup tan s li uid is withdrawn, gas rom the gas decay tan s is returned to the holdup tan s. The gas decay tan selected to supply the returning co er gas is attached to the return header rom the au iliary control board by manually opening the appropriate al e.

To ma imize residence time or decay in the decay tan s, the last tan illed should be the irst tan attached to the header. A bac up supply o gas or the holdup tan s is pro ided by the nitrogen header.

Be ore a gas decay tan is discharged to the atmosphere ia the plant ent, a gas sample is ta en to determine acti ity concentration o the gas and total acti ity in entory in the tan . Total tan acti ity in entory is determined rom the acti ity concentration and pressure in the tan .

To release the gas, the appropriate local manual stop al e is opened to the plant ent and the gas discharge modulating al e is opened at the au iliary control panel. The plant ent acti ity le el is also indicated on the panel to aid in setting the al e properly.

I there should be a high acti ity le el in the ent during release, the modulating al e closes.

Refueling When 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 le el o 5 cc/ g and a desired acti ity concentration o Xe-133 to 1 Ci/cc. At the start o the de-gassing operation, the olume control tan gas space contains H2 and traces o ission gases. This atmosphere is replaced with nitrogen by raising and lowering the tan li uid le el while enting and introducing nitrogen, until the abo e hydrogen and Xe-133 desired limits abo e are met.

ASE US WASTE SYSTEMS 11.3-5

WATTS BAR Gas e ol ed rom the olume control tan during this operation is pumped by the waste-gas compressors to the gas-decay tan s.

Operation o the gaseous side o the GWPS is the same during the actual re ueling operation as during normal operation.

Au iliary Ser ices During normal operation the GWPS supplies nitrogen and hydrogen rom standard cylinders to primary plant components. Two headers are pro ided, one or operation and one or bac up. The pressure regulator in the nitrogen operating header is set abo e the bac up header pressure and an alarm alerts the operator when this pressure alls below setpoint. The standby header or nitrogen comes into ser ice automatically to ensure a continuous supply o gas. A ter the e hausted header has been replaced, the operator manually sets the operating pressure and the bac up pressure to their respecti e set points. When the supply header pressure or the hydrogen alls below the setpoint, an alarm alerts the operator to manually select the bac up. A two header (low and high) li uid nitrogen (N2) supply is pro ided to supplement the N2 cylinders and headers. This li uid N2 supply is normally used to maintain a charge on both the cylinders and headers. I the li uid supply is depleted, then the cylinders supply the N2 or the headers.

11.3.5 Performance Tests Initial per ormance tests are per ormed to eri y the operability o the components, instrumentation and control e uipment.

During reactor operation the system is used at all times and hence is monitored.

11.3. Deleted by Amendment 11.3. Radioacti e Releases 11.3. .1 RC Requirements The ollowing documents ha e been issued by the NRC to pro ide regulations and guidelines or radioacti e 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 pro iding assurance that the e posures to indi iduals in unrestricted areas are as low as reasonably achie able during normal plant operation and during anticipated operational occurrences.

11.3. .2 Westinghouse PWR erience Releases A sur ey has been per ormed o gaseous discharges rom di erent Westinghouse PWR plants or one calendar year. The results are presented in Table 11.3-2.

11.3-6 ASE US WASTE SYSTEMS

WATTS BAR 11.3. .3 ected aseous Waste Processing System Releases Gaseous 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 blan eting system. The gas decay tan capacity permits at least 60 days decay or waste gases be ore discharge during normal operation.

The uantities and isotopic concentration o gases discharged rom the GWPS ha e been estimated. The analysis is based on input sources to the GWPS per NUREG 0017, modi ied to re lect WBN plant-speci ic parameters.

The e pected gaseous releases in curies per year per reactor unit are gi en in Table 11.3-5.

11.3. . Releases from entilation Systems A detailed re iew o the entire plant has been made to ascertain those items that could possibly contribute to airborne radioacti e releases.

During normal plant operations, airborne noble gases and/or iodines can originate rom reactor coolant lea age, e uipment drains, enting and sampling, secondary side lea age, condenser air e ector and gland seal condenser e hausts, and GWPS lea age.

The assumptions used to estimate the annual uantity o radioacti e gaseous e luents are gi en 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 Releases The estimated releases listed in Table 11.3-7c ha e been used in calculating the site boundary doses as shown in Table 11.3-10. Table 11.3-7a is the e pected 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 e pected 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 ob ecti es 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 radioacti e wastes are released to the atmosphere through ents located on the Shield Building, Au iliary Building, Turbine Building, and Ser ice Building. A brie description, including unction and location o each type ent, is presented below.

ASE US WASTE SYSTEMS 11.3-7

WATTS BAR Shield uilding ent Waste gases rom containment purge and the waste gas decay tan s are discharged to the en ironment 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 appro imately 130 eet abo e ground le el. The location o the Reactor Building ents is shown in the e uipment 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 e cept containment purge air e haust monitor discharges are passed through HEPA ilters and charcoal adsorbers prior to release. The e luent 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 e hausted through the ent rom the waste gas decay tan s is shown in Figure 11.3-1.

Au iliary uilding ent Waste gases in the Au iliary Building are discharged through the Au iliary Building e haust ent. In addition, containment atmosphere is continuously ented, during normal operation or pressure control, into the annulus a ter it is iltered through HEPA and charcoal ilters, and subse uently, discharged into the Au iliary Building e haust ent. The ent is o the chimney type ha ing a rectangular cross section o 10 by 30 eet. The top o the ent is located atop the Au iliary Building and discharges appro imately 106 eet abo e grade. Under normal operating conditions, gases are continuously discharged through the ent. E luent low rates can be near 224,000 c m when two Au iliary Building general e haust ans and one uel-handling area e haust an are operating at ull capacity. Under accident conditions, the Au iliary Building is isolated, and the Au iliary Building gas treatment system (ABGTS) is used to treat gaseous e luents. When in ser ice, the ABGTS discharges to the Shield Building e haust ent. The location o the Au iliary Building e haust ent is shown in the e uipment layout diagram, Figure 1.2-1. The Au iliary Building is shown on the main plant general plan, Figure 2.1-5.

Turbine uilding ents Gaseous wastes rom the condenser are discharged through the condenser acuum e haust ent. The ent, which is a 12-inch diameter pipe, discharges at appro imately the 760- oot le el. Under normal operating conditions the discharge low rate will typically be less than 45 c m.

Non-radioacti e entilation air is e hausted rom the Turbine Building through the Turbine Building ents. There are eighteen ents at the 755- oot le el and twenty ents at the 824- oot le el (roo le el). The e luent low rates ary or each type o ent.

Generally, the normal low rates through a typical ent at the 755- oot le el is 22,888 c m and the low rates through typical ent at the 824- oot le el is 28,500 c m. 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.

11.3-8 ASE US WASTE SYSTEMS

WATTS BAR Condenser acuum haust ent Gaseous wastes rom the condenser are discharged through the condenser acuum e haust ent. The ent, which is a 12-inch diameter pipe, discharges at appro imately the 760- oot le el. Under normal operating conditions the discharge low rate will typically be less than 45 c m.

Ser ice uilding ent Radiologically monitored potentially radioacti e waste gases rom the radiochemical laboratory and the titration room are e hausted through HEPA ilters ia a common duct which discharges to the common Ser ice Building roo e haust plenum. E haust air rom the general area discharges to the common Ser ice Building roo e haust plenum. Separate ents rom the common roo e haust plenum discharge to atmosphere appro imately 24 eet abo e grade. The Ser ice Building is shown on the site plot plan, Figure 2.1-5.

11.3. Atmos heric Dilution Calculations o atmospheric transport, dispersion, and ground deposition are based on the straight-line air low model discussed in NRC Regulatory Guide 1.111 (Re ision 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 Au iliary Building (AB) ents are treated as ground le el. The computer code titled Gaseous E luent Licensing Code (GELC) was used to per orm routine dose assessments or WBN.

During Unit 1 licensing, terrain ad ustment actors (TAF) were de eloped to account or recirculation e ects due to the ri er alley location o the plant. The ground le el oint re uency distribution ( FD) is gi en in Section 2.3. Air concentrations and deposition rates were calculated considering radioacti e decay and buildup during transit. Plume depletion was calculated using the igures pro ided in Regulatory Guide 1.111.

Table 11.3-8 pro ides the receptor locations or per orming the dose assessments in this chapter. The data was based on the 2007 land use sur ey. The TAF, X/ , and D/ or each receptor were calculated or the locations based on this sur ey. The TAF alues presented in Table 11.3-8 were de eloped 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 de elopment 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 e ist are listed in Table 11.3-8.

11.3.1 stimated Doses from Radionuclides in aseous ffluents Indi iduals are e posed to gaseous e luents ia the ollowing pathways (1) e ternal radiation rom radioacti ity in the air and on the ground (2) inhalation and (3) ingestion o bee , egetables, and mil . No other additional e posure pathway has been identi ied which would contribute 10 or more to either indi idual or population doses.

ASE US WASTE SYSTEMS 11.3-9

WATTS BAR 11.3.1 .1 Assum tions and Calculational ethods E ternal air e posures are e aluated at points o potential ma imum e posure (i.e.,

points at the unrestricted area boundary). E ternal s in and total body e posures are e aluated at nearby residences. The dose to the critical organ rom radioiodines, tritium and particulates is calculated or real pathways e isting at the site during a land use sur ey conducted in 2007.

To e aluate the potential critical organ dose, mil animals and nearest gardens were identi ied by a detailed sur ey within i e miles o the plant (Table 11.3-8). In ormation on grazing seasons and eeding regimes are re lected 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 ta en rom Figure 2.2 in NUREG/CR-4653 GASPAR II - Technical Re erence and User Guide, 1987 that pro ides the growing season across the US. The alue chosen is on the high end or the middle Tennessee Valley. The LUS and publicly a ailable in ormation support that this is a conser ati e eeding actor. Supplemental eed is assumed to be grown in the icinity o Watts Bar and ha e 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 e ceptions as ollows (1) Inhalation doses are based on the a erage indi iduals inhalation rates ound in ICRP Publication 23 o 1,400 5,500 8,000 and 8,100 m3/year or in ant, child, teen, and adult, respecti ely.

(2) The mil ingestion pathway has been modeled to include speci ic in ormation on grazing periods or mil animals obtained rom a detailed arm sur ey. A eeding actor (FF) has been de ined as that raction o total eed inta e 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 radioacti ity in stored eed are ad usted to re lect radioacti e decay during the ma imum assumed storage period o 180 days by the actor 180 1 1 - e p - O i 180 180 ³ exp -Oi t dt = ----------------------------------------

180O i 0

11.3-10 ASE US WASTE SYSTEMS

WATTS BAR This actor replaces the actor e p (-i th) in e uation C-10 o Regulatory Guide 1.109.

(3) The stored egetable and bee ingestion pathways ha e been modeled to re lect more accurately the actual dietary characteristics o indi iduals. For stored egetables the assumption is made that home grown stored egetables are consumed when resh egetables are not a ailable, i.e.,

during the 9 months o all, winter, and spring. Rather than use a constant storage period o 60 days, radioacti e decay is accounted or e plicitly during the 275-day consumption period. The radioacti e decay correction is calculated by 275 1 1 - e p - O i 275 275 ³ e p - O i t dt = ------------------------------------------

275O i 0

This replaces the term e p (-ith) in E uation C-5 o Regulatory Guide 1.109.

(4) The bee consumption pathways can be di ided into either commercial sales or home use pathways. Dose calculations are made or indi iduals consuming meat produced or home use. The normal processing route is or an indi idual to slaughter the bee animal, pac age and reeze the meat, and then consume the meat during the ne t 3-month period. Radioacti e decay is calculated during the 3-month period by 90 1 1 - e p - O i 90 90 ³ e p - O i t dt = --------------------------------------

90 O i 0

The term is multiplied into E uation C-12 in Regulatory Guide 1.109. I the bee animals are sold commercially, then indi iduals would not be e posed ASE US WASTE SYSTEMS 11.3-11

WATTS BAR continuously to meat containing radioacti ity rom the same arm. It is e pected that this pathway will not cause signi icant indi idual e posures.

Population doses were based on U.S. Population distribution o Category Ages (A)* Fraction In ant A 2 0.015 Child 2 A 13 0.167 Teen 13 A 19 0.153 Adult 19 A 0.665

• e.g., someone who is 1 year, 11 months is an in ant, while someone who is e actly two years old is a child.

Tables 11.3-11 and 11.3-12 pro ide the doses estimated or indi iduals 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 pro ected poplulation distribution or the year 2040 is gi en in Table 11.3-9.

Vegetable in estion is the critical pathway.

11.3.1 .2 Summary of Annual Po ulation Doses TVA has estimated the radiological impact to regional 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 bac ground to indi iduals within the United States ranges rom appro imately 100 mrem to 250 mrem per year. The annual total body dose due to bac ground or a population o about 1,500,000 persons e pected to li e within a 50 mile radius o the Watts Bar Nuclear Plant in the year 2040 is calculated to be appro imately 210,000 man-rem assuming 140 mrem/year/indi idual. By comparison, the same population (e cluding onsite radiation wor ers) will recei e a total body dose o appro imately 6.66 man-rem rom e luents. Based on these results, TVA concludes that the normal operation o the Watts Bar Nuclear Plant will present minimal ris to the health and sa ety o the public.

R F R C S None 11.3-12 ASE US WASTE SYSTEMS

WATTS BAR Table 11.3-1 aseous Waste Processing System Com onent Data1 Waste as Com ressors Number 2 Type Water Sealed Centri ugal Design low rate, N2 40 (at 140(F, 2 psig) c m Design pressure, psig 150 Design temperature, (F 180 Normal operating pressure, psig Suction 2.0 - 3.5 Discharge 0 - 100 Normal operating temperature, (F 70 - 130 as Decay Tan s Number 9 Volume, each, t3 600 Design pressure, psig 150 Design temperature, (F 180 Normal operating pressure, psig 0 - 110 Normal operating temperatures, (F 50 - 140 Material o construction Carbon steel Type Vertical Cylindrical Sequential Automatic as Analy er O ygen Electrochemical Sensor o the Polargraphic Type, 0 - 20 O2 Hydrogen2 By Thermal Conducti ity, 0 - 100 H2 Automatic stepping switch 8 steps Recorded Readout 8 points Temperature, (F 120 Number (Shared) 1

1. For design codes and sa ety classes, see Section 3.2.

2. Hydrogen is uanti ied to determine i it e ceeds lower lammability limit.

ASE US WASTE SYSTEMS 11.3-13

WATTS BAR Table 11.3-2 D Airborne Radioacti e oble as Releases For 1 3 From Westinghouse Designed O erating Reactors Plant Total Released Curies

1. Yan ee Rowe 3.5 101

2. Connecticut Yan ee (Haddam Nec ) 3.2 101

3. San Ono re 1.1 104

4. R. E. Ginna 5.76 102

5. H. B. Robinson 3.1 103

6. Point Beach Units 1 and 2 5.75 103 11.3-14 ASE US WASTE SYSTEMS

WATTS BAR Table 11.3-3 ases Used n Calculating ected System Acti ities and Releases From The WPS A. P CT D S ST ACT T

1. The ma or inputs to the gas system during normal operation are ents on the CVCS Holdup Tan s (HUT) and Reactor Coolant Drain Tan s (RCDT). Inputs rom the gas analyzer sampling system and CVCS olume control tan are assumed to be negligible.

2. Reactor coolant gaseous acti ities are based on NUREG-0017 as modi ied to re lect Watts Bar plant parameters.

3. Twenty- i e percent o dissol ed radiogases in the reactor coolant entering the RCDT s and HUT s lea e solution and enter the apor space.

4. Radioacti e decay was assumed while the CVCS HUT, RCDT s and gas decay tan s were illing. No additional decay was assumed in the e aporator.

5. The CVCS HUT is assumed to be illed to 80 capacity be ore processing by the waste disposal system. The RCDT s are assumed to be illed to 300 gallons be ore draining.

6. Values or li uid low rates to the tan s were based on estimates o annual a erage lows.

CVCS HUT low 4 gpm (2 gpm per unit)

RCDT low 300 gpd (per each unit)

7. Plant capacity actor 0.8

8. Iodine partition coe icient in the RCDT s and CVCS HUT was 7.5 10-3 Ci/cc in apor (Based on NUREG-0017)

Ci/cc in li uid

9. Hydrogen concentration in the primary coolant was assumed 35 cc/ g.

. A UAL R L AS S Per NUREG-0017, the ollowing assumptions were used in calculating e pected annual releases

1. 173 t3/day (at STP) o reactor coolant o gas is input into the waste gas disposal system.

2. WGDT in entory is assumed to be at RCS coolant concentrations, a ter correcting or standard temperature and pressure (273.2( and 14.7 psia)

3. RCS coolant is at 588.2(F and 2250 psia.

4. GWPS releases are based on a 60 day hold-up time.

5. Particulate releases are ta en rom Table 2-17 o NUREG-0017.

ASE US WASTE SYSTEMS 11.3-15

Table 11.3- Process Parameters And ected Acti ities n aseous Waste System (Concentrations n Ci m) (Sheet 1 of 2) 11.3-16 Pressu Flo re Tem . Rate (PS ) ((F) (cc day) R 3 R 5 R 5 R R R 131 133 133 135

1. Unit 1 RCDT Vent 1.5 170 ma . 1.14(+6) 0.0E+06 1.5E-03 3.2E-02 1.4E-02 1.3E-02 0.0E+00 7.3E-02 3.9E-04 2.9E-01 7.5E-04 WATTS BAR

2. Unit 2 RCDT Vent 1.5 170 ma . 1.14(+6) 0.0E+06 1.5E-03 3.2E-02 1.4E-02 1.3E-02 0.0E+00 7.3E-02 3.9E-04 2.9E-01 7.5E-04

3. Sampling System VCT Vent Unit 1 1.5 115 0 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00

4. Sampling System VCT Vent Unit 2 1.5 115 0 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00

5. CVCS HUT Vent - - 2.18(+7) 0.0E+00 9.0E-05 2.9E-02 2.3E-03 1.0E-03 0.0E+00 5.6E-02 2.4E-05 1.7E-01 4.6E-05

6. Gas Analyzer - - 0 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00

7. Waste Disposal System SRST Vent - - 0 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00

8. CVCS VCT Vent Unit 1 1.5 115 0 0.0E+00 4.1E-01 3.5E+00 1.4E-01 5.3E-01 0.0E+00 5.3E-00 4.8E-01 2.0E+01 2.5E-02

9. CVCS VCT Vent Unit 2 1.5 115 0 0.0E+00 4.1E-01 3.5E+00 1.4E-01 5.3E-01 0.0E+00 5.3E-00 4.8E-01 2.0E+01 2.5E-02

10. Combination o Normal 1/p to WPS(G) 1.5 VAR 2.48(+7) 0.0E+00 3.9E-04 2.0E-01 8.5E-03 4.2E-03 0.0E+00 3.3E-01 1.0E-04 8.8E-01 2.0E-04

11. Compressor Recirculation Line 1.5 140 0 0.0E+00 3.9E-04 2.0E-01 8.5E-03 4.2E-03 0.0E+00 3.3E-01 1.0E-04 8.8E-01 2.0E-04

12. Compressor Inlet 3.5 VAR 2.48(+7) 0.0E+00 3.9E-04 2.0E-01 8.5E-03 4.2E-03 0.0E+00 3.3E-01 1.0E-04 8.8E-01 2.0E-04

13. Compressor Inlet 2.0 VAR 2.48(+7) 0.0E+00 3.9E-04 2.0E-01 8.5E-03 4.2E-03 0.0E+00 3.3E-01 1.0E-04 8.8E-01 2.0E-04

14. Downstream o Compressor 100 140 2.48(+7) 0.0E+00 1.8E-03 9.6E-01 4.0E-02 2.0E-02 0.0E+00 1.6E+00 4.8E-04 4.1E+00 1.0E-03

15. Compressor Outlet to GDT s - - 0 0.0E+00 1.8E-03 9.6E-01 4.0E-02 2.0E-02 0.0E-02 1.6E+00 4.8E-04 4.1E+00 1.0E-03

16. Inlets to Filling GDT s 100 140 2.48(+7) 0.0E+00 1.8E-03 9.6E-01 4.0E-02 2.0E-02 0.0E-02 1.6E+00 4.8E-04 4.1E+00 1.0E-03

17. Line to GDT Header 100 AMB VAR 0.0E+00 1.0E-05 9.6E-01 6.0E-0 6.5E-04 0.0E+00 1.4E+00 1.5E-06 3.1E+00 3.0E-06

18. Discharge Line 20 AMB VAR 0.0E+00 0.0E+00 4.6E-01 0.0E+00 0.0E+00 0.0E+00 2.1E-02 0.0E+00 5.6E-04 0.0E+00

19. Discharge Line 1 AMB VAR 0.0E+00 0.0E+00 4.6E-01 0.0E+00 0.0E+00 0.0E+00 2.1E-02 0.0E+00 5.6E-04 0.0E+00

20. Gas Analyzer 2 AMB 0 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00

21. From GDT s to Compressor Inlet 100 AMB 2.48(+7) 0.0E+00 1.0E-05 9.6E-01 6.0E-03 6.5E-04 0.0E+00 1.4E+00 1.5E-06 3.1E+00 3.0E-06

22. From GDT s to BRS HT s 3 AMB 2.48(+7) 0.0E+00 1.0E-05 9.6E-01 6.0E-03 6.5E-04 0.0E+00 1.4E+00 1.5E-06 3.1E+00 3.0E-06 ASE US WASTE SYSTEMS

Table 11.3- PROC SS PARA T RS A D P CT D ACT T S AS OUS WAST S ST (CO C TRAT O S Ci gm) (Sheet 2 of 2)

Pressur Flo e Tem . Rate (PS ) ((F) (cc day) 135 13 13 13 131 132 133 13 135

1. Unit 1 RCDT Vent 1.5 170 ma . 1.14(+6) 7.0E-02 5.0E-05 7.5E-04 0.0E+00 3.4E-04 3.8E-04 8.9E-04 2.7E-04 1.0E-03

2. Unit 2 RCDT Vent 1.5 170 ma . 1.14(+6) 7.0E-02 5.0E-05 7.5E-04 0.0E+00 3.4E-04 3.8E-04 8.9E-04 2.7E-04 1.0E-03 WATTS BAR

3. Sampling System VCT Vent Unit 1 1.5 115 0 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 ASE US WASTE SYSTEMS

4. Sampling System VCT Vent Unit 2 1.5 115 0 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00

5. CVCS HUT Vent - - 2.18(+7) 9.7E-03 3.0E-06 4.7E-05 0.0E+00 2.4E-05 2.8E-06 1.7E-05 1.8E-06 1.0E-05

6. Gas Analyzer - - 0 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00

7. Waste Disposal System SRST Vent - - 0 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00

8. CVCS VCT Vent Unit 1 1.5 115 0 3.2E+00 1.7E-03 2.5E-02 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00

9. CVCS VCT Vent Unit 2 1.5 115 0 3.2E+00 1.7E-03 2.5E-02 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00

10. Combination o Normal 1/p to WPS(G) 1.5 VAR 2.48(+7) 3.9E-02 1.3E-05 2.0E-04 0.0E+00 5.3E-05 3.8E-05 4.6E-05 2.5E-05 1.0E-04

11. Compressor Recirculation Line 1.5 140 0 3.5E-02 1.3E-05 2.0E-04 0.0E+00 5.3E-05 3.8E-05 9.6E-05 2.5E-05 1.0E-04

12. Compressor Inlet 3.5 VAR 2.48(+7) 3.5E-02 1.3E-05 2.0E-04 0.0E+00 5.3E-05 3.8E-05 9.6E-05 2.5E-05 1.0E-04

13. Compressor Inlet 2.0 VAR 2.48(+7) 3.5E-02 1.3E-05 2.0E-04 0.0E+00 5.3E-05 3.8E-05 9.6E-05 2.5E-05 1.0E-04

14. Downstream o Compressor 100 140 2.48(+7) 1.7E-01 6.1E-05 9.6E-04 0.0E+00 2.6E-04 1.8E-04 4.4E-04 1.2E-04 4.9E-04

15. Compressor Outlet to GDT s - - 0 1.7E-01 6.1E-05 9.6E-04 0.0E+00 2.6E-04 1.8E-04 4.4E-04 1.2E-04 4.9E-04

16. Inlet to Filling GDT s 100 140 2.48(+7) 1.7E-01 6.1E-05 9.6E-04 0.0E+00 2.6E-04 1.8E-04 4.4E-04 1.2E-04 4.9E-04

17. Line to GDT Header 100 AMB VAR 1.8E-02 3.1E-08 3.1E-06 0.0E+00 2.0E-04 4.8E-06 1.1E-04 1.3E-06 3.9E-05

18. Discharge Line 20 AMB VAR 0.0E+00 0.0E+00 0.0E+00 0.0E+00 6.0E-07 0.0E+00 0.0E+00 0.0E+00 0.0E+00

19. Discharge Line 1 AMB VAR 0.0E+00 0.0E+00 0.0E+00 0.0E+00 6.0E-07 0.0E+00 0.0E+00 0.0E+00 0.0E+00

20. Gas Analyzer 2 AMB 0 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00 0.0E+00

21. From GDT s to Compressor Inlet 100 AMB 2.48(+7) 1.8E-03 3.1E-08 3.1E-06 0.0E+00 2.0E-04 4.8E-06 1.1E-04 1.3E-06 3.9E-05

22. From GDT s to BRS HT s 3 AMB 2.48(+7) 1.8E-02 3.1E-08 3.1E-06 0.0E+06 2.0E-04 4.8E-06 1.1E-04 1.3E-06 3.9E-05 11.3-17

WATTS BAR Table 11.3-5 ected Annual aseous Releases From The WPS - Per Reactor Unit GWPS Gas release (Ci/Yr) r-85m 0.00E+00 r-85 4.63E+00 r-87 0.00E+00 r-88 0.00E+00 Xe-131M 3.52E-01 Xe-133M 1.14E-08 Xe-133 1.72E-02 Xe-135M 0.00E+00 Xe-135 6.01E-47 Xe-137 0.00E+00 Xe-138 0.00E+00 Ar-41 0.00E+00 Br-84 0.00E+00 I-131 1.44E-03 I-132 0.00E+00 I-133 1.16E-21 I-134 0.00E+00 I-135 4.08E-66 H-3 0.00E+00 Cr-51 1.40E-07 Mn-54 2.10E-08 Co-57 0.00E+00 Co-58 8.70E-08 Co-60 1.40E-07 Fe-59 1.80E-08 Sr-89 4.40E-07 Sr-90 1.70E-07 Zr-95 4.80E-08 Nb-95 3.70E-08 Ru-103 3.20E-08 Ru-106 2.70E-08 Sb-125 0.00E+00 Cs-134 3.30E-07 Cs-136 5.30E-08 Cs-137 7.70E-07 Ba-140 2.30E-07 Ce-141 2.20E-08 C-14 1.20E+00 11.3-18 ASE US WASTE SYSTEMS

WATTS BAR Table 11.3- Radioacti e 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 Core based on 3480 MWt)

2. Primary and secondary side coolant and steam acti ities are based on ANSI N18.1 and ha e been plant ad usted or WBN speci ic parameters.

3. RCS water parameters Volume = 11,375 t3 Press. = 2250 psia Temp. = 588.2 F Spec. Vol. = 0.02265 t3/lb

4. Containment releases are iltered through a HEPA and charcoal ilter with minimum iltration e iciencies o 99 and 70 , respecti ely.

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 airborne atmosphere.

6. WGDT releases are based on a 173 t3/day ( STP) input o RCS coolant o gas to the waste gas disposal system and a WGDT holdup time o 60 days.

7. Au iliary Building (AB) entilation noble gas source terms are based on a 160 lb/day release o RCS coolant acti ity 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. Re ueling Area iodine releases are based on 0.16 Ci/yr per Ci/gm o RCS or 300 days and 0.3 Ci/yr per Ci/gm or 65 days.

10. Turbine Building (TB) entilation noble gas source 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 300 days and 1400 Ci/yr per Ci/gm or 65 days.

12. Condenser acuum e haust noble gas source terms are based on a steam lowrate to the condenser o 8.5E6 lb/hr at secondary steam acti ities.

13. Condenser acuum e haust iodine source terms are based on a 3500 Ci/yr per Ci/gm o secondary steam released to the condenser acuum e haust.

14. Steam generator blowdown lash tan source terms are based on a ma imum steam generator blowdown low o 12.5 gpm/steam generator. Iodines are urther reduced in the o gases 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 the 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 a ailable or release ia gaseous pathways.

17. Total particulate releases are ta en directly rom Table 2-17 o NUREG-0017. Since these alues are prior to treatment, the releases rom the Containment Building either through the purge air, or containment ent ilters, are reduced by applying a HEPA iltration actor o 0.01 (99 e iciency).

ASE US WASTE SYSTEMS 11.3-19

WATTS BAR Table 11.3- Radioacti e aseous ffluent Parameters (Page 2 of 2)

18. 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 (e iciency o 99 ) and charcoal (e iciency 70 ) ilter prior to release.

20. A continuous iltered containment ent o 100 c m is the e pected normal release and is e aluated.

A separate e aluation assuming one purge e ery two wee s will be per ormed. NUREG-0017 suggests 22 containment purges a year during power operation, and 2 purges during re ueling.

11.3-20 ASE US WASTE SYSTEMS

WATTS BAR Table 11.3- Annual Radioacti e Releases With Purge Air Filters (Curies ear Reactor)

Table based on operation o one unit.

Contain.(1) Au . Turbine Total Nuclide Building Building Building r-85m 2.00E+01 4.53E+00 1.23E+00 2.58E+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 1.62E+01 r-88 2.84E+01 7.95E+00 2.13E+00 3.85E+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 4.88E+01 Xe-133 3.12E+03 6.70E+01 1.77E+01 3.20E+03 Xe-135m 3.86E+00 3.68E+00 9.80E-01 8.52E+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 3.33E+00 3.42E+00 9.06E-01 7.66E+00 Ar-41 3.40E+01 0.00E+00 0.00E+00 3.40E+01 Br-84 6.00E-05 5.02E-02 4.81E-04 5.07E-02 I-131 7.29E-03 1.39E-01 7.08E-03 1.53E-01 I-132 1.61E-03 6.56E-01 1.70E-02 6.75E-01 I-133 3.55E-03 4.35E-01 2.03E-02 4.58E-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 8.45E-01 H-3 1.39E+02 0.00E+00 0.00E+00 1.39E+02 H-3 (TPC)(3)

Unit 1 Only 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 Ru-103 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 3.95E-05 C-14 2.80E+00 4.50E+00 0.00E+00 7.30E+00 (1) Includes release rom GWPS (2) 4.28E+02 = 4.28 X 102 (3) Tritium alues or a Tritim Production Core ASE US WASTE SYSTEMS 11.3-21

WATTS BAR Table 11.3- a Design (For 1 Failed Fuel) ected as Release Concentration ( ffluent Concentration Limit) With Containment Purge (Sheet 1 of 2)

Single Unit Dual Unit E p. Rel. Design Design 10CFR20 O eration O eration (Ci/yr) Des/E p (Ci/yr) (Ci/cc) (ECL) C/ECL C/ECL r-85m 2.58E+01 12.28 3.17E+02 1.10E-10 1.0E-07 0.0010951 0.0021902 r-85 6.99E+02 33.08 2.31E+04 7.99E-09 7.0E-07 0.0114124 0.0228248 r-87 1.62E+01 7.45 1.21E+02 4.18E-11 2.0E-08 0.0020906 0.0041812 r-88 3.85E+01 12.33 4.75E+02 1.64E-10 9.0E-09 0.0182306 0.0364612 Xe-131m 1.19E+03 2.91 3.45E+03 1.19E-09 2.0E-06 0.0005971 0.0011942 Xe-133m 4.88E+01 43.24 2.11E+03 7.29E-10 6.0E-07 0.0012142 0.0024284 Xe-133 3.20E+03 111.07 3.55E+05 1.23E-07 5.0E-07 0.2456675 0.4913350 Xe-135m 8.52E+00 5.04 4.29E+01 1.48E-11 4.0E-08 0.0003710 0.0007420 Xe-135 1.85E+02 6.97 1.29E+03 4.46E-10 7.0E-08 0.006375 0.012750 Xe-138 7.66E+00 5.43 4.16E+01 1.44E-11 2.0E-08 0.0007188 0.0014376 Br-84 5.07E-02 2.50 1.27E-01 4.38E-14 8.0E-08 5.478E-07 1.096E-06 I-131 1.53E-01 52.41 8.03E+00 2.77E-12 2.0E-10 0.013875 0.027750 I-132 6.75E-01 4.00 2.70E+00 9.33E-13 2.0E-08 4.67E-05 0.0000934 I-133 4.58E-01 26.85 1.23E+01 4.25E-12 1.0E-09 0.0042535 0.0085070 I-134 1.08E+00 1.65 1.78E+00 6.14E-13 6.0E-08 1.023E-05 2.046E-05 I-135 8.45E-01 7.91 6.69E+00 2.31E-12 6.0E-09 0.0003851 0.0007702 Cs-134 2.27E-03 40.60 9.20E-02 3.18E-14 2.0E-10 0.0001589 0.0003178 Cs-136 8.01E-05 165.20 1.32E-02 4.57E-15 9.0E-10 5.079E-06 1.016E-05 Cs-137 3.48E-03 153.22 5.33E-01 1.84E-13 2.0E-10 0.0009203 0.0018406 Cr-51 5.92E-04 0.29 1.73E-04 5.96E-17 3.0E-08 1.988E-09 3.976E-09 Mn-54 4.31E-04 0.47 2.03E-04 7.01E-17 1.0E-09 7.005E-08 1.401E-07 Fe-59 7.70E-05 3.48 2.68E-04 9.27E-17 5.0E-10 1.853E-07 3.706E-07 Co-58 2.32E-02 5.37 1.24E-01 4.30E-14 1.0E-09 4.298E-05 8.596E-05 Co-60 8.74E-03 1.38 1.21E-02 4.17E-15 5.0E-11 8.333E-05 1.667E-04 Sr-89 2.98E-03 22.45 6.69E-02 2.31E-14 1.0E-09 2.313E-05 4.626E-05 Sr-90 1.14E-03 13.49 1.54E-02 5.33E-15 6.0E-12 0.0008877 0.0017754 Zr-95 1.00E-03 1.71 1.71E-03 5.92E-16 4.0E-10 1.481E-06 2.962E-06 Nb-95 2.45E-03 2.34 5.73E-03 1.98E-15 2.0E-09 9.895E-07 1.979E-06 Ba-140 4.00E-04 0.31 1.26E-04 4.34E-17 2.0E-09 2.171E-08 4.342E-08 H-3 1.39E+02 1 1.39E+02 4.80E-11 1.0E-07 0.0004811 0.0009622 H-3 (TPC) 3.70E+02 1 3.70E+02 1.28E-10 1.0E-07 0.0012775 0.0012775 1 rod 1.53E+03 1 1.53E+03 5.29E-10 1.0E-07 0.0052869 0.0052869 2 rod 2.69E+03 1 2.69E+03 9.30E-10 1.0E-07 0.0092962 0.0092962 C-14 7.30E+00 1 7.30E+00 2.52E-12 3.0E-09 0.000841 0.001682 Ar-41 3.40E+01 1 3.40E+01 1.18E-11 1.0E-08 0.0011752 0.0023504 Total 0.3109694 0.6219388 Total (TPC) 0.3117657 0.6227352 1 rod 0.3157751 0.6267446 2 rod 0.3197845 0.6307539 11.3-22 ASE US WASTE SYSTEMS

WATTS BAR Table 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 abo e calculation considers dual unit operation.

Based on the e aluation done or Re ision 7, the per unit concentrations are the same or both units. There ore, the last column is twice the preceeding column e cept in the case o TPC.

Note Dual unit operation considers only Unit 1 with TPC.

ASE US WASTE SYSTEMS 11.3-23

WATTS BAR Table 11.3- b Design (For 1 Failed Fuel) ected as Release Concentration ( ffluent Concentration Limit) With Continuous Filtered Containment ent (Sheet 1 of 2)

Single Unit Dual Unit E p. Rel. Design Design 10CFR20 O eration O eration (Ci/yr) Des/E p (Ci/yr) (Ci/cc) (ECL) C/ECL C/ECL r-85m 9.48E+00 12.28 1.16E+02 4.02E-11 1.0E-07 0.0004024 0.0008048 r-85 6.78E+02 33.08 2.24E+04 7.75E-09 7.0E-07 0.0110743 0.0221486 r-87 5.81E+00 7.45 4.33E+01 1.50E-11 2.0E-08 0.0007480 0.0014960 r-88 1.32E+01 12.33 1.63E+02 5.63E-11 9.0E-09 0.0062505 0.0125010 Xe-131m 1.09E+03 2.91 3.18E+03 1.10E-09 2.0E-06 0.0005489 0.0010978 Xe-133m 4.31E+01 43.24 1.86E+03 6.44E-10 6.0E-07 0.0010735 0.0021470 Xe-133 2.90E+03 111.07 3.22E+05 1.11E-07 5.0E-07 0.2227110 0.4454220 Xe-135m 4.68E+00 5.04 2.36E+01 8.15E-12 4.0E-08 0.0002038 0.0004076 Xe-135 8.88E+01 6.97 6.19E+02 2.14E-10 7.0E-08 0.0030561 0.0061122 Xe-138 4.34E+00 5.43 2.36E+01 8.15E-12 2.0E-08 0.0004073 0.0008146 Br-84 5.07E-02 2.50 1.27E-01 4.38E-14 8.0E-08 0.0000005 0.0000010 I-131 1.53E-01 52.41 8.00E+00 2.77E-12 2.0E-10 0.0138277 0.0276554 I-132 6.73E-01 4.00 2.69E+00 9.30E-13 2.0E-08 0.0000465 0.0000930 I-133 4.57E-01 26.85 1.23E+01 4.24E-12 1.0E-09 0.0042433 0.0084866 I-134 1.07E+00 1.65 1.77E+00 6.10E-13 6.0E-08 0.0000102 0.0000204 I-135 8.42E-01 7.91 6.66E+00 2.30E-12 6.0E-09 0.0003837 0.0007674 Cs-134 2.27E-03 40.60 9.20E-02 3.18E-14 2.0E-10 0.0001589 0.0003178 Cs-136 8.01E-05 165.20 1.32E-02 4.57E-15 9.0E-10 0.0000051 0.0000102 Cs-137 3.48E-03 153.22 5.33E-01 1.84E-13 2.0E-10 0.0009203 0.0018406 Cr-51 5.92E-04 0.29 1.73E-04 5.96E-17 3.0E-08 0.0000000 0.0000000 Mn-54 4.31E-04 0.47 2.03E-04 7.01E-17 1.0E-09 0.0000001 0.0000002 Fe-59 7.70E-05 3.48 2.68E-04 9.27E-17 5.0E-10 0.0000002 0.0000004 Co-58 2.32E-02 5.37 1.24E-01 4.30E-14 1.0E-09 0.0000430 0.0000860 Co-60 8.74E-03 1.38 1.21E-02 4.17E-15 5.0E-11 0.0000833 0.0001666 Sr-89 2.98E-03 22.45 6.69E-02 2.31E-14 1.0E-09 0.0000231 0.0000462 Sr-90 1.14E-03 13.49 1.54E-02 5.33E-15 6.0E-12 0.0008877 0.0017754 Zr-95 1.00E-03 1.71 1.71E-03 5.92E-16 4.0E-10 0.0000015 0.0000030 Nb-95 2.45E-03 2.34 5.73E-03 1.98E-15 2.0E-09 0.0000010 0.0000020 Ba-140 4.00E-04 0.31 1.26E-04 4.34E-17 2.0E-09 0.0000000 0.0000000 H-3 1.39E+02 1 1.39E+02 4.80E-11 1.0E-07 0.0004811 0.0009622 H-3 (TPC) 3.70E+02 1 3.70E+02 1.28E-10 1.0E-07 0.0012775 0.0012775 1 rod 1.53E+03 1 1.53E+03 5.29E-10 1.0E-07 0.0052869 0.0052869 2 rod 2.69E+03 1 2.69E+03 9.30E-10 1.0E-07 0.0092962 0.0092962 C-14 7.30E+00 1 7.30E+00 2.52E-12 3.0E-09 0.0008410 0.0016820 Ar-41 3.40E+01 1 3.40E+01 1.18E-11 1.0E-08 0.0011752 0.0023504 Total 0.2696131 0.5392262 Total (TPC) 0.2704095 0.5400226 1 rod 0.2744189 0.5440320 2 rod 0.2784283 0.5480413 11.3-24 ASE US WASTE SYSTEMS

WATTS BAR Table 11.3- b Design (For 1 Failed Fuel) ected as Release Concentration ( ffluent Concentration Limit) With Continuous Filtered Containment ent (Sheet 2 of 2)

Note The Dual Unit Operation column in the abo e calculation considers dual unit operation.

Based on the e aluation done or Re ision 7, the per unit concentrations are the same or both units. There ore, the last column is twice the preceeding column e cept in the case o TPC.

Note Dual unit operation considers only Unit 1 with TPC.

ASE US WASTE SYSTEMS 11.3-25

WATTS BAR Table 11.3- c Total Releases (based on A S 1 .1-1 in Ci yr), ith Continuous Filtered Containment ent (Sheet 1 of 1)

Table based on operation o one unit Contain.(1) Au . Turbine Total Nuclide Building Building Building r-85m 3.72E+00 4.53E+00 1.23E+00 9.48E+00 r-85 6.69E+02 7.05E+00 1.86E+00 6.78E+02 r-87 4.48E-01 4.27E+00 1.09E+00 5.81E+00 r-88 3.10E+00 7.95E+00 2.13E+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-41 3.40E+01 0.00E+00 0.00E+00 3.40E+01 Br-84 8.16E-07 5.02E-02 4.81E-04 5.07E-02 I-131 6.74E-03 1.39E-01 7.08E-03 1.53E-01 I-132 1.36E-04 6.56E-01 1.70E-02 6.73E-01 I-133 2.36E-03 4.35E-01 2.03E-02 4.57E-01 I-134 4.26E-05 1.06E+00 1.47E-02 1.07E+00 I-135 8.80E-04 8.10E-01 3.13E-02 8.42E-01 H-3 1.39E+02 0.00E+00 0.00E+00 1.39E+02 Cr-51 9.21E-05 5.00E-04 .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 Ru-103 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 3.95E-05 C-14 2.80E+00 4.50E+00 0.00E+00 7.30E+00 11.3-26 ASE US WASTE SYSTEMS

WATTS BAR Table 11.3- Data On Points Of nterest ear Watts ar uclear Plant (Page 1 of 2)

Chi-o er- D-o er- Terrain il Distance (s m 3) (1 m 2) Ad ustment Feeding Sector ( eters) Factor Factor Unrestricted Area Boundary N 1550 5.12e-06 8.13e-09 1.70 Unrestricted Area Boundary NNE 1980 6.35e-06 1.23e-08 1.80 Unrestricted Area Boundary NE 1580 1.05e-05 1.10e-08 2.10 Unrestricted Area Boundary ENE 1370 1.23e-05 8.77e-09 1.70 Unrestricted Area Boundary E 1280 1.37e-05 9.66e-09 1.60 Unrestricted Area Boundary ESE 1250 1.43e-05 1.16e-08 1.80 Unrestricted Area Boundary SE 1250 1.11e-05 9.49e-09 1.50 Unrestricted Area Boundary SSE 1250 6.04e-06 8.21e-09 1.50 Unrestricted Area Boundary S 1340 5.33e-06 1.17e-08 1.90 Unrestricted Area Boundary SSW 1550 4.14e-06 1.05e-08 2.00 Unrestricted Area Boundary SW 1670 4.46e-06 7.34e-09 2.10 Unrestricted Area Boundary WSW 1430 5.47e-06 6.37e-09 1.80 Unrestricted Area Boundary W 1460 2.11e-06 2.07e-09 1.20 Unrestricted Area Boundary WNW 1400 2.49e-06 2.38e-09 2.50 Unrestricted Area Boundary NW 1400 2.05e-06 2.13e-09 1.70 Unrestricted Area Boundary NNW 1460 2.68e-06 3.08e-09 1.60 Nearest Resident N 2134 2.84e-06 4.21e-09 1.50 Nearest Resident NNE 3600 2.69e-06 4.41e-09 1.80 Nearest Resident NE 3353 3.84e-06 3.22e-09 2.20 Nearest Resident ENE 2414 6.26e-06 3.83e-09 1.90 Nearest Resident E 3268 3.97e-06 2.14e-09 1.70 Nearest Resident ESE 4416 2.64e-06 1.46e-09 1.90 Nearest Resident SE 1372 9.66e-06 8.16e-09 1.50 Nearest Resident SSE 1524 4.18e-06 5.56e-09 1.40 Nearest Resident S 1585 3.91e-06 8.42e-09 1.80 Nearest Resident SSW 1979 2.76e-06 6.64e-09 1.90 Nearest Resident SW 4230 1.15e-06 1.43e-09 2.00 Nearest Resident WSW 1829 3.61e-06 4.03e-09 1.70 Nearest Resident W 2896 7.30e-07 6.01e-10 1.10 Nearest Resident WNW 1646 2.26e-06 2.12e-09 2.90 Nearest Resident NW 2061 1.03e-06 9.95e-10 1.50 Nearest Resident NNW 4389 3.50e-07 2.97e-10 1.00 Nearest Garden N 7664 3.13e-07 3.00e-10 1.00 Nearest Garden NNE 6173 1.06e-06 1.42e-09 1.50 Nearest Garden NE 3353 3.84e-06 3.22e-09 2.20 Nearest Garden ENE 4927 2.01e-06 9.39e-10 1.60 Nearest Garden E 6372 1.35e-06 5.42e-10 1.40 Nearest Garden ESE 4758 2.26e-06 1.21e-09 1.80 Nearest Garden SE 4633 1.58e-06 8.97e-10 1.30 Nearest Garden SSE 7454 3.73e-07 2.80e-10 1.10 Nearest Garden S 2254 2.50e-06 4.94e-09 1.90 ASE US WASTE SYSTEMS 11.3-27

WATTS BAR Table 11.3- Data On Points Of nterest ear Watts ar uclear Plant (Page 2 of 2)

Chi-o er- D-o er- Terrain il Distance (s m 3) (1 m 2) Ad ustment Feeding Sector ( eters) Factor Factor Nearest Garden SSW 1979 2.76e-06 6.64e-09 1.90 Nearest Garden SW 8100 4.28e-07 4.03e-10 1.80 Nearest Garden WSW 4667 8.70e-07 7.11e-10 1.50 Nearest Garden W 5120 3.03e-07 2.03e-10 1.00 Nearest Garden WNW 5909 1.72e-07 1.05e-10 1.30 Nearest Garden NW 3170 4.13e-06 3.50e-10 1.10 Nearest Garden NNW 4602 3.28e-07 2.74e-10 1.00 Mil Cow ESE 6706 1.35e-06 6.18e-10 1.70 0.65 Mil Cow SSW 2286 2.24e-06 5.20e-09 1.90 0.65 Mil Cow SSW 3353 1.36e-06 2.84e-09 2.00 0.65 11.3-28 ASE US WASTE SYSTEMS

WATTS BAR Table 11.3- Pro ected 2 Po ulation Distribution Within 5 iles Of Watts ar uclear Plant Po ulation 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 NNW 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 3,063 44,013 105,990 ESE 135 6,230 2,120 5,068 3,280 34,833 SE 203 19,852 1,185 3,950 4,822 44,012 SSE 782 8,951 1,907 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 14,449 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 ASE US WASTE SYSTEMS 11.3-29

WATTS BAR Table 11.3-1 Watts ar uclear Plant- ndi idual Doses From aseous ffluents (For 1 Unit ithout TPC)

E luent Pathway Guideline* Location Dose Noble Gases  Air dose 10 mrad Ma imum E posed 0.801 mrad/yr Indi idual1

 Air dose 20 mrad Ma imum E posed 2.710 mrad/yr Indi idual1 Total body 5 mrem Ma imum Residence2,3 0.571 mrem/yr S in 15 mrem Ma imum Residence2,3 1.540 mrem/yr Iodines/ Bone 15 mrem Ma imum Real 9.15 mrem/yr Particulates (critical organ) Pathway4 rea do n of odine Particulate Doses (mrem yr)

Total Vegetable Ingestion 6.57 Inhalation 0.0704 Ground Contamination 0.0947 Submersion 0.130 Bee Ingestion5 2.28 Total 9.145 mrem/yr Guidelines are de ined in Appendi I to 10 CFR Part 50.

1 Ma imum e posure point is at 1250 meters in the ESE sector.

2 Dose rom air submersion.

3 Ma imum e posed residence is at 1372 meters in the SE sector.

4 Ma imum e posed indi idual is a child at 1979 meters in the SSW sector.

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

11.3-30 ASE US WASTE SYSTEMS

WATTS BAR Table 11.3-11 Summary Of Po ulation Doses T RO D In ant Child Teen Adult Total Submersion 1.26e-02 1.41e-01 1.28e-01 5.57e-01 8.38e-01 Ground 2.31e-03 2.59e-02 2.36e-02 1.03e-01 1.54e-01 Inhalation 6.62e-02 1.24e+00 6.64e-01 2.36e+00 4.33e-00 Cow Mil Ingestion 3.22e-01 1.57e+00 6.63e-01 1.25e+00 3.81e+00 Bee Ingestion 0.00e+00 3.17e-01 1.59e-01 8.04e-01 1.28e+00 Vegetable Ingestion 0.00e+00 1.04e+00 4.16e-01 1.09e-01 2.55e+00 Total man-rem 4.04e-01 4.34e+00 2.05e+00 6.17e+00 1.30e+01 TOTAL OD In ant Child Teen Adult Total Submersion 1.26e-02 1.41e-01 1.28e-01 5.57e-01 8.38e-01 Ground 2.31e-03 2.59e-02 2.36e-02 1.03e-01 1.54e-01 Inhalation 3.93e-03 1.05e-01 6.65e-02 2.76e-01 4.52e-01 Cow Mil Ingestion 1.04e-01 5.73e-01 2.17e-01 3.85e-01 1.28e+00 Bee Ingestion 0.00e+00 3.06e-01 1.53e-01 7.74e-01 1.23e+00 Vegetable Ingestion 0.00e+00 1.06e-00 4.40e-01 1.21e+00 2.70e+00 Total man-rem 1.23e-01 2.20e+00 1.03e+00 3.31e+00 6.66e+00 ASE US WASTE SYSTEMS 11.3-31

WATTS BAR THIS PAGE INTENTIONALLY BLAN 11.3-32 ASE US WASTE SYSTEMS

Enclosure 2, 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 Table 3-1 . Rece tors from Actual Land Use Sur ey Results Used for Potential aseous Releases From W Unit 2 Rece tor Rece tor Distance Sector umber Ty e (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 Replace this table 18 Nearest Garden NNE 6173 with information 19 Nearest Garden NE 3829 provided on the 20 Nearest Garden ENE 4831 next page.

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 86 Final Supplemental En ironmental Impact Statement

Completion and Operation o Watts Bar Nuclear Plant Unit 2 Rece tors from Actual Land Use Sur ey Table 3-1 Results Used for Potential aseous Releases From W Unit 2 Rece tor Rece tor Distance Sector umber Ty e (meters)

1. Nearest Resident N 2134

2. Nearest Resident NNE 3600 Place the 3. Nearest Resident NE 3353

4. Nearest Resident ENE 2414 information

5. Nearest Resident E 3268 provided in 6. Nearest Resident ESE 4416 this table into 7. Nearest Resident SE 1372 the table on 8. Nearest Resident SSE 1524 the preceding 9. Nearest Resident S 1585 page. 10. Nearest Resident SSW 1979

11. Nearest Resident SW 4230

12. Nearest Resident WSW 1829

13. Nearest Resident W 2896

14. Nearest Resident WNW 1646

15. Nearest Resident NW 2061

16. Nearest Resident NNW 4389

17. Nearest Garden N 7664

18. Nearest Garden NNE 6173

19. Nearest Garden NE 3353

20. Nearest Garden ENE 4927

21. Nearest Garden E 6372

22. Nearest Garden ESE 4758

23. Nearest Garden SE 4633

24. Nearest Garden SSE 7454

25. Nearest Garden S 2254

26. Nearest Garden SSW 1979

27. Nearest Garden SW 8100

28. Nearest Garden WSW 4667

29. Nearest Garden W 5120

30. Nearest Garden WNW 5909

31. Nearest Garden NW 3170

32. Nearest Garden NNW 4602

33. Mil Cow ESE 6706

34. Mil Cow SSW 2286

35. Mil Cow SSW 3353 86 Final Supplemental En ironmental Impact Statement

Replace this table with information provided Chapter 3 in the table on the next page.

Table 3-2 . W Total Annual aseous Discharge Per O erating Unit (curies year reactor)

Containment Au iliary Turbine Total er uclide uilding uilding uilding Unit r-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 radioacti e gaseous e luents rom WBN is presented in Figure 3-9.

Final Supplemental En ironmental Impact Statement 87

Place the information provided in this Chapter 3 table into the table on the preceding page.

Table 3-2 W Total annual aseous discharge Per O erating Unit (curies year reactor)

Containment Au iliary Turbine uclide Total uilding uilding uilding r-85m 3.72E+00 4.53E+00 1.23E+00 9.48E+00 r-85 6.69E+02 7.05E+00 1.86E+00 6.78E+02 r-87 4.48E-01 4.27E+00 1.09E+00 5.81E+00 r-88 3.10E+00 7.95E+00 2.13E+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-41 3.40E+01 0.00E+00 0.00E+00 3.40E+01 Br-84 8.16E-07 5.02E-02 4.81E-04 5.07E-02 I-131 6.74E-03 1.39E-01 7.08E-03 1.53E-01 I-132 1.36E-04 6.56E-01 1.70E-02 6.73E-01 I-133 2.36E-03 4.35E-01 2.03E-02 4.57E-01 I-134 4.26E-05 1.06E+00 1.47E-02 1.07E+00 I-135 8.80E-04 8.10E-01 3.13E-02 8.42E-01 H-3 1.39E+02 0.00E+00 0.00E+00 1.39E+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 Ru-103 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 3.95E-05 C-14 2.80E+00 4.50E+00 0.00E+00 7.30E+00 A companion igure illustrating the release points or radioacti e gaseous e luents rom WBN is presented in Figure 3-9.

Final Supplemental En ironmental Impact Statement 87

Replace with Chapter 3 "Bone" A tabulation o the resulting calculated gaseous doses to indi iduals per operational unit is gi en in Table 3-21. Replace with Replace 1 Replace with with Table 3-21. W Doses From aseous ffluent For Unit 2 Without Tritium Production for ear 2 2,3 "9.15" ffluent Path ay uideline1 Location Dose Ma imum E posed Noble Gases J Air dose 10 mrad 0.801 mrad/year Indi idual2 Ma imum E posed E Air dose 20 mrad 2.710 mrad/year Indi idual2 Total body 5 mrem Ma imum Residence3,4 0.571 mrem/year Iodines/ S in 10 mrem Ma imum Residence3,4 1.540 mrem/year Particulate Thyroid (critical organ) 15 mrem Ma imum Real Pathway5 2.715 mrem/year Replace with rea do n of odine Particulate Doses (mrem yr) Replace 4

Cow Mil with with Replace with Feeding Factor o 0.65 2.44 6.57 Total Vegetable Inhalation 0.174 Ingestion Ground Contamination 0.0405 0.0704 Replace with Submersion 0.0603 0.0947 Bee Ingestion2 0.00 5

Total 2.7148 0.130 1

2 Guidelines are de ined in Appendi I to 10 CFR Part 50. 2.28 3

Ma imum e posure point is at 1250 meters in the ESE sector.

4 Dose rom air submersion.

Ma imum e posed residence is at 1372 meters in the SE sector.

5 Ma imum e posed indi idual is an in ant at 3353 meters in the SSW sector. 9.145 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 Radioacti e E luent Reports to the NRC) with NRC guidelines gi en in 10 CFR 50 Appendi I are compared in Table 3-22. These guidelines are designed to assure that releases o radioacti e material rom nuclear power reactors to unrestricted areas during normal conditions, including e pected occurrences, are ept as low as practicable.

Replace with Replace with Insert

• 1979 5Maximum dose location for all 1 Replace with 2 receptors is 1250 meters in 3 the ESE sector.

Final Supplemental En ironmental Impact Statement child 89 4

Completion and Operation o Watts Bar Nuclear Plant Unit 2 Table 3-22. Com arison of stimated Annual Airborne Releases and Resulting Doses Unit 1 1 CFR 5 1 2F S Unit 1 Unit 2 Units 1 2 1 -year A endi (Table 2. -2) FSAR aluation Combined O erational uidelines A erage er Unit Particulate Acti ity (Ci1) 3.0E-01 7.6E+00 4.70E-02 7.6E+00 9.29E-05 10 oble as Acti ity (Ci1) 7.0E+03 1.4E+04 4.84E+03 4.84E+03 2.7E-03 N/A2 ternal Dose (mrad3) 6.6E+00 6.2E+00 3.5E+00 9.7E+00 3.69E-01 10 Organ Dose 3.5E+00 2.82E+00 1.38E+01 8.3E-02 (mrem4) (inhalation 1.1E+01 (all (all (all 15 and mil (all pathways) pathways) pathways) pathways) only) 1 Ci = Curies 2

N/A = Not Applicable 3

mrad = millirad 4

mrem = millirem Replace with data on the nextTwopage conclusions can be drawn rom the data in Table 3-20 x The Unit 2 FSAR estimates, e en though based on ery conser ati e (worst-case) assumptions, indicate that estimated doses continue to meet the per unit dose guidelines gi en in 10 CFR Part 50, Appendi I.

x Historical WBN operational data or airborne e luents indicate that actual releases and resulting dose estimates (e ternal and organ) to the public are a small raction o the Appendi I guideline (a eraging 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 Doses TVA has estimated the radiological impact rom the normal operation o WBN Unit 2 using a 50-mile regional population pro ection 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 Radioacti e E luent Reports to the NRC) are presented in Table 3-23.

Table 3-23. stimated Po ulation Doses From O eration of Watts ar uclear Plant Unit 1 1 -year 1 CFR 5 1 2F S Unit 1 Unit 2 Units 1 2 O erational A endi (Table 2. - ) FSAR aluation Combined A erage uidelines 3.1E+01 12.8E+00 2.362E+01 3.64E+01 3.38E-01 N/A 90 Final Supplemental En ironmental Impact Statement

9.42E-01 9.68E+03 For FSEIS Table For FSEIS Table 3-22 3-23

Completion and Operation o Watts Bar Nuclear Plant Unit 2 Revise to read Auxiliary Building Vent (Common) and Continuous Vents Figure 3- . Watts ar uclear Plant aseous ffluent Release Points 88 Final Supplemental En ironmental Impact Statement

Enclosure 2, Attachment 5 Response to FSAR Chapter 11 and FSEIS, Chapter 3 Request For Additional Information Proposed Clean Copy of FSEIS, Chapter 3

Chapter 3 C APT R 3

3. C A S T AFF CT D RO TA D RO TAL CO S U C S The en ironmental conse uences o constructing and operating WBN were addressed comprehensi ely in the 1972 FES or WBN Units 1 and 2. Subse uent en ironmental re iews 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 e ects had already occurred. As described in Section 2.1, WBN Unit 2 would use structures that already e ist and most o the wor re uired 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 tentati e site plan are not irm, any relocation would occur within the mar ed 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 re iews by TVA and NRC in 1993 and 1995 ocused primarily on the completion o WBN Unit 1. Some modi ications to plant design and operations ha e occurred since that time.

Chapter 3 summarizes the en ironmental e ects assessed in past WBN-related en ironmental re iews, identi ies any new or additional e ects that could result rom the completion and operation o WBN Unit 2, and assesses the potential or impacts. The current re iew ocused on the entire proposed area to be disturbed.

Cumulati e ffects cumulati e e ects 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 cumulati e e ects to sur ace water and a uatic resources are addressed by the plant s NPDES permit and its monitoring re uirements. Concerns o er potential cumulati e e ects to air were tied to emissions rom WBF plant, which had not operated since 1983 and has since been retired.

Cumulati e e ects are also considered in many o the documents incorporated by re erence and/or tiered rom or this supplement. Most notably, cumulati e e ects o spent uel storage and transportation were addressed in the CLWR FEIS cumulati e e ects o transportation o radioacti e materials were addressed in NUREG-75/038 (NRC 1975) and cumulati e e ects o hydrothermal and water supply were addressed in the ROS FEIS. In this re iew, TVA has ound that no new or additional cumulati e e ects beyond those identi ied in earlier NEPA documents are e pected to result rom completing the construction o WBN Unit 2. As summarized in Table 2-1, or the most part, only minor, temporary, or insigni icant e ects are e pected or most o the resources considered. As such, these e ects are not e pected to contribute to cumulati e impacts on a ected resources. The potential or additional operational cumulati e e ects are considered in the ollowing assessments.

Final Supplemental En ironmental Impact Statement 33

Completion and Operation o Watts Bar Nuclear Plant Unit 2 3.1. Water uality 3.1.1. S W E Hydrothermal e ects primarily consist o the impact o the heated e luent rom WBN on the Tennessee Ri er. Here, hydrothermal e ects are di ided into two categories, near- ield e ects and ar- ield e ects. Near- ield e ects consist o the impact o the heated e luent on the ri er water temperature in the immediate icinity o the plant, as de ined by the assigned mi ing zones or the out alls in the NPDES permit. Limits or ri er water temperature are speci ied by the State o Tennessee in the NPDES permit or the plant. Far- ield e ects consist o the impact on the recei ing stream on a larger scale, in this case all o Chic amauga Reser oir.

Waste heat created by the operation o WBN is dissipated both in the atmosphere and in the Tennessee Ri er. A description o the heat dissipation system is gi en in Section 2.2.2. The current con iguration o the system includes three out alls to the ri er. Out all 101 includes regulated releases through two multiport di users located on the bottom o the ri er at TRM 527.9. Out all 102 includes emergency o er low rom the plant yard holding pond and consists o a sur ace discharge rom a local stream channel at TRM 527.2. Historically, releases rom Out all 102 ha e been made only when maintenance is re uired or Out all 101. Out all 113 includes releases rom the WBN SCCW system through a discharge structure at TRM 529.2.

Out all 113, originally the out all or the retired WBF, consists o a shoreline release slightly below the water sur ace o the ri er. The current con iguration o the SCCW system pro ides 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 modi ied to preser e the original design bases or all three out alls.

An e tensi e number o pre ious studies on the hydrothermal characteristics o releases rom WBN ha e been conducted o er the years. These studies are described and their results summarized in Appendi A. In general, these studies ha e basically e aluated and documented

1. That WBN can be e ecti ely operated without causing iolations o water temperature limits in the Tennessee Ri er (near- ield e ect).

2. The alidity o operating assumptions made in pre ious analyses.

3. The alidity o the assigned mi ing zones and modeling results or ri er temperature.

4. E aluations or changes such as the addition o the SCCW system or the Reser oir Operations Study (ROS).

5. That operation o WBN is not e pected to ha e any noticeable impact on Chic amauga Reser oir ( ar- ield e ect).

PD S Ri er Tem erature Limits The current NPDES permit limits or managing the near- ield impact o the thermal e luent rom WBN out alls are summarized in Table 3-1. Those or Out all 101 and Out all 102 apply to the temperature o the e luent be ore it enters the ri er (i.e., end-o -pipe limitations). Those or Out all 113 are instream limitations and apply relati e to the assigned mi ing zones. Releases rom Out all 101 can be made only when the low in the ri er rom WBH is at or abo e 3500 c s.

34 Final Supplemental En ironmental Impact Statement

Chapter 3 Releases rom Out all 113 do not re uire a minimum low in the ri er, e cept in e ents where there is a planned, sudden change in the thermal loading rom the SCCW system.

Table 3-1. PD S Tem erature Limits for W Outfalls to the Tennessee Ri er Outfall ffluent Parameter Daily Re ort Limit 101 E luent Temperature Daily A g 35.0 C (95 F) 102 E luent Temperature Grab 35.0 C (95 F)

Instream Temperature1 Ma Hourly A g 30.5 C (86.9 F)

Instream Temperature Rise2 Ma Hourly A g 3.0 C (5.4 F) 113 Instream Temperature Rate-o -Change1 Ma Hourly A g 2 C /hr ( 3.6 F /hour)

Instream Temperature Recei ing Stream Bottom3 Ma Hourly A g 33.5 C (92.3 F) 1 Notes Downstream edge o mi ing zone 2

Upstream ambient to downstream edge o mi ing zone 3

Mussel relocation zone at SCCW outlet i ing ones The mi ing zone or Out all 101 is shown in Figure 3-1. The recommended dimensions o the mi ing zone are based on a physical hydrothermal model test o the di users (TVA 1977b, 1977c). Measurements rom the model indicated that su icient mi ing would be achie ed at a distance e ui alent to roughly the length o the out low section o the di user ports. The blowdown system includes two di user legs, one containing an out low section 80 eet long (upstream) and one containing an out low section 160 eet long (downstream). Hence, the assigned mi ing zone or Out all 101 is 240 eet wide and 240 eet downstream. The width o the ri er at Out all 101 is about 1100 eet, thus about 80 percent o the ri er is a ailable or sa e passage o ish. The design o the di users and mi ing zone are based on the operation o both units at WBN, and the e treme ri er conditions used or the design o the di user are still applicable (i.e., minimum ri er low o 3500 c s). For the operation o one unit, the per ormance o the di user was con irmed by ield studies a ter the startup o Unit 1 (TVA 1998b). Similar studies would be per ormed to con irm the per ormance o the di users with the operation o two units at WBN.

Since releases resulting rom the emergency o er low o the yard holding pond are so in re uent, a mi ing zone currently is not de ined in the NPDES permit or Out all 102.

For Out all 113, standards or water temperature are en orced by means o two mi ing zones, acti e and passi e, as shown in Figure 3-2. Two mi ing zones are used to better align monitoring o Out all 113 with the beha ior o the e luent in the ri er. Computations and measurements show that spreading o the e luent rom Out all 113 aries substantially between conditions and low in the ri er rom Watts Bar Dam (TVA 1997b, 2001, 2004b).

For conditions low, the e luent tends to reside in the right-hand-side o the ri er ( acing downstream) and is monitored by the acti e mi ing zone, which includes instream temperature monitors at its downstream edge. For conditions low, the e luent can spread across the ri er and is monitored by the passi e mi ing zone. Since the passi e mi ing zone encompasses regions o the ri er that must remain clear or na igation, the ade uacy o the passi e mi ing zone is chec ed biannually (winter and summer) by special water termperature sur eys (i.e., rather than instream monitors). Out all 113 is a near-sur ace discharge, and computations and measurements con irm that the heated e luent rom Out all 113 disperses in the sur ace region o the water column (TVA, 1997b, 2001, 2004b, 2005c, 2006a, 2007b, 2007c), pro iding ample room beneath or the sa e passage o ish, particularly in the deep Final Supplemental En ironmental Impact Statement 35

Completion and Operation o Watts Bar Nuclear Plant Unit 2 na igation channel on the right-hand-side o the ri er. TVA would not change the dimensions o the Out all 113 mi ing zones with the completion and startup o Unit 2.

Figure 3-1. i ing one for Outfall 1 1 Figure 3-2. i ing ones for Outfall 113 It is important to note that since the startup o WBN Unit 1, the plant has operated success ully through a wide range o ri er low conditions, without any e ceedences o the NPDES limits or the near- ield impact o thermal e luent on the Tennessee Ri er. Concurrently, no signi icant 36 Final Supplemental En ironmental Impact Statement

Chapter 3 ad erse impacts ha e been reported on the ecological health o the ri er as a result o releases rom any o the WBN discharge structures Out all 101, Out all 102, or Out all 113.

U dated ydrothermal Analyses In depth near- ield hydrothermal analyses o the heat dissipation system ha e been updated or the proposed completion and operation o WBN Unit 2 (Dynamic Solutions 2007). This was necessary or se eral reasons. First, although the SCCW system has pro en to be an e ecti e method to boost generation o the plant, the combined operation o Unit 1 and Unit 2 with the SCCW system had not been e amined. Second, detailed multiyear simulations with the dual mi ing zone or Out all 113, as depicted in Figure 3-2, had not been per ormed. Third, pre ious model e aluations had not considered the combined operation o Unit 1 and Unit 2 coupled with the ri er 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 pre ious model e aluations and the modi ications to the Out all 113 mi ing zone.

The updated analyses began with the model used or the 1998 EA o the SCCW system (TVA 1998a). For the updated analyses, modi ications were made in the model or (1) combined operation o Unit 1 and Unit 2, (2) discharges rom Out all 113 with dual mi ing zones, (3) ambient ri er conditions based on the ri er operations policies o the ROS, and (4) per ormance 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 pro ide the same le el o per ormance as that o the cooling tower or Unit 1.

WBN Unit 2 would operate with the original steam generators.

The SCCW system currently ser es Unit 1. With the combined operation o Unit 1 and Unit 2, the SCCW system would ser e both units. While some modi ications to the SCCW system would be re uired or combined operation (see abo e), these modi ications would be limited to installed plant systems and would not change the olume o water deli ered and remo ed by the SCCW system. The ollowing analysis assumes that the SCCW system would be changed to pro ide ser ice solely to Unit 2. This assumption pro ides a suitable bounding estimate o the potential order o magnitude o the hydrothermal impact on the Tennessee Ri er 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 ri er through Out alls 101, 102, and 113.

Mi ing o thermal e luent rom Out all 101 is ade uately described by the obser ed beha iour in the physical model study o the discharge di users (TVA 1977b TVA 1997c),

and in a ield study conducted a ter the startup o Unit 1 (TVA 1998c).

Mi ing o thermal e luent rom Out all 113 is ade uately described by an analysis tool recommended by the U.S. EPA nown as CORMIX ( ir a, et al. 1996).

Model simulations were per ormed or a 30-year period based on obser ed hydrology and meteorology in the upper Tennessee Ri er watershed or years 1976 through 2005. The model input re uires the low and ambient temperature o the ri er at WBN. To incorporate the impact o the ROS operating policy, a reser oir scheduling model was used to help estimate the hourly ri er low at WBN. Hourly alues o the ambient water temperature were estimated using SysTemp, a collection o lin ed water uality models o the ey water Final Supplemental En ironmental Impact Statement 37

Completion and Operation o Watts Bar Nuclear Plant Unit 2 bodies in the Tennessee Ri er reser oir system. The reser oir scheduling model and SysTemp were both pre iously calibrated as a part o the ROS FEIS (TVA 2004a).

An important aspect common to all the abo e 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 Out alls 101, 102, and 113. That is, the ma imum olume o low and heat rom the out alls would not change substantially rom their original design. For Out alls 101 and 102, this includes the operation o both WBN units, and or Out all 113, this includes a ma imum low o about 365 c s, whether rom Unit 1, Unit 2, or both Unit 1 and Unit 2. In this manner, the updated hydrothermal analyses would primarily ascertain the e pected impact o recent changes in ri er operations, and pro ide assurance that with both WBN units, the current mi ing zones and methods o operating the plant and ri er would e ecti ely satis y state standards or instream water temperature and pro ide sa e passage or a uatic species in Chic amauga Reser oir.

Two operating cases or WBN were considered as part o the updated hydrothermal analyses Unit 1 only (i.e., current, base case conditions) and combined operation o Unit 1 and Unit 2, with the SCCW system ser ing 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 a erage releases ranged rom a minimum o 3300 c s in May to a ma imum o o er 150,000 c s in both March and April. Flows o er about 45,000 c s would be due to spill operations in support o lood control. On an hourly basis, releases can be 0 c s, due to pea ing operations o the hydro units. The o erall a erage release or the entire 30-year period was about 27,000 c s. The hourly release temperature aried between a minimum o 36.3 F in February and a ma imum o 84.6 F in August. Thus, based on historical hydrology and meteorology, the ambient ri er temperature is not e pected to e ceed the state standard o 86.9 F.

Table 3-2. stimated ydrothermal Conditions for Release From Watts ar Dam Daily A erage Release ourly Release ourly Release (cfs) onth (cfs) Tem erature ( F) in ean a in ean a in ean a an 5,600 36,900 122,400 0 36,900 122,400 36.6 44.0 52.0 Feb 6,300 43,000 115,300 0 43,000 115,300 36.3 43.8 52.2 Mar 5,000 36,600 156,600 0 36,600 156,600 38.9 48.9 60.0 Apr 3,600 21,000 156,600 0 21,000 156,600 47.8 56.3 65.4 May 3,300 17,300 119,300 0 17,300 119,300 54.4 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 32,300 102,300 37.7 49.3 59.5 Notes

1. Results per SysTemp hydrothermal model simulation

2. Reser oir operating policy per the ROS FEIS

3. Historical hydrology and meteorology or 1976 through 2005 38 Final Supplemental En ironmental Impact Statement

Chapter 3 The ollowing summaries are pro ided or the results o the updated hydrothermal analyses.

Out all 101 The estimated hydrothermal conditions or the thermal e luent rom Out all 101 are gi en 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 Out all 101 aried between 0 c s and about 108 c s. Discharges o 0 c s occur or periods when the release rom WBH is less than 3500 c s. With both WBN units in ser ice, the hourly discharge rom Out all 101 can be as large as 175 c s, as shown in Table 3-4. This is about 3 percent larger than the ma imum alue cited in pre ious design studies (TVA 1977b), but is not considered signi icant with respect to the as-built size o the blowdown system. For both cases, the estimated ma imum daily a erage e luent temperature was 89.8 F, well below the NPDES limit o 95 F. For the purpose o udging the impact on instream ri er temperatures, the statistical properties o the resulting hourly ri er temperature and ri er temperature rise also are gi en in Tables 3-3 and 3-4. As shown, the ma imum alues are well below the state standards o 86.9 F or ma imum ri er temperature and 5.4 F or ma imum ri er temperature rise. For the latter, the estimated ma imum 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 le els, the ma imum 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 1 1 With Unit 1 O eration ourly Tem erature at ourly Tem erature Daily A erage ffluent ourly Discharge (cfs) Do nstream dge of Rise at Do nstream onth Tem erature ( F) i ing one ( F) dge of i ing one (F )

in ean a in ean a in ean a in ean a an 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 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 ser ing Unit 1

5. Reser oir operating policy per the ROS FEIS

6. Historical hydrology and meteorology or 1976 through 2005 Final Supplemental En ironmental Impact Statement 39

Completion and Operation o Watts Bar Nuclear Plant Unit 2 Table 3- . stimated ydrothermal Conditions for Thermal ffluent From Outfall 1 1 With Unit 1 and Unit 2 O eration ourly Tem erature at ourly Tem erature Daily A erage ffluent ourly Discharge (cfs) Do nstream dge of Rise at Do nstream onth Tem erature ( F) i ing one ( F) dge of i ing one (F )

in ean a in ean a in ean a in ean a an 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 Notes

1. 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 ser ing Unit 2

5. Unit 2 cooling tower per ormance the same as Unit 1 cooling tower per ormance

6. Reser oir operating policy per the ROS FEIS

7. Historical hydrology and meteorology or 1976 through 2005 Out all 102 For both the sole operation o Unit 1 (base case) and the combined operation o both Unit 1 and Unit 2, there were no e ents with o er low rom the plant yard holding pond. As a result, under normal operating conditions, releases rom Out all 102 are not e pected.

Out all 113 The estimated hydrothermal conditions or the thermal e luent rom Out all 113 are gi en 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 Out all 113 aried between about 222 c s and about 294 c s. This demonstrates that the low rom the SCCW system is independent o the unit ser ed 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 e luent temperature through Out all 113 aried between about 39.5 F and 97.3 F. Since the low and temperature o the SCCW e luent are essentially the same or both cases, similar conditions are ound or instream temperature conditions. The estimated ma imum hourly instream ri er temperature or both cases is 84.7 F, well below the NPDES limit o 86.9 F. The estimated ma imum hourly instream ri er temperature rise or both cases is 5.4 F , which is the same as the current NPDES limit. The estimated largest hourly instream ri er 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 e treme alues or the temperature rise and temperature rate-o -change occur in the cooler winter months o the year, when the buoyancy-related mi ing o the thermal e luent is reduced. In practice, TVA would not ris operation o the SCCW system with the e luent parameters so close to the NPDES limits. In e treme temperature e ents, the SCCW system would be operated in a more conser ati e manner than what has been assumed in the hydrothermal model. In particular, the temperature o the Out all 113 e luent would be reduced 40 Final Supplemental En ironmental Impact Statement

Table 3-5. stimated ydrothermal Conditions for Thermal ffluent From Outfall 113 With Unit 1 O eration ourly Tem erature ourly Tem erature ourly Tem erature at ourly ffluent Rise at Do nstream Rate-of-Change at ourly Discharge (cfs) Do nstream dge of onth Tem erature ( F) dge of Do nstream dge of i ing one ( F) i ing one ( F) i ing one ( F hr)1 in ean a in ean a in ean a in ean a in ean a an 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 1

Amount o change in rei er 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 Final Supplemental En ironmental Impact Statement

4. SCCW ser ing Unit 1

5. Reser oir operating policy per the ROS FEIS

6. Historical hydrology and meteorology or 1976 through 2005 Chapter 3 41

42 Completion and Operation o Table 3- . stimated ydrothermal Conditions for Thermal ffluent From Outfall 113 With Unit 1 and Unit 2 O eration ourly Tem erature ourly Tem erature ourly Tem erature at ourly ffluent Rise at Do nstream Rate-Of-Change at ourly Discharge (cfs) Do nstream dge of onth Tem erature ( F) dge of Do nstream dge of i ing one ( F) i ing one (F ) i ing one (F hr)

Watts Bar Nuclear Plant Unit 2 in ean a in ean a in ean a in ean a in ean a an 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 Notes

1. 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 ser ing Unit 2

5. Unit 2 cooling tower per ormance the same as Unit 1 cooling tower per ormance

6. Reser oir operating policy per the ROS FEIS

7. Historical hydrology and meteorology or 1976 through 2005 Final Supplemental En ironmental Impact Statement

Chapter 3 by passing additional water through the SCCW bypass conduit or perhaps by remo ing the SCCW system rom operation.

For Out all 113 the NPDES permit also includes a limitation on the ma imum temperature o the recei ing stream bottom (mussel relocation zone). This temperature is not estimated by the WBN hydrothermal model. Howe er, historical data can be e amined to demonstrate that the Out all 113 e luent would not create a signi icant impact on ri er bottom temperature. Measured temperatures or the Out all 113 e luent and ri er 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, e en in a warm year, the ma imum MRZ bottom temperature is only about 84 F, well below the NPDES limit o 92.3 F. It is important to note that the ma imum allowable temperature o essential raw cooling water (ERCW) or continued operation o WBN Unit 1 currently is 85 F, which is needed to guarantee a sa e shutdown o the reactor in the e ent o an emergency. E orts currently are underway to increase this limit to 88 F (TVA, 2004c, 2006b). The completion o Unit 2 is e pected to include an ERCW limit o 88 F. I the water temperature at the plant pumping station located 1.3 miles downstream o Out all 113 approaches 88 F, the operation o WBN would be suspended, and thus the heat load rom the SCCW system would be dramatically reduced. There ore, in terms o protecting bottom-dwelling species and ish passage, the impact to the ri er rom Out all 113 would by necessity be reduced by WBN suspension o operations should the ambient bottom temperature e er reach 88 F, still well below the MRZ temperature limit o 92.3 F.

100 Out all 113 E luent Temperature MRZ Bottom Temperature NPDES Limit 92.3 F 90 ERCW Limit 88.0 F 80 Water Tem erature ( F) 70 60 50 40 1999 2000 2001 2002 2003 2004 Figure 3-3. easured Tem eratures for Outfall 113 ffluent and ottom of ussel Relocation one Final Supplemental En ironmental Impact Statement 43

Completion and Operation o Watts Bar Nuclear Plant Unit 2 m act on W O eration As emphasized in Section 2.2.1, the purpose o the WBN SCCW is to enhance the per ormance o the unit(s) that it ser es. When TVA anticipates that one or more o the NPDES temperature limits are threatened or Out all 113, part o the SCCW in low is di erted ia the bypass to the discharge conduit to reduce the temperature o the SCCW e luent (e.g., see Figure 2-2). I the temperature o the Out all 113 e luent cannot be su iciently reduced by this process, the SCCW system is remo ed rom ser ice. In this manner, the impact o the SCCW system on WBN operation can be e aluated based on the length o time the SCCW system is placed in bypass and the length o time the SCCW system is remo ed rom ser ice. Pro ided in Table 3-7 is a summary o these impacts or the two cases e amined 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 pro ides a slight reduction in the hours o re uired bypass operation, and no change in the number o hours the system must be remo ed rom ser ice. For all practical purposes, gi en modeling uncertainties, the results in Table 3-7 suggest that the completion and operation o Unit 2 as assumed herein would not create a substanti e change in the operation o the SCCW system. The a erage 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 a erage 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 di erence is due to the minor change in per ormance characteristics o the new steam generators or Unit 1 erses the original steam generators or Unit 2.

Table 3- . Predicted SCCW m act on W O eration A erage ours A erage ours er ear Case er ear SCCW Remo ed SCCW in y ass From Ser ice Unit 1 only with SCCW 525 10 ser ing Unit 1 (base case)

Unit 1 and Unit 2 with SCCW 515 10 ser ing Unit 2 Lo Ri er Flo It is important to note that the simulation period rom 1976 through 2005 contains our o the i e driest years e er recorded in East Tennessee, 1988, 1986, 2000, and 2005 (1st, 3rd, 4th, and 5th driest or period o record rom 1875 to present). Thus, the simulations summarized herein encompass perhaps near the most e treme conditions e pected or the impact o WBN thermal e luent on the ri er. For Out all 101, the e tent o dry conditions is o little signi icance because the thermal e luent can be released rom Out all 101 only when the discharge rom Watts Bar Dam is at least 3500 c s. That is, e en in the driest years, there will be at least 3500 c s o low in the ri er or the assimilation o waste heat rom WBN.

The minimum daily a erage release in Table 3-2, 3300 c s, would allow a release o 3500 c s 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 le els abo e 3500 c s (e.g., 6000 c s). Under these conditions, the impact o a dry year is to reduce the number o hours per day that a low o 3500 c s can be pro ided or Out all 101, thereby orcing a greater olume o water to be stored in the WBN yard holding pond. This would increase the probability o an o er low rom the yard holding pond and unwanted releases rom Out all 102. But as presented earlier, in the 30-year 44 Final Supplemental En ironmental Impact Statement

Chapter 3 simulations, there were no e ents where it was ound necessary to pro ide releases rom the yard holding pond ia the emergency o er low (i.e., including years such as 1988).

For Out all 113, the impact o a low low year would be to increase the duration o e ents where hourly releases rom the SCCW system are made in the absence o hourly releases rom Watts Bar Dam. In general, or such e ents, i there is a threat to one or more o the hourly instream water temperature limits, the amount o heat released rom Out all 113 would be reduced by passing water through the SCCW bypass conduit or perhaps by remo ing the SCCW system rom operation. Since the plant can be operated without the SCCW system in ser ice, such action poses no threat to the o erall integrity o WBN generation. O erall, because WBN in closed mode uses such a small amount o low compared to the potential minimum daily a erage low in the ri er, the plant thermal e luent under e treme low low conditions would not ha e an ad erse impact on water temperature in the Tennessee Ri er.

O erall ear-Field ffects O erall, with the recent changes that ha e been made at the plant (e.g., SCCW system and new steam generators or Unit 1) and or the operation o the Tennessee Ri er (i.e., ROS),

the updated hydrothermal analyses recon irm, as concluded in the 1972 FES, that the operation o two units at WBN will not ha e a signi icant impact on near- ield hydrothermal conditions in the Tennessee Ri er. E ects on water temperatures in the ri er can be e ecti ely maintained within the current NPDES limits or all the plant discharge out alls without signi icant ad erse e ects on plant generation. Additionally, data rom recent ield studies (Appendi A) support the methods o modeling the dissipation o waste heat in the ri er, and the patterns o mi ing rom the out alls pro ide ample space or ish passage and protection o bottom habitat.

Far-Field ffects By irtue o the act that the heated e luent is e pected to ha e an insigni icant impact on near- ield conditions in ri er, ar- ield impacts on Chic amauga Reser oir also are e pected to be insigni icant, or both the operation o one or two units at WBN. This is supported by the WBN discharge temperature limit e aluation conducted in 1993 (TVA 1993b), by water uality modeling per ormed as part o the ROS FEIS (TVA 2004a), and by operating e perience since the startup o Unit 1 in 1996. Ongoing acti ities under the TVA Reser oir Releases Impro ement Program and the TVA Vital Signs Monitoring Program would continue to pro ide close scrutiny o any potential ar- ield impacts rom the heated e luent rom WBN.

The near- ield and ar- ield e ects summarized abo e are based on the hydrothermal analyses described herein, and are udged to ha e no signi icant impact on temperatures in Chic amauga Reser oir. That conclusion, howe er, is limited to the impacts o discharge to the Tennessee Ri er rom Out alls 101, 102, and 113 associated with the presumed simultaneous operation o Watts Bar Units 1 and 2. The potential or cumulati e e ects o the completion o WBN Unit 2 in con unction with other actors that could impact Tennessee Ri er temperatures was also considered.

In une 2004, ollowing completion o a detailed ROS, TVA implemented a new reser oir operating policy (TVA 2004a). This policy speci ied changes in the operating guide cur es at Chic amauga and other reser oirs. Potential changes in reser oir 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 Final Supplemental En ironmental Impact Statement 45

Completion and Operation o Watts Bar Nuclear Plant Unit 2 strati ication, both cold and warm water olumes, dissol ed o ygen, and algae. The impacts o the adoption o the ROS pre erred operating policy or all o these characteristics, relati e to the pre ious operating policy, were determined to be insigni icant in Chic amauga Reser oir. There is no e idence to suggest that the adoption o the new operating policy has had or will ha e any contribution to cumulati e e ects in Chic amauga Reser oir. Whereas the ROS studies included only the operation o WBN Unit 1, the updated hydrothermal analyses summarized abo e show that the impact to the near- ield ri er temperature o adding WBN Unit 2 would be insigni icant. As such, the startup o WBN Unit 2 would not change this conclusion regarding the potential or cumulati e e ects.

3.1.2. S W A R W The re erenced earlier en ironmental re iews analyzed potential impacts to sur ace water and water uality. A primary area o concern or sur ace water and water uality relates to the chemicals added to treat raw water. These earlier analyses continue to ade uately depict the inds o chemicals used at the plant and associated en ironmental impacts.

Proposed chemical additi es and their respecti e to icological data are presented to the state or appro al prior to plant use in the acility s Biocide and Corrosion Treatment Plan (B/CTP) re uired by the WBN Unit NPDES permit. To ensure the water uality criteria in the recei ing stream is maintained, the state re iews the chemical usage re uest and e aluates the reasonable potential en ironmental impacts o a speci ic chemical discharge to determine the plant NPDES permit monitoring re uirements 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 Out all 101 and Out all 102 turbine building sump water, alum sludge supernate, re erse osmosis re ect water, drum dewatering water, water puri ication 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 Out all 112 and SCCW rom Out all 113 to the Tennessee Ri er (re er to Figure 1-2, Unit 2 Site Plan and Appendi B, NPDES Flow Diagram). In addition to re isions to the B/CTP, the potential sources o chemicals and chemical uantities are re iewed and updated in connection with the application or NPDES Permit renewal. Compliance with the State Water uality criteria is also con irmed by routine semi-annual Whole E luent To icity (WET) testing at Out all 101, Out all 112, and Out all 113.

TVA applied to renew the WBN permit in May 2006. To support the application or this permit reissuance, a detailed wal down o the plant was conducted to ensure that pre iously identi ied discharge point sources remain alid. A comprehensi e sampling and analysis e ent was also conducted to characterize waste water discharges rom the authorized discharge points.

As a component o the NPDES Permit, Part III, Section G, B/CTP, WBN is authorized to conduct treatments o inta e or process waters with biocides, dispersants, sur actants, corrosion inhibiting chemicals, and deto i ication chemicals. To ensure protection o the recei ing stream, water treatment processes are controlled to comply with State Water uality criteria and applicable NPDES permit conditions. WBN monitors e luent discharges and reports to the state the speci ic chemicals in ected along with the respecti e acti e ingredient discharged on the monthly Discharge Monitoring Report (DMR) and the Annual B/CTP Report. In addition, WBN per orms semi-annual WET testing at Out all 101, Out all 112, and Out all 113. Most o the chemicals used in these treatment programs are added at 46 Final Supplemental En ironmental Impact Statement

Chapter 3 the IPS to ensure all raw water systems are protected. Se eral o these systems, the High Pressure Fire Protection and the ERCW systems in particular, are essential or the sa e operation o the plant.

While WBN has re uested modi ications to the B/CTP o er the years, the approach and acti e ingredients or the arious water treatment programs at WBN ha e not undamentally changed. Proposed chemicals undergo an e tensi e to icological re iew and comparison with ma imum instream wastewater concentrations to ensure water uality standards are met. The products used ha e changed o er the years to slightly di erent ormulations o the same acti e ingredients or constituents and the processes or re uencies o applying those products occasionally ha e been changed. These B/CTP modi ications continue to pro ide the same high le el o protection or a uatic li e in the Tennessee Ri er while increasing the le ibility o plant e uipment treatment options. Most recently, WBN submitted a B/CTP modi ication re uest to the state in December 2006. TVA sought appro al (1) to replace the dispersant PCL-401 with 73200, (2) or continuous use o o idizing biocides, and (3) to chlorinate using sodium hypochlorite. In addition, TVA re uested to add the non-o idizing biocide H150M to the B/CTP appro al list. This re uest was appro ed 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 1998 ERCW/RCW Spectrus NX1104* 1998 Present ERCW/RCW CopperTrol CU-1 1996 1998 ERCW/RCW Biotrol 88P 1996 1998 ERCW/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 -Present1 Chemical Start ear nd ear System H-901G 1996 Present ERCW3/RCW4 Coppertrol 1996 1999 ERCW/RCW PCL-10Z 1996 2002 ERCW/RCW PCL-60 1996 2002 ERCW/RCW PCL-401 1996 2006 ERCW/RCW Towerbrom 960 1999 Present Cooling Tower H-130M2 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 deto i ication in 2002 3

ERCW = Essential Raw Cooling Water 4

RCW = Raw Cooling Water Final Supplemental En ironmental Impact Statement 47

Completion and Operation o Watts Bar Nuclear Plant Unit 2 Ra Water Chemical Treatment Summary for the W Unit 1 CTP The ollowing summarizes chemical treatment programs currently in use or a ailable or uture use at WBN Unit 1 and/or Unit 2 or corrosion, deposit, microbiological, and macro ouling control in the raw water systems in accordance with the current B/CTP.

Protection o the raw water cooling water pipe systems re uires o idizing biocide (chlorination) and non-o idizing biocide treatments to control macro in ertebrates and microbiologically induced corrosion (MIC). WBN currently uses products rom Nalco, a ma or 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 ri er water temperature is abo e 60o F. The concentration o zinc and phosphorous is not to e ceed 0.2 parts per million (ppm) at e luent discharges Out all 101 and Out all 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 acti e HSP le el will not e ceed 0.2 ppm at e luent discharges Out all 101 and Out all 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 le el will not e ceed 0.25 ppm at e luent discharges Out all 101 and Out all 113.

Raw Water Microbiological/Macro ouling Treatment Microbiological and macro ouling re ers to the undesirable accumulation o microorganisms, plants, algae, and a uatic animals on submerged structures and piping systems. WBN currently in ects on a continuous basis the o idizing biocide BCDMH (H-901G) or microbiological and macro ouling control in the ERCW and RCW systems. Continuous o idation is necessary to ensure plant sa ety as TVA has recently obser ed year-round eliger (mussel lar ae) in estations. H-901G puts 57 percent o its acti e halogen ingredient into solution as bromine and chlorine. Chlorine, or Total Residual O idant (TRO) is monitored i e (5) days per wee at Out all 101 and Out all 113 in accordance with permit re uirements to ensure discharge limits o 0.10 ppm or 0.158 mg/l daily ma imum (respecti ely) are met.

As an alternati e to H-901G, WBN has the option to eed li uid bleach in the orm o sodium hypochlorite. Li uid bleach, containing 10.2 percent a ailable chlorine, can also be ed on a continuous basis. Monitoring or chlorine le els in the e luent would remain the same as or H-901G.

An option to eed a biodetergent (73551) to increase the e icacy o either H-901G or li uid bleach with microbiological control has been retained by WBN. The 73551 biodetergent consists o a 20 percent blend o non-ionic sur actants and is ed or 30 minutes one to three times per wee to the ERCW and RCW systems. The acti e sur actant le el will not e ceed 2.0 ppm to the e luent discharges Out all 101 and Out all 113.

48 Final Supplemental En ironmental Impact Statement

Chapter 3 WBN de-chlorinates as re uired using sodium bisul ite (Nalco 7408) to ensure the current discharge limit o 0.1 ppm TRO is not e ceeded at e luent discharges Out all 101 or 0.158 mg/l daily ma imum at Out all 113. Nalco 7408 consists o 45 percent sodium bisul ite and is ed at a ratio o appro imately 4 ppm product or e ery 1.0 ppm o TRO. The sodium bisul ite le el will not e ceed 10 ppm at e luent discharges Out all 101 and Out all 113.

When ri er temperatures are greater than or e ual to 60qF, WBN terminates o idizing biocides treatment and per orms a periodic (minimum o 4 times per train per year) non-o idizing biocide treatment o the raw water systems. A train is the cluster o e uipment which must be operational to per orm a certain unction.

WBN uses a non-o idizing biocide (H150M, Clamtrol) to limit Asiatic clam and zebra mussel populations in the raw water system, the presence o which can signi icantly a ect ERCW and RCW system per ormance. 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 acti e H150M residual to no more than 0.05 ppm at e luent discharges Out all 101 and Out all 113, bentonite clay (Coagulant Aid-35) is ed into the Unit 1 cooling tower basin prior to e luent discharge to the ri er ia NPDES out alls Out all 101 or Out all 113. Coagulant Aid-35 is ed at a ratio o 5 parts to 1 part H150M during each mollus treatment. Total clay le el is not to e ceed 10 ppm at e luent discharges Out all 101 and Out all 113. The e ecti eness o deto i ication is con irmed with twice daily sampling or the acti e ingredient in the discharge during the treatment period.

Cooling Tower Treatments WBN currently adds Towerbrom 960 to the cooling tower basin on a periodic basis or microbiological control or CCW. Towerbrom 960 is an o idizing biocide, containing 57 percent a ailable halogen, and generates bromine and chlorine solutions when dissol ed in water. WBN also has the option to eed li uid bleach in place o Towerbrom 960. This treatment is per ormed with the di users and the SCCW system isolated (closed). To ensure the current discharge limit o 0.1 ppm TRO is not e ceeded at e luent discharges Out all 101 or 0.158 mg/l daily ma imum at Out all 113, the chemically treated water is not released to the ri er until the discharge concentration o chlorine is below the NPDES permit limit. To enhance the e ecti eness o this program, WBN has re uested the option to eed Biodetergent 73551 with Towerbrom 960. WBN de-chlorinates as needed using sodium bisul ite (Nalco 7408) to ensure the current discharge limit o 0.1 ppm TRO is not e ceeded at e luent discharges Out all 101 or 0.158 mg/l daily ma imum at Out all 113.

Nalco 7408 is ratio- ed at a rate o 4 ppm product or e ery 1.0 ppm o chlorine.

Additional Chemicals Used in W Processes In addition to the raw water additi es or biocide and corrosion treatment chemicals discussed abo e, other chemical additi es are used in plant processes. These chemicals may be ound in trace uantities at the arious NPDES discharge points (Out all 101, Out all 102, IMP 103, IMP 107, Out all 112) due to cooling tower blowdown (CTBD) to the Yard Holding Pond (YHP) or Out all 101, lea age, and system maintenance acti ities (see Figure 2.1). Since the potential discharge o these chemicals is through the CTBD line, Final Supplemental En ironmental Impact Statement 49

Completion and Operation o Watts Bar Nuclear Plant Unit 2 Out all 113 does not recei e these discharges. The summary o potential chemicals discharged by NPDES out all number is shown in Table 3-10.

Table 3-1 . Potential Chemical Discharge to PD S Outfalls at W Outfall Outfall Descri tion Chemical umber Ammonium Hydro ide, Ammonium Chloride, Alpha Cellulose, Boric Acid, Sodium Tetraborate, Bromine, Chlorine, Copolymer Dispersant, Ethylene Glycol, Hydrazine, Laboratory Chemical Wastes, Lithium, Molybdate, Monoethanolamine, 101 Di user Discharge Molluscicide H150M, Oil and Grease, Phosphates, Phosphate Cleaning Agents, Paint Compounds, Sodium Hydro ide, Sur actant -

Dimethylamide and Alcohol, Tolyltriazole, Zinc Sul ate, Zinc Acetate Dihydrate, LCS-60 102 YHP O er low Weir Alternate discharge path or Out all 101 Ammonium Hydro ide, Ammonium Chloride, Boric Acid, Sodium Tetraborate, Bromine, Chlorine, Copolymer Dispersant, Ethylene Glycol, Hydrazine, Laboratory Chemical Wastes, 103 LVWTP Molybdate, Monoethanolamine, Molluscicide H150M, Oil and Grease, Phosphates, Phosphate Cleaning Agents, Paint Compounds, Sodium Hydro ide, Sur actant - Dimethylamide and Alcohol, Tolyltriazole, Zinc Sul ate Metals - Iron and Copper, Acids and Caustics, Ammonium Hydro ide, Ammonium Chloride, Boric Acid, Sodium Tetraborate, Bromine, Chlorine, Copolymer Dispersant,Hydrazine, Laboratory Chemical Wastes, Molybdate, 107 LP and ULP Monoethanolamine, Molluscicide H150M, Oil and Grease, Phosphates, Phosphate Cleaning Agents, Sodium, Sodium Hydro ide, Sur actant -

Dimethylamide and Alcohol, Tolyltriazole, Zinc Sul ate Sewage Treatment Chlorine, Organic Matter, Laboratory Chemical 111 Plant Wastes, Paint Compounds Chlorine, Organic Matter, Paint Compounds, Potable Water (Cooling Tower at Training 112 Runo Holding Pond Center), High Pressure Fire Protection lushes, Superior SWS 4550 Primary System Chemical Additions The 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 hydro ide is added to the RCS ia components in the Au iliary Building to establish the initial pH and corrosion control. A ter 50 Final Supplemental En ironmental Impact Statement

Chapter 3 the reactor becomes critical, lithium is a byproduct o a neutron-boron reaction and no urther lithium hydro ide additions are re uired. 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 appro imately one month a ter restart rom a re ueling outage.

For appro imately the ne t month the concentration is increased and then o er the course o the operating cycle the concentration steadily decreases. Hydrogen pero ide is added during a re ueling outage to enhance primary system cleanup to reduce radiation e posure to maintenance personnel and ensure water clarity. Hydrazine is added stoichiometrically prior to heat-up rom a re ueling outage to sca enge o ygen and minimize system corrosion. The RCS is a closed system, there ore any lea age or letdown rom the RCS system would be processed through the li uid radiological waste system.

WBN recei ed state appro al in October 2006 to add low concentrations o Zinc Acetate Dihydrate to the RCS. Industry e perience has shown zinc additions yield a 20 to 30 percent reduction in plant dose rates and reduce primary water stress corrosion crac ing in plant materials. Zinc would also reduce the corrosion rate and release o corrosion products to the coolant rom the metal sur aces o replacement or new steam generators. WBN initiated in ection at 20 grams per day ia components in the Au iliary Building and maintained this eed rate until a zinc residual was obser ed 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 lea age or letdown rom the RCS system would be processed through the li uid 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 2006 Present RCS1 Dihydrate Training Center Superior SWS 4550 2006 Present Cooling Tower 1

RCS = Reactor Coolant System odium molybdate, tolyltriazole, sodium hydro ide are added to this system in the Au iliary Building to control pH and corrosion. Lea age 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 E uipment 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 pac ages. Lea age with concentrations less than10 percent is discharged to the ULP or degradation, while greater than or e ual to 10 percent is collected in drums and shipped to a endor to be recycled.

Final Supplemental En ironmental Impact Statement 51

Completion and Operation o Watts Bar Nuclear Plant Unit 2 Secondary System Chemical Additions The 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 recei es e hausted steam rom the turbine discharge to repeat the cycle.

Hydrazine, ammonia, ammonia chloride, boric acid, and monoethanolamine (ETA) are in ected into the Condensate System at the turbine building or secondary chemistry control. Hydrazine unctions as a dissol ed o ygen sca enger while ammonia and ETA are added or pH control and corrosion control. Ammonia chloride is in ected as necessary or molar ratio control to aid in reduction o stress corrosion crac ing in the steam generators. Boric acid is also in ected at the turbine building or reduction or pre ention o stress corrosion crac ing in the steam generators. The reduction o stress corrosion crac ing assists in the maintenance o steam generator integrity thereby realizing their design li espan. Up to 300 pounds o modi ied alpha cellulose may be added to the condenser inta e channel to temporarily plug pinhole tube lea s in the condenser.

Other Plant Systems Chemicals are also added to other plant systems and include Chilled Water Systems, Turbine Building Heating System, Au iliary Boilers, and Diesel ac et Cooling Systems.

x Hydrazine and ammonia are added to the Chilled Water Systems, Turbine Building Heating System, and Au iliary Boilers or pH and corrosion control x LCS-60 is added to the diesel ac et 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 lea age or maintenance acti ities 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 Out all 112.

n ironmental Consequences of Chemical Additions to Ra Water Under the pre erred alternati e, TVA would complete the construction o WBN Unit 2 and the plant would operate at its ull capacity as originally designed. Prior to construction acti ity, WBN would de elop an erosion and sedimentation control plan as part o an application or a General NPDES Permit or Storm Water Discharges Associated with Construction Acti ity although it is e pected that most o the construction wor would occur inside constructed buildings, and all o the wor is e pected to occur within the e isting plant site ootprint. Operation o Unit 2 along with Unit 1 would result in an increase o raw water inta e 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 additi es by an estimated 33 percent. This increase is within original design basis or operation o Units 1 and 2. Since an additional e isting cooling tower would be placed in ser ice, Towerbrom 960 treatment or CCW treatment would increase by an estimated 100 percent.

52 Final Supplemental En ironmental Impact Statement

Chapter 3 The current NPDES permit contains pro isions re uiring authorization o the B/CTP and the use o the water treatment chemicals described abo e are e pected 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, deto i ication o non-o idizing biocides would be con irmed with twice-daily sampling or the acti e ingredient in the e luent during the treatment period.

The state retains the authority to re uire WBN to conduct additional monitoring to ensure that Unit 2 operation does not ha e an ad erse a ect on NPDES e luent limitations or other permit conditions. In the e ent the state determines that additional monitoring should be conducted, the results would need to be e aluated and submitted to the state per the conditions set orth. Potential changes in plant discharges are not e pected to be signi icant as compliance with applicable regulatory sa eguards and internal assessments would ensure that resulting e ects to water uality are insigni icant.

3.1.3.

The 1995 FSER updated the groundwater in ormation in the 1972 FES, and the descripti e in ormation about groundwater systems in the icinity o WBN pro ided in that update is still accurate. In August 2002, tritium was detected in one o the on-site en ironmental monitoring locations at le els that were ust at the detectable le el. At that time, TVA noti ied the NRC and State o Tennessee en ironmental and radiological representati es.

To address this issue, in December 2002, TVA installed our new en ironmental monitoring locations on the plant site as a modi ication to the Radiological En ironmental Monitoring Program. Since that time TVA has been closely monitoring in-ground tritium and reporting these results in the WBN Annual Radiological En ironmental Operating Reports to NRC and the state o Tennessee.

Samples ta en anuary 2003 through December 2004 indicated the presence o low le els o tritium in three o the our monitoring locations, which are maintained or en ironmental monitoring purposes only. The sources o this tritium were lea age rom an underground radioacti e e luent piping and lea age rom a bellows or the Unit 2 uel trans er tube. In order to stop the tritium ingress into the groundwater, the radioacti e e luent piping was replaced with a new 4-inch pipe. In addition, the Unit 2 uel trans er tube was sealed, and the uel trans er canal was coated. These acti ities were completed by No ember 2005.

Results rom two o the new indi idual sample locations, ta en in February 2005 and une 2005, were greater than the NRC 30-day reporting le el o 30,000 picocuries per liter (pCi/L). Further inspections re ealed no lea age in underground radioacti e e luent piping.

TVA s in estigation determined that the source o the increased tritium le els was a result o the pre ious e luent piping lea , which had been repaired. The highest amount o tritium detected was appro imately 550,000 pCi/L.

Some residual tritium will remain in the groundwater until the tritium either decays or is diluted. E entually, this groundwater will migrate into the ri er where these degraded tritium le els will be e en urther reduced and there ore pose no public health hazard. TVA continues to monitor wells monthly to eri y 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.

Final Supplemental En ironmental Impact Statement 53

Completion and Operation o Watts Bar Nuclear Plant Unit 2 3.2. Aquatic cology The characteristics o the WBN site s a uatic en ironment and biota were described in the 1972 FES (TVA 1972) with updated in ormation described in the NRC 1995 FES (NRC 1995a) and the TVA 1998 FEA or the WBN SCCW Pro ect (TVA 1998a). This in ormation was based on site-speci ic data combined with general nowledge o Tennessee Ri er tailwater habitats and associated a uatic biota. E tensi e supplemental in ormation speci ic to WBN is a ailable rom reports detailing results o the TVA Vital Signs Monitoring Program (TVA, unpublished data). These cited reports and data were e amined and determined to continue to represent current en ironmental conditions ade uately in the Watts Bar Dam tailwaters and upper Chic amauga Reser oir. They were used or the present FSEIS as a basis or a re iew o the a uatic ecology in the icinity o the WBN site.

Plan ton Recent studies indicate that the ma ority o plan tonic organisms (including ish eggs, lar al ish, microin ertebrates, algae, etc.) in the icinity o WBN originate in the Watts Bar Reser oir and pass through the turbines at Watts Bar Dam. Plan ton density aries greatly rom day to day. Sampling sur eys (1973-1985) indicate that plan ton populations decreased rapidly as distance rom Watts Bar Dam increased due to the swi t- lowing, ri erine nature o the upper portions o Chic amauga Reser oir. As water enters the reser oir pool o Chic amauga Reser oir (25-30 miles downstream o WBN), elocities decrease and plan ton densities gradually increase to le els comparable to those in the Watts Bar Dam orebay (TVA 1986).

Though there are no data on phytoplan ton densities in the icinity o the WBN site, comparisons between preoperational (1976-1985) and operational (1996-1997) densities o ish eggs and lar al ish show similar patterns (Appendi C, Table C-1) (TVA 1998d). An entrainment study conducted during the spring and summer o 1975 estimated the a erage loss o ish lar ae in the icinity o WBF as a result o water di ersion to the plant was 0.24 percent o the total population (TVA 1976b).

In the TVA FEA or the SSCW, TVA e aluated one-unit operation and concluded that the proposed pro ect would result in loss o ish eggs and lar ae through entrainment at appro imately the same rate as pre iously studied in 1976 (TVA 1998a). Similar results were reported in the 2001 ish monitoring program or the SCCW and it was concluded that no signi icant impact to ichthyoplan ton populations rom WBN SCCW operation would occur (Ba ter et al. 2001). These entrainment rates indicate the operation o both WBN Unit 1 and Unit 2 would ha e little or no e ect on lar al ish and egg populations in Chic amauga Reser oir because the WBN condenser cooling water system (CCW) is commensurate with a closed cycle cooling system.

n asi e and onin asi e Aquatic Plants A uatic plants present in Chic amauga Reser oir include the in asi e species Eurasian water mil oil ( ), spinylea naiad ( ), and the nati e southern naiad ( ) (TVA 1994a). E cessi e a uatic plant co erage can cause reser oir use con licts in areas around industrial water inta es, public access and recreation sites, and la eshore de elopments. These e ects ha e not been seen in the icinity o WBN because the WBN site is located in the ri erine tailwater area o the reser oir downstream o Watts Bar Dam. A uatic plants ha e di iculty establishing dense growths in this area e en during years o pea co erage due to current elocity. As a result, a uatic plant densities in the reser oir near WBN ha e not reached nuisance le els, and no control measures ha e been ta en in the icinity o the plant. Pea a uatic plant 54 Final Supplemental En ironmental Impact Statement

Chapter 3 co erage in Chic amauga Reser oir occurs in shallow, o erban la eli e habitat ar downstream o WBN. Combined operation o WBN Units 1 and 2 would not ha e e ects on the occurrence o in asi e or nonin asi e a uatic plants.

Aquatic Communities Be ore 1978, isheries biologists thought the tailwaters o Watts Bar Dam contained a orable spawning habitat or se eral species including sauger ( ),

smallmouth bass ( ), white bass ( ) and possibly yellow perch ( ). Howe er, the e aluation o in ormation in the 1978 NRC FES discounted this theory. Since 1978, additional studies ha e con irmed that the reach between the Watts Bar Dam and the WBN site is a staging area, not an area o signi icant spawning acti ity or these species (NRC 1995a).

TVA began a program to systematically monitor the ecological conditions o its reser oirs in 1990, though no samples were ta en on the Watts Bar or Chic amauga Reser oirs until 1993. Pre iously, reser oir studies had been con ined to assessments to meet speci ic needs as they arose. Reser oir (and stream) monitoring programs were combined with TVA s ish tissue and bacteriological studies to orm an integrated Vital Signs Monitoring Program. Part o the monitoring consisted o the reser oir 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 relati ely constant with an a erage 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 reser oirs (including upstream in low areas such as that around WBN). The tailwaters o Watts Bar Dam support a ariety o benthic organisms including se eral 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 e tending 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 relati ely constant. The ri erine tailwater reach downstream o Watts Bar Dam and WBN rated good in 2001 and the rating has increased to e cellent in 2003-2005 (Appendi C, Tables C-4 and C-5).

Under the proposed action, no construction acti ities would occur within 500 eet o the reser oir, and all construction acti ities would be sub ect to appropriate BMPs to ensure that there are no impacts to sur ace water uality. NPDES discharge limits as outlined in the 1995 NRC FES and in this document would not be re ised. No discharges e ceeding current NPDES limits would occur during operation o WBN Units 1 and 2. The amount o cooling water re uired or operation o both WBN Unit 1 and WBN Unit 2 would result in increases in cooling water inta e and discharge olumes, but thermal discharge rates would remain below ma imum allowed le els 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 e ect on a uatic animals or their habitats in the icinity o WBN. Because inta e lows would not be increased abo e le els outlined in the 1978 NRC FES, ish entrainment rates would not e ceed ma imum le els pre iously e aluated in that FES or operation o both WBN Units 1 and 2.

Final Supplemental En ironmental Impact Statement 55

Completion and Operation o Watts Bar Nuclear Plant Unit 2 n asi e 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 Chic amauga Reser oir. Subse uently, the zebra mussel ( ) has become established in the Watts Bar Dam tailwater area. The plan tonic lar ae o zebra mussels can be drawn into raw-water piping systems, and attach to pipe sur aces. Multiple layers o adult zebra mussels can accumulate resulting in partial to total bloc age o pipes and grates. This can cause damage to pipes and acilities re uiring acility outage time to remo e the bloc age.

Currently, WBN has implemented the use o Clamtrol (WBN uses H150M), a nono idizing molluscide, within the acility to inhibit bio ouling by Asiatic clams and zebra mussels.

Howe er, this control method is restricted to the acility itsel and concentrations o molluscide released into the reser oir are too low to ha e any e ect on nati e mussel beds (NRC 1995a).

3.3. Terrestrial cology 3.3.1.

The terrestrial plant communities were assessed during the initial en ironmental re iew or the construction o WBN Units 1 and 2 (TVA 1972). Ma or 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 re uency, density, basal area and olume or all tree species occurring on the Watts Bar reser ation are presented. In the 1976 En ironmental In ormation Report or WBN Units 1 and 2, the ma or community types are listed as oa -hic ory 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 identi ied or building WBN, 210 wooded acres were to remain undisturbed (appro imately 80 percent o the e isting woodlands).

More than 70 percent o the plant area was already disturbed in the orm o culti ated or old ields.

The terrestrial plant communities o the WBN site ha e changed ery little o er the past 34 years. The ma ority o the pro ect area (o er 70 percent) is composed o herbaceous egetation types ound in old ields, gra el par ing areas, roadside rights-o -way and arious other disturbed sites. Appro imately 30 percent o the site is still orested with the ollowing orested egetation classes deciduous orest and e ergreen-deciduous orest.

The deciduous orest can be characterized as two separate community types, oa -hic ory orest and bottomland hardwood orest. In asi e species including apanese stilt grass, apanese honeysuc le, multi lora rose, and Russian oli e occur on WBN Reser ation.

Some disturbance o e isting plant communities may occur i construction o WBN Unit 2 recommences although most construction acti ities are e pected to occur in already constructed buildings or within the pre iously 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 e pected to be insigni icant as a result o the proposed actions. No new in estations o e otic in asi e plant species are e pected as a result o the Action Alternati e.

56 Final Supplemental En ironmental Impact Statement

Chapter 3 3.3.2. W The terrestrial ecology at the WBN acility has changed little rom those described in earlier en ironmental re iews. Habitats surrounding the acilities consist o mowed grass, ields o short egetation, and ditches that are intermittently wet. The pro ect site, which is highly de eloped, includes par ing areas and ball ields in addition to these habitats.

Wildli e using these areas, primarily ad acent to the disturbed area ootprint, include locally abundant species that are tolerant o human acti ity and highly modi ied habitats. Species such as eastern meadowlar , American gold inch, eastern bluebird, and song sparrow were obser ed at or ad acent to the proposed pro ect site. Spotted sandpiper and illdeer were obser ed in or near the settling ponds at the acility most o these ponds are lined with riprap and pro ide poor habitat or shorebirds. Howe er, 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 obser ed on a nearby structure.

Due to the o erall lac o wildli e habitat at the pro ect site and the limited amount o additional habitat disturbance anticipated, the proposed pro ect is not e pected to result in ad erse impacts to terrestrial animal resources within the disturbed area ootprint (Figure 1-2) or in the ad acent areas. Wildli e in the pro ect area is locally abundant and no rare or uncommon habitats e ist at the site.

3. . Threatened and ndangered S ecies As discussed in Sections 3.2 and 3.3, most o the a uatic and site disturbance re uired or completion o WBN Unit 2 has already occurred. The ollowing sections pro ide 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 muc et, 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 e tending 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 relati e to WBN.

The snail darter, ederally listed as threatened, is also nown to occur occasionally in this reach o the Tennessee Ri er. The ma ority o the snail darter population in the area is con ined to Sewee Cree , a tributary to the Tennessee Ri er, which enters the ri er at TRM 524.6.

The lar ae o snail darters are pelagic and can dri t substantial distances (miles) during early li e stages. Spawning o snail darters has not been documented in the main stem o the Tennessee Ri er downstream o Watts Bar Dam, and no snail darter lar ae ha e been collected during entrainment sampling.

Two mussel species considered sensiti e by the State o Tennessee pyramid pigtoe and Tennessee clubshell, and one state-listed threatened ish species blue suc er, are also nown rom this reach o the Tennessee Ri er (Appendi C, Table C-6).

Final Supplemental En ironmental Impact Statement 57

Completion and Operation o Watts Bar Nuclear Plant Unit 2 Figure 3- . Location of ussel Sanctuary in Chic amauga Reser oir elo Watts ar Dam 58 Final Supplemental En ironmental Impact Statement

Chapter 3 Under the proposed action, wor would be conducted on WBN Unit 2 in order to bring it to ull operational capacity. No construction acti ities would occur within 500 eet o the reser oir, and all construction acti ities would be sub ect to appropriate BMPs to ensure that there are no impacts to sur ace water uality. NPDES discharge limits as outlined in the 1995 NRC FES would not be re ised. No discharges e ceeding current NPDES limits would occur during operation o WBN Units 1 and 2. The amount o cooling water re uired or operation o both WBN Unit 1 and WBN Unit 2 would result in increases in cooling water inta e and discharge olumes up to the original two-unit design. Thermal discharge rates would remain below ma imum allowed le els outlined in the 1978 NRC FES.

The steam generator blowdown (SGDB) contains low le els o ammonia, which is in ected 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 ma imum SGBD discharge or Units 1 and 2 would be 524 gallons per minute (gpm) through the di users at out all 101 and would re uire 3500 c s o minimum ri er low. Based on the hydrothermal analysis in Section 3.1 and pre ious di user studies (Had erioua, et.al. 2003), in the worst case conditions, ammonia concentrations would be ully mi ed prior to reaching the stream bottom in the 240-eet wide by 240- eet-long assigned mi ing zone. SGDB is di erted to the yard holding pond with cooling tower blowdown when the minimum ri er low o 3500 c s is not a ailable, unless it has already been di erted to the condensate system. When the minimum ri er low o 3500 c s is a ailable, the YHP discharges through out all 101. The YHP has an emergency o er low that discharges through out all 102. In general, the operation o Watts Bar Dam and the WBN blowdown system are ery care ully coordinated so that there are no une pected o er lows rom the yard holding pond. (see Section 2.2.2). No e ents with o er low rom the YHP occurred during the hydrothermal analysis described in Section 3.1, there ore under operating conditions, releases rom Out all 102 are not e pected. There ore, there would be no e ect 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 e ect on state-listed or ederally listed a uatic animals or their habitats in the icinity o WBN. Because inta e lows would not be increased abo e le els outlined in the 1978 NRC FES, ish entrainment rates would not e ceed ma imum le els pre iously e aluated in that FES or operation o both WBN Units 1 and

2. Because snail darter lar ae ha e not been encountered in entrainment sampling at WBN, there is no potential or snail darter lar ae to be entrained at the cooling water inta e or WBN e en under the increased withdrawal rates re uired to support operation o both WBN Units 1 and 2.

3.4.2.

Historically, one plant species, spider lily, (now ), was identi ied 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 gi en any special status within the state o Tennessee. In addition, ield sur eys 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 sensiti e plant species or habitat to support these species were ound during ield re iews (TVA 2005a).

Final Supplemental En ironmental Impact Statement 59

Completion and Operation o Watts Bar Nuclear Plant Unit 2 The 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 S ecies Re orted From Within 5 iles of the Pro osed Pro ect in Rhea County, Tennessee State Common ame Scientific ame Status Ran Appalachian bugbane THR (S3)

Hea y sedge SPCO (S1)

Northern bush honeysuc le THR (S2)

Prairie goldenrod END (S1S2)

Slender blazing star THR (S2)

Spreading alse o glo e THR (S3)

Status abbre iations 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 ad acent to the area to be disturbed under the proposed Action Alternati e. There ore, no impacts to sensiti e plant species are e pected.

3.4.3. W Earlier re iews indicated that ederally listed as threatened or endangered gray bats (

) and bald eagles ( ) were reported within 5 miles o the pro ect. Small numbers (less than 500) o gray bats continue to roost in a ca e appro imately 3.3 miles rom the pro ect. Bald eagles nest on Chic amauga and Watts Bar Reser oirs appro imately 1.8 and 4.7 miles, respecti ely, rom the pro ect site. Gray bats and bald eagles orage o er the Tennessee Ri er in the icinity.

Se eral heron colonies ha e been reported rom the icinity since the late 1980s. Many o these colonies were destroyed during recent pine beetle in estations. The closest acti e colony is located 4 miles north o WBN.

Hellbenders ( ), listed as in need o management by the State o Tennessee, ha e been reported rom the upper reaches o Sewee Cree , appro imately 2.5 miles rom the pro ect site. The species may continue to inhabit streams in the icinity.

Completion o WBN Unit 2 is not e pected to result in impacts to any ederally listed or state listed as threatened or endangered species o terrestrial animals or their habitats. No suitable habitat or gray bats or bald eagles e ists on or ad acent to the pro ect site. Construction and operation o WBN Unit 2 would not result in impacts to bald eagles and gray bats in the region.

60 Final Supplemental En ironmental Impact Statement

Chapter 3 3.5. Wetlands Wetland communities were assessed during the initial en ironmental re iew 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 ha e de eloped 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 sur ey or wetlands conducted on October 30, 2006, indicated a orested wetland is present ad acent to the pro ect ootprint. This wetland is associated with an unnamed stream between the road and the rail line ust outside o the northeast corner o the pro ect ootprint.

The area is appro imately 1 acre in size dominant egetation includes tag alder, sycamore, and blac willow. The remainder o the site is composed o upland plant communities, gra el par ing areas, and de eloped areas.

Since there are no plans to disturb the abo e-mentioned orested wetland, no impacts to wetlands would occur as the result o construction acti ities related to the completion o WBN Unit 2. I pro ect plans are modi ied and impacts to this wetland are una oidable, mitigation may be re uired as a condition o state and/or ederal wetland protection regulations (Section 404, Clean Water Act, and A uatic 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 .

O erall impacts to wetlands in the pro ect area would be insigni icant 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 en ironmental impact on natural areas within 3 miles o WBN are assessed below or the purpose o updating pre ious documentation to current conditions.

Three o i e natural areas currently listed in the Natural Heritage database and within 3 miles o WBN were re iewed in pre ious documents. These areas are Yellow Cree unit o the Chic amauga State Wildli e Management Area (WMA), the Chic amauga Reser oir State Mussel Sanctuary, and the Chic amauga Shoreline TVA Habitat Protection Area (HPA). TVA 1998a ound no direct or indirect e ects to Yellow Cree WMA or the TVA HPA. NRC 1995b, which re iewed the 1978 NRC FES, noted no signi icant changes in, and there ore no signi icant impacts to, the a uatic en ironment in the icinity o WBN. Additionally, no impacts to the mussel sanctuary (an area designated by the State o Tennessee to be a biological preser e or mussel species) are anticipated rom the proposed action (Stephanie Chance, TVA, personal communication, No ember 14, 2006). No signi icant changes in area or management ob ecti es o the WMA and TVA HPA ha e occurred since they were last re iewed, and there ore, 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 appro imately 1.5 miles north o the site, and Yuchi Wildli e Re uge at Smith Bend, a 2600-acre ha en or migratory water owl and shorebirds. This re uge, managed by the Tennessee Wildli e Resources Agency, is appro imately 2.2 miles south o the site. The Final Supplemental En ironmental Impact Statement 61

Completion and Operation o Watts Bar Nuclear Plant Unit 2 distance rom the site to these two areas is su icient such that no direct or indirect impacts are anticipated.

3. . Cultural Resources As part o the e tensi e history o en ironmental re iew o constructing and operating WBN, TVA has considered the potential impact on historic and archaeological resources associated with each underta ing. It was determined during the initial en ironmental re iew that two archaeological sites (40RH6 and 40RH7) would be ad ersely a ected by construction o the plant. Based on this inding, TVA proceeded with data reco ery o these sites (Calabrese 1976 Schroedl 1978). One historic cemetery (Leuty Cemetery) was located on the property prior to plant construction. Two gra es were remo ed in 1974 and placed in Ewing Cemetery.

Subse uent en ironmental re iews conducted resulted in a no-e ect inding or archaeological resources. In the 1998 re iew o the WBN SCCW pro ect (TVA 1998a), TVA determined that WBF was eligible or listing on the National Register o Historic Places (NRHP). Howe er, it was determined that this property would not be ad ersely a ected.

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 sur ey in 1936.

The latter was recorded later during a post-inundation Chic amauga Reser oir shoreline sur ey.

While a portion o these sites was e ca ated, the sites remain eligible or listing on the NRHP with a potential or signi icant archaeological deposits and eatures to be present. Sites 40RH8 and 40RH64 are both considered potentially eligible or listing on the NRHP. While a reconnaissance sur ey was conducted on the plant property prior to its construction, archaeological sur ey techni ues ha e signi icantly impro ed since that time. Based on what we already now, undisturbed areas outside the current pro ect s area o potential e ect (APE) ha e a high potential or archaeological resources to be present. Any uture ground-disturbing acti ity in these areas would ha e to be re iewed.

A ma ority o the APE or this pro ect has been e tensi ely disturbed. Completing WBN Unit 2 would result in some additional ground-disturbing acti ities but largely would be restricted to the e isting disturbed portion o the plant property. A ield isit conducted con irmed the prior disturbance in these areas. Pro ect plans submitted include a larger ootprint surrounding the plant that has been identi ied as the disturbance area. A portion o this ootprint east o the cooling towers (the a oidance area shown on Figure 3-5) includes parts o archaeological site 40RH6 and it is un nown i this site contains signi icant archaeological deposits. Although this site is within the area identi ied as potentially to be disturbed, current plans actually would not disturb it. I those plans change and this area would be disturbed, an archaeological sur ey o the a ected area would be conducted to determine the signi icance o the site and i determined to be archaeologically signi icant, appropriate measures would be ta en to a oid ad ersely impacting identi ied resources. This would include coordination with the SHPO.

62 Final Supplemental En ironmental Impact Statement

Chapter 3 Figure 3-5. Archaeological A oidance Area Within the Area of Potential ffect Final Supplemental En ironmental Impact Statement 63

Completion and Operation o Watts Bar Nuclear Plant Unit 2 As planned, archaeological resources within the APE at WBN should not be ad ersely a ected by this action. TVA is coordinating with the SHPO or concurrence with this inding.

3. . Socioeconomic, n ironmental 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 ri er, were both slow growing, with a total net population growth o 400 between 1960 and 1970. This in ormation was updated and e panded or the 1978 NRC FES. While the 1972 FES pro ected 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 pro ections o 10,770 within 10 miles and 950,461 within 50 miles.

In 1995, NRC and TVA pro ided estimates or 1990 and pro ections 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. Pro ections 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 pro ected. Based on these trends, the population in 2040 is pro ected to be about 29,300 within 10 miles and 1,519,000 within 50 miles, a much higher growth rate than in earlier pro ections.

Since the earlier reports were prepared both Rhea and Meigs Counties, as well as most o the surrounding counties, ha e 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 e perienced 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 Ri er, 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 speci ically in Rhea and Meigs Counties, but at a somewhat slower rate than during the 1990s.

During construction, population would increase due to the in lu o wor ers. At pea construction employment, the total construction and design employment could be as high as 3000 howe er, many o these are engineers, nonmanual cra t, and other wor ers who li ely would not relocate to the site. TVA is conducting a more detailed study o construction re uirements, which will pro ide a more precise estimate. For this analysis, a conser ati e estimate is made by assuming that the pea on-site wor orce would be 2200.

Based on pre ious e perience at the site, it is assumed that 40 percent o these would mo e into the area. Gi en this assumption, the total number o mo ers would be 880. The remaining 60 percent or more o the wor ers would either be local residents or would commute rom the surrounding area, including the Chattanooga and no ille areas.

Impacts o this increase in population should be similar to those described in the earlier documents re erenced abo e.

64 Final Supplemental En ironmental Impact Statement

Chapter 3 Based on e perience during construction at Unit 1 rom 1982 to 1986, about two-thirds o the in-mo ing wor ers would mo e into Rhea and Meigs Counties due to their pro imity 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 a ailability o housing or o sites or recreational ehicles (RVs) and trailers. The widespread distribution o the residential location o wor ers, including those who mo e into the area, would lessen the impacts.

O erall, this in lu should be similar to what occurred during the mid-1980s with earlier construction at the site, e cept that the number o wor ers is e pected 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 e periencing employment growth, in particular industrialization. The latest employment data suggest that these counties ha e been able to retain their industrial competiti e edge. While the nation, the state, and almost all o the counties within the 50 mile area around the plant e perienced substantial decreases in manu acturing 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 a erage 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. Pri ate employment other than arm and manu acturing generally had signi icant 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, howe er, are lower than the state and national a erages o 46.3 and 49.4 percent, respecti ely.

Much o the income recei ed by these wor ers on the WBN Unit 2 pro ect would be spent in the area, especially by those who mo e 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. A ter 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, respecti ely, o the total population. Within 10 miles o the site, the a erage 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 Ri er (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 a erages are well below the state a erage o 20.8 percent and the national a erage o 30.9 percent.

Final Supplemental En ironmental Impact Statement 65

Completion and Operation o Watts Bar Nuclear Plant Unit 2 According to the 2000 Census o Population, the po erty le el 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 po erty le el 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 po erty le el in Rhea County o 16.2 percent and in Meigs County, 17.5 percent gi en the con idence le els o the estimates, little or no change seems to be indicated since the 2000 Census. Po erty le els within the 10-mile area around the plant are slightly higher than both the state and national le els, with a po erty rate estimated to be about 15.1 percent among those who li e within 10 miles o the site and 11.8 percent within 50 miles. Based on the 2000 Census o Population, the po erty le el 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 po erty le el increased rom 237 to 282. In the area immediately across the ri er (Meigs County, Census Tract 9601, Bloc Group 2) the po erty le el is 21.7 percent. This was an increase rom 19.2 percent 10 years earlier and an increase in the number o persons below po erty rom 184 to 333.

Within the 10-mile area around the site, the po erty le el 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 po erty le els in the area around the site ha e been declining, as ha e the rates statewide and nationally, while the number o persons in po erty has continued to increase in some o the areas around the site as it has statewide and nationally. Howe er, the o erall po erty le el in the area is still abo e the state and national a erages and also abo e the le el or the 50-mile area around the site.

The low minority population share, along with the di used nature o potential negati e impacts, ma es it unli ely that there would be disproportionate impacts to minority or low-income populations. Howe er, such impacts are possible, particularly impacts arising rom housing needs and increased tra ic during the construction period. TVA would wor with local representati es and o icials to help reduce impacts rom these sources by pro iding more detailed in ormation about the anticipated wor orce. A mitigating action could be identi ication o the area as an impact area under the e isting state ta code (see Section 3.8.7). This would allow more o the ta e ui alent payments that TVA annually ma es to Tennessee to be allocated to these counties.

3.8.4. S Both Rhea and Meigs Counties ha e e perienced 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 e perienced a higher rate o increase than the state as a whole, which increased by 20.4 percent. This growth may result in more di iculty in inding sites or temporary housing, such as RVs and trailers. Howe er, the temporary in lu o wor ers 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 wor ers would be commuting rom their e isting homes in this area or slightly arther away, especially the Chattanooga and no ille areas. The result would be some increase in temporary housing needs, including apartments and acilities or trailers and RVs. To the e tent that the pattern rom construction in the 1980s is ollowed, Rhea and Meigs li ely would see 66 Final Supplemental En ironmental Impact Statement

Chapter 3 close to 600 temporary wor ers locating in those two counties o these, about three- ourths would bring amilies with them. At that time, amilies on the a erage had about 1.3 children, ma ing an a erage amily size o 3.3. Families, especially those with children, would be more li ely to loo or houses or apartments while wor ers mo ing alone may be more li ely to bring trailers or RVs with them or to rent trailers or small apartments. Many, especially those whose wor is li ely to continue through most o the construction period, are li ely 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 representati es and o icials to help reduce impacts by pro iding more detailed in ormation about the anticipated wor orce. A mitigating action could be identi ication o the area as an impact area under the e isting state ta code (see Section 3.8.7).

Community ser ices such as health ser ices, water and sewer, and ire and police protection would also be impacted. While Rhea and Meigs Counties li ely 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 pro ected to ha e no ad erse e ects. A ter construction is completed, there would be an increase o appro imately 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 abo e, Rhea and Meigs Counties most li ely would be the residential location o roughly two-thirds o the wor ers who mo e into the general area to wor at the site. I the location patterns and mo er characteristics o wor ers during construction o Unit 1 in the 1980s is ollowed, there would be an increase o appro imately 660 school-age children in the broader area around the site, o which an estimated 434 li ely would reside in Rhea and Meigs Counties. Total public school enrollment in these two counties is appro imately 6800. There is some capacity or certain grade le els in some o the schools. Howe er, the systems o erall are at or near capacity, and in some cases o er capacity, such as at Rhea County High School and in some lower grade le els in Rhea County. The schools in these counties ha e been e periencing a steady growth in enrollment or se eral years, and this growth is e pected to continue. Additional growth due to an in lu o construction wor ers would increase the o ercrowding already being e perienced. TVA would wor with local representati es and o icials to help reduce impacts by pro iding more detailed in ormation about the anticipated wor orce. A mitigating action could be identi ication o the area as an impact area under the e isting 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 signi icant 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 li ely to ha e a ma or impact on this trend, although it might accelerate it slightly. As discussed abo e, the number o construction wor ers and their amilies that would locate in the area during the construction period is e pected to be less than 2000.

Final Supplemental En ironmental Impact Statement 67

Completion and Operation o Watts Bar Nuclear Plant Unit 2 3.8.7. L R Under Section 13 o the TVA Act, TVA ma es ta e ui alent 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 go ernments. Payments to counties are based on relati e 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 e ui alent 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, there ore, increase ta e ui alent payments to the state. This increase would be distributed in part to local go ernments as described abo e, resulting in a small increase in payments to Rhea and Meigs Counties.

During construction, Tennessee law (Tennessee Code Annotated TCA , 67-9-101) pro ides or allocation o additional payments to impacted local go ernments rom the TVA ta e ui alent payments. These additional payments would be made to the local go ernments, 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 a terward. The actual amount paid would be determined by the state comptroller o the treasury, based on the pro isions o TCA 67 102(b). The additional payments rom state allocation o TVA ta e ui alent payments to these local go ernments during construction could be used to address some o the impacts on public ser ices discussed abo e.

In addition, there would be additional ta re enue associated with e penditures made in the area or materials associated with the proposed plant completion as well as sales ta re enue associated with purchases by indi iduals employed during construction and subse uently 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 wor ers employed at the site.

3.8.8. E No cumulati e socioeconomic e ects were identi ied in earlier WBN-related en ironmental re iews. The ma or change in the area s socioeconomic en ironment since those earlier documents were prepared is the more rapid population growth the area has seen and is e pected to continue to e perience, especially in the areas along the Tennessee Ri er 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 di erse and growing howe er, this growth has resulted in some impact to community ser ices, most notably in increased o ercrowding in certain public schools. The increase rom the in lu o wor ers 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 dra t land plan and dra t en ironmental impact statement (TVA 2005d) or Watts Bar Reser oir. TVA plans to issue an amended DEIS or the Watts Bar Reser oir Land Management Plan in the summer o 2007. In the e ent that nearby TVA land is allocated or industrial or recreational de elopment in the re ised land plan, potential cumulati e e ects rom subse uent de elopment in con unction with construction 68 Final Supplemental En ironmental Impact Statement

Chapter 3 or operation o WBN Unit 2 would be addressed when proposals or de elopment are re iewed.

The e tent o the impact o erall and on indi idual school systems and schools is largely dependent on where in-mo ing wor ers locate their residences. The recent growth that has occurred, along with the e pected continuation o this growth, could result in location patterns di erent in some ways rom the patterns associated with earlier construction at the site. For e ample, some o the in-coming wor ers might locate arther away rom the site than they would pre er. This could ha e the e ect o decreasing the number locating in Rhea and Meigs Counties, or parts o these counties, and increasing the number in some nearby counties. Impro ed roadways in the area, as contrasted to earlier construction periods, may also ma e location at greater distances relati ely more attracti e, increasing the tendency to locate arther rom the site. In addition to schools, other community ser ices could be impacted by the temporary in lu o construction wor ers in con unction with the current growth pattern. These impacts are li ely to be less noticeable than the school impacts. Additional road tra ic at pea times, gi en the combination o construction wor ers and the growth o permanent population, could cause a noticeable impact at some locations. There could also be noticeable impacts to other community ser ices such as medical acilities and public sa ety. The e tent o all these cumulati e impacts would depend greatly on the residential locations o the in-mo ing wor ers. As noted abo e, TVA is conducting a labor study, the results o which will be pro ided to o icials 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. . Flood lains 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 Sur ey is re iewing geologic and hydrologic data rele ant to WBN Units 1 and 2, as supplied by TVA in a preliminary sa ety analysis report (PSAR) to the AEC. This re iew pertains to geologic and hydrologic aspects o the site such as earth ua e e ects, 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 in ormation related to potential looding o the Watts Bar site rom the Tennessee Ri er and local probable ma imum precipitation4 (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 Chic amauga Reser oir between TRM 528.0 and 528.6 in Rhea County, Tennessee. The area potentially impacted by this pro ect would e tend rom about TRM 528.4 to 529.0. The proposed pro ect area could possibly be looded rom the Tennessee Ri er and local PMP site drainage.

4 The Probable Ma imum Precipitation is de ined as the theoretically greatest depth o precipitation or a gi en duration that is physically possible o er 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 interrelationships in storms, PMP alues are identi ied as estimates.

Final Supplemental En ironmental Impact Statement 69

Completion and Operation o Watts Bar Nuclear Plant Unit 2 The 100-year loodplain or the Tennessee Ri er would be the area below ele ation 697.3 eet abo e mean sea le el (msl) at TRM 528.4 and ele ation 697.6- eet msl at TRM 529.0.

The Tennessee Ri er TVA lood ris pro ile (FRP) ele ation would be ele ation 701.1- eet msl at TRM 528.4 and 701.4 at TRM 529.0. The FRP is used to control residential and commercial de elopment on TVA lands and lood damageable de elopment or TVA pro ects. In this area, the FRP ele ations are e ual to the 500-year lood ele ations.

Under current conditions, the estimated Tennessee Ri er Probable Ma imum Flood5 (PMF) le el would be ele ation 734.9- eet msl at WBN. Conse uent wa e run-up abo e the lood le el would be 2.0 eet, which would produce a ma imum lood le el o ele ation 736.9- eet msl (TVA 2004d). Based on site topography, much o the proposed pro ect area would be inundated at this ele ation. It has pre iously been determined that the critical ele ation or PMP site drainage should be no higher than ele ation 729.0- eet msl.

The loodplains and lood ris assessment in ol es ensuring that acilities would be sited to pro ide a reasonable le el o protection rom looding. In doing this, the re uirements o E ecuti e Order 11988 (Floodplain Management) would be ul illed. Due to the act that the proposed pro ect could potentially impact lood ele ations at se eral buildings at a nuclear generating acility, the NRC re uires a lood ris e aluation o possible impacts rom the PMF and PMP site drainage or all alternati es.

The ollowing proposed acti ities 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 cra t trailers would be added and temporary par ing and laydown areas would be de eloped. All proposed acilities would be located outside the limits o the Tennessee Ri er 100- and 500-year loodplains, but many o the proposed structures would be located on ground below the Tennessee Ri er PMF ele ation o 734.9- eet msl. For those structures located below the Tennessee Ri er PMF, an acceptable le el o lood ris would be pro ided because the probability o looding would be e tremely low, and looding o these structures would not impact the sa e operation o the plant. None o the proposed acti ities would result in changes to the Tennessee Ri er PMF ele ation.

All e isting sa ety-related acilities, systems, and e uipment are housed in structures that would pro ide protection rom looding or all lood conditions up to plant grade at ele ation 728- eet msl. Other rain all loods would e ceed plant grade ele ation 728- eet msl and re uire plant shutdown. Howe er, lood warning criteria and orecasting techni ues ha e been de eloped to assure that there will always be ade uate time to shut the plant down and be ready or loodwaters abo e plant grade (TVA 2004d).

The placement o temporary and permanent structures both inside and outside the security ence would be re uired to complete Unit 2. The tentati e 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 Ma imum Flood is de ined as the most se ere 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 se uence o related meteorologic and hydrologic actors typical o e treme storms.

70 Final Supplemental En ironmental Impact Statement

Chapter 3 security ence. These structures would not be located within critical areas or PMP site drainage and would not ad ersely impact PMP site drainage ele ations.

The new multipurpose building (28) and temporary cra t trailers (29) are both within the area de ined as Area East o Main Plant in the site drainage calculation that were de eloped or the Watts Bar FSAR (TVA 2004d). The original site analysis determined the ele ation resulting rom the site PMP would be less than the critical ele ation 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 cra t trailers (29) are being designed not to e ceed the ootprint o the buildings that ha e been remo ed rom this area (Richard ing, TVA, personal communication, December 2006). There ore, the new structures would not impact pre iously determined PMP ele ations. The proposed new construction access acility (31) would be located ad acent to the e isting control building and au iliary (reactor) building and would not impact lood ele ations. The temporary outage building (33) would not be an obstruction as shown on the current site plan.

Construction o the temporary par ing areas (3) could result in minor changes to the e isting topography, but PMP drainage rom these areas does not low toward the plant and, there ore, no ad erse impacts would be e pected. 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 par ing should be designated as a no par ing area. This area is located within the PMP drainage ditch and any cars par ed in the area could ad ersely impact PMP drainage ele ations. Although there is no indication that de elopment would ta e place in the switchyard area (30), this area has been identi ied as critical or PMP drainage.

There ore, any structural modi ications that are proposed in the switchyard should be re iewed prior to construction to ensure they would not ad ersely impact PMP drainage ele ations.

Based on the current design and site plan, the proposed pro ect would be consistent with E ecuti e Order 11988, and there would be no anticipated ad erse lood-related impacts.

Any changes to the tentati e site plan would be re iewed to determine the potential or lood related impacts.

3.1 . Seismic ffects The 1972 FES described the ma imum historical Modi ied Mercalli Intensity (a scale o earth ua e e ects that ranges rom Roman numeral I through XII) e perienced at WBN rom local ua es and the origins o this ground motion. The 1995 FSER described the sa e shutdown earth ua e or WBN and its basis and discussed seismic analyses o WBN using a site-speci ic earth ua e model and a re iew le el earth ua e (TVA 1995b). The WBN FSAR (TVA 2004d) pro ides 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 re uire updating. First, the largest earth ua e in the southern Appalachians since the 1972 FES is now the April 29, 2003, Fort Payne, Alabama, earth ua e, which had a moment magnitude o 4.6 and Nuttli body wa e magnitude o 4.9.

The Fort Payne earth ua e s magnitude is still lower than the design basis earth ua e, which has a body wa e magnitude o 5.8 there ore, the occurrence o the 2003 Fort Payne earth ua e has no signi icant impact on pre ious indings.

Final Supplemental En ironmental Impact Statement 71

Completion and Operation o Watts Bar Nuclear Plant Unit 2 Second, preliminary results o the Indi idual Plant E amination or E ternal E ents (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 e amination o seismic e ects and concluded that the seismic capacity o WBN or a Re iew Le el Earth ua e e ceeds 0.3g6, the minimum le el re uired by NRC. There ore, no seismic design change recommendations resulted rom the IPEEE seismic e aluation.

3.11. Climatology and eteorology The 1972 FES contains a discussion o the climatology and meteorology or the Watts Bar site. The 1995 FSER pro ides a description o the Watts Bar on-site meteorological program and a re iew o the pre ious discussion. The conclusion was that the regional climate description in the 1972 FES remained alid. Some o the in ormation was updated based on more recent data. It also concluded that the 20-year data period update (1974-1993) in local meteorology was more representati e than the one year o data used pre iously. The se ere weather in ormation in the 1972 FES was udged to be alid e cept 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 in ormation 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 a erage annual temperature o 60.0 F, with monthly a erages ranging rom 39.4 F in anuary to 79.6 F in uly. These temperatures are slightly warmer than data or the 1961-1990 period o record used in the 1995 FSER. The e treme temperatures, ma imum rain all in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, and ma imum snow all 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 a erage 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 representati e data rom the 20-year period rom 1986-2005.

These data were collected rom the permanent meteorological acility. On an annual basis, the most re uent wind directions at 10 meters are south-southwest and southwest at 16.0 percent and 8.4 percent, respecti ely. This re lects a small shi t rom easterly to westerly directions rom the on-site data rom 1974-1993 used in the 1995 FSER. The annual a erage wind speed decreased rom 4.1 miles per hour to 3.7 miles per hour at the 10-meter le el in the more recent 20-year data period. In addition, the annual re uency o calms, de ined 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 gra ity (an acceleration o 9.78 meters/second2). When there is an earth ua e, the orces caused by the sha ing can be measured as a percentage o the orce o gra ity, or percent g.

72 Final Supplemental En ironmental Impact Statement

Chapter 3 Se ere Weather Based on Section 2.3.1.3 o the WBN FSAR (TVA 2004d), the se ere weather in ormation in the 1972 FES remains accurate, e cept 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 stri ing the site is 1.48E-4 with a recurrence inter al o 6755 years. This is based on tornado data rom 1950 through 1986. E tension o the tornado database end date rom 1986 to 2005 increases the estimate o the probability o a tornado stri ing the site to 2.7 E-4 with a recurrence inter al o 3703 years. During the period rom 1950-2005, 44 tornadoes were identi ied within a 30-nautical-mile radius o Watts Bar (appro imately 2827 s uare miles). The mean tornado path was 0.96 s uare miles, and the annual tornado re uency was 0.80.

Dis ersion Section 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, abo e, results in an increase o the ma imum dispersion alue rom 1.09E-5 to 1.43E-5 second/cubic meters and shi ts 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 re uirements, and resulting impacts are insigni icant.

3.12. uclear Plant Safety and Security 3.12.1. S A A TVA maintains a probabilistic sa ety assessment model to use in e aluating the most signi icant ris s 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, e cept or a ew procedural changes implemented as part o the WBN operation, none o the se ere accident mitigation design alternati es were bene icial to mitigating the ris o se ere accidents urther. The term accident re ers to any unintentional e ent (i.e., outside the normal or e pected plant operation en elope) that results in a release or a potential or a release o radioacti e material to the en ironment. The NRC categorizes accidents as either design basis or se ere. Design basis accidents are those or which the ris is great enough that NRC re uires plant design and construction to pre ent unacceptable accident conse uences. Se ere accidents are those that NRC considers too unli ely to warrant normal design controls.

Since 1995, TVA has implemented the industry-re uired design and corresponding design and corresponding mitigating action changes as re uired by NRC or continued operation o WBN Unit 1 and would implement them or operation o Unit 2. The design changes ha e already been implemented in the WBN Unit 1 probabilistic sa ety assessment model. The analysis is based on the WBN Unit 1 probabilistic sa ety assessment model, which is considered applicable or Unit 2 operations because o its similarity to Unit 1.

Final Supplemental En ironmental Impact Statement 73

Completion and Operation o Watts Bar Nuclear Plant Unit 2 An analysis was per ormed or this FSEIS to estimate the human health impacts rom potential accidents at WBN in the e ent that Unit 2 became operational ( arimi 2007). Only se ere 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 en ironmental conse uences would be signi icantly less.

The MACCS2 computer code (Version 1.13.1) was used to per orm probabilistic analyses o radiological impacts. The generic input parameters gi en with the MACCS2 computer code that were used in NRC s se ere accident analysis (NUREG-1150) ormed the basis or the analysis. These generic data alues were supplemented with parameters speci ic to WBN and the surrounding area. Site-speci ic data included population distribution, economic parameters, and agricultural product. Plant-speci ic release data included nuclide release, release duration, release energy (thermal content), release re uency, and release category (i.e., early release, late release). The beha ior o the population during a release (e acuation parameters) was based on declaration o a general emergency and the emergency planning zone (EPZ) e acuation time. These data in combination with site-speci ic meteorology were used to simulate the probability distribution o impact ris s (e posure and atalities) to the surrounding 80- ilometer (within 50 miles) population.

The conse uences o a beyond-design-basis accident, with mean meteorological conditions, to the ma imally e posed o -site indi idual, an a erage indi idual, 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 ha e been declared early in the accident se uence and that all nonessential site personnel would ha e e acuated the site in accordance with site emergency procedures be ore any radiological releases to the en ironment occurred. In addition, emergency action guidelines would ha e been implemented to initiate e acuation o 99.5 percent o the public within 16 ilometers (10 miles) o the plant. The location o the ma imally e posed o -site indi idual may or may not be at the site boundary or these accident se uences because emergency action guidelines would ha e been implemented and the population would be e acuating rom the path o the radiological plume released by the accident.

Table 3-13. Se ere Accident Annual Ris s A erage ndi idual a imally osed Off- ember of Po ulation Release Category Site ndi idual Within ilometers (frequency er reactor year) (5 miles)

Dose Ris a Cancer Dose Ris a Cancer (rem year) Fatality b (rem year) Fatality b I - Early Containment ailure (3.4 10-7) 2.2 10-5 2.6 10-8 1.8 10-7 1.1 10-10 II - Containment Bypass (1.4 10-6) 2.2 10-5 1.3 10-8 8.2 10-7 4.9 10-10 III - 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 li elihood o occurrence o each release category b

Increased li elihood o cancer atality per year The results presented in this table indicate that the highest ris to the ma imally e posed o -site indi idual is one atality e ery 38 million years (or 2.6 10-8 per year) and the 74 Final Supplemental En ironmental Impact Statement

Chapter 3 highest ris to an a erage indi idual member o the public is one atality e ery 2 billion years (or 4.9 10-10 per year). O erall, the ris results presented abo e are small.

Completion and operation o WBN Unit 2 would not change the ris s e aluated here because the li elihood o an accident that could a ect both units and lead to radioacti e releases beyond those analyzed here would be e tremely low. This is consistent with the conclusions o NRC s Generic En ironmental Impact Statement or License Renewal o Nuclear Plants (GEIS) (NRC 1996a). Accidents that could a ect multi-unit sites are initiated by e ternal e ents. Se ere accidents initiated by e ternal e ents as tornadoes, loods, earth ua es, and ires traditionally ha e not been discussed in uantitati e terms in inal en ironmental statements and were not considered in the GEIS. In the GEIS, howe er, NRC sta did e aluate e isting impact assessments per ormed by NRC and the industry at 44 nuclear plants in the United States and concluded that the ris rom beyond-design-basis earth ua es at e isting nuclear power plants is small. Additionally, the sta concluded that the ris s rom other e ternal e ents are ade uately addressed by a generic consideration o internally initiated se ere accidents.

3.12.2. T Some nongo ernmental entities and members o the public ha e e pressed concern about the ris s posed by nuclear generating acilities in light o the threat o terrorism. Because WBN is already an acti e nuclear generating acility, the ris s posed by adding a second generating unit are not the same as the ris s that may be associated with locating a nuclear generating acility at a new location. The ris posed by a terrorist attac already e ists at this site. Regardless, TVA belie es that the possibility o a terrorist attac a ecting operation o WBN Unit 2 or the combined operation o both WBN units is ery remote and that postulating potential health and en ironmental impacts rom a terrorist attac in ol es substantial speculation.

TVA has in place detailed, sophisticated security measures to pre ent physical intrusion into its nuclear plant sites, including WBN, by hostile orces see ing to gain access to plant nuclear reactors or other sensiti e acilities or materials. TVA contract security personnel are trained and retrained to react to and repel hostile orces threatening TVA nuclear acilities. TVA s security measures and personnel are inspected and tested by the NRC. It is highly unli ely that a hostile orce could success ully o ercome these security measures and gain entry into sensiti e acilities, and e en less li ely that they could do this uic ly enough to pre ent operators rom putting plant reactors into sa e shutdown mode.

Howe er, the security threat that is more re uently identi ied by members o the public or in the media are not hostile orces in ading nuclear plant sites but attac s using hi ac ed et airliners, the method used on September 11, 2001, against the World Trade Center and the Pentagon. The li elihood o this now occurring is e ually remote in light o today s heightened security awareness, but this threat has been care ully studied.

The Nuclear Energy Institute (NEI) commissioned the Electric Power Research Institute (EPRI) to conduct an impact analysis o a large et airline being purpose ully crashed into sensiti e 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 re iewed when it was inished. Using conser ati e 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 destructi e e ents. Nuclear reactor containment buildings, or e ample, ha e thic concrete walls with hea y rein orcing steel and are designed to withstand large Final Supplemental En ironmental Impact Statement 75

Completion and Operation o Watts Bar Nuclear Plant Unit 2 earth ua es, e treme o erpressures, and hurricane orce winds. Using computer models, a Boeing 767-400 was crashed into containment structures that were representati e o all U.S. nuclear power containment types. The containment structures su ered some crushing and chipping at the ma imum impact point but were not breached. The results o this analysis are summarized in an NEI paper titled Aircra t Crash Impact Analyses Demonstrate Nuclear Power Plant s 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 McGa igan obser ed

( )

(

)

( 2 )

Notwithstanding the ery remote ris o a terrorist attac a ecting WBN operations, TVA increased the le el o security readiness, impro ed physical security measures, and increased its security arrangements with local and ederal law en orcement agencies at all o its nuclear generating acilities a ter the e ents o September 11, 2001. These additional security measures were ta en in response to ad isories issued by NRC. TVA continues to enhance security at its plants in response to NRC guidance. The security measures TVA has ta en at WBN are complemented by the measures ta en throughout the United States to impro e security and reduce the ris o success ul terrorist attac s. This includes measures designed to respond to and reduce the threats posed by hi ac ing large et airliners.

In the ery remote li elihood that a terrorist attac did success ully breach the physical and other sa eguards at WBN resulting in the release o radionuclides, the conse uences o such a release are reasonably captured by the discussion o the impacts o se ere accidents discussed abo e in this section.

3.13. Radiological ffects This section discusses the potential e pected radiological dose e posure o the public during normal operations o WBN Units 1 and 2. Based on operational data rom WBN Unit 1, TVA e pects WBN Unit 2 dose data to be o the same magnitude as those pro ected in its 1972 FES or a single unit. TVA has determined that the doses to the public resulting rom the discharge o radioacti e e luents rom WBN would li ely be less than two percent o the NRC guidelines gi en in 10 CFR 50 Appendi I, and that there would be no new or 76 Final Supplemental En ironmental Impact Statement

Chapter 3 di erent e ects on the surrounding en ironment due to these releases than rom those discussed in the FES. NRC addressed potential radiological e ects in detail in its SEIS, at pp. 5-11 to 5-21 (NRC 1995b). TVA s assessment o potential impact agrees with NRCs.

The dose alues used in the Dra t 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 re ised alues do not di er materially rom those presented in the DSEIS.

Radiological m acts on umans Radionuclides in Li uid E luents The e posure pathways to humans that were used in the 1972 FES analysis remain alid.

The pathways considered are illustrated in Figure 3-6. Se eral o the pathways included in the 1972 FES analysis are not considered in the current analysis o the impact o the release o radioacti ity in li uid e luents in the area around WBN site. These pathways are doses recei ed rom swimming in and boating on the Tennessee Ri er. These pathways are no longer considered because they ha e been ound to be se eral orders o magnitude lower than the dose recei ed rom shoreline recreation. The e clusion o these e ternal dose pathways or the analysis does not signi icantly change the calculated dose commitments to indi iduals or populations since essentially all o the total body dose due to the release o radioacti e material is accounted or by ish and water ingestion. Doses to terrestrial ertebrates rom the consumption o a uatic plants, and doses to a uatic plants, a uatic in ertebrates, and ish ha e not been reassessed in the current analysis o the impact o radioacti ity in li uid e luents because doses to these organisms are less than or e ual to the doses to humans (TVA 1972).

Current analyses o potential doses to members o the public due to releases o radioacti ity in li uid e luents are calculated using the models presented in NUREG-0133 (NRC 1996b) and 11 1 (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).

Ri er water use (ingestion, ish har est), and recreational use data ha e been updated using more recent in ormation (Tables 3-14 and 3-15).

Decay time between the source and consumption is handled as describe in 1 1 (NRC 1977)

Only those doses within a 50-mile radius o WBN are considered in the population dose.

The population data are updated and pro ected through the year 2040.

Final Supplemental En ironmental Impact Statement 77

Completion and Operation o Watts Bar Nuclear Plant Unit 2 Figure 3- . Path ays to an Due to Releases of Radioacti e aterial 78 Final Supplemental En ironmental Impact Statement

Chapter 3 Table 3-1 . Public Water Su lies Within a 5 - ile Radius Do nstream of W ame Tennessee Ri er ile stimated 2 Po ulation Dayton, Tennessee 504 19,170 Soddy-Daisy/Falling Water Utility 487 11,452 District East Side Utility, Tennessee 473 49,700 Chattanooga, Tennessee 465 237,048 Table 3-15. stimated Recreational Use of Tennessee Ri er Within a 5 - ile Radius Do nstream of W eginning nding Si e stimated 2 ame TR 1 TR (acres) Recreational isits year Chic amauga Reser oir ( rom WBN to 528 510 4,799 120,986 100 percent mi ing point)

Chic amauga Reser oir ( rom 100 510 484 22,101 1,297,880 percent mi ing point to S N)

Chic amauga Reser oir ( rom S N to 484 471 9,889 7,421,905 Chic amauga Dam)

Nic a ac Reser oir ( rom Chic amauga Dam to WBN 50-mile 471 460 1,799 284,000 radius) 1 Tennessee Ri er Mile Trans er coe icients, consumption rates, and bioaccumulation actors used are those presented in the documents listed abo e, or more recent data, i a ailable. The models and input ariable used are those presented in the (TVA 1994b) which was appro ed by the NRC on uly 26, 1994. The estimated li uid radioacti e releases used in the analysis are gi en in Table 3-16.

Final Supplemental En ironmental Impact Statement 79

Completion and Operation o Watts Bar Nuclear Plant Unit 2 Table 3-1 . W Total Annual Discharge-Liquid Waste Processing System for T o-Unit O eration 1 Unit 1 Unit 1 Unit uclide 2 Unit Totals LRW1 S 2 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 80 Final Supplemental En ironmental Impact Statement

Chapter 3 Table 3-1 (continued) 1 Unit 1 Unit 1 Unit uclide 2 Unit Totals LRW1 S 2 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 1.25 3 1.2 3 2.52 3 Total -3 (TPC3) 3.33 3 3.33 3 .5 3 1

Li uid Radwaste 2

Steam Generator Blowdown 3

Tritium Production Core (single unit)

A companion igure, illustrating the release points or radioacti e plant li uid e luents rom WBN is presented in Figure 3-7. A simpli ied diagram o the WBN radioacti e li uid waste (radwaste) system is shown in Figure 3-8. The li uid radwaste system is designed to control and minimize release o the sub ect radionuclides.

A tabulation o the resulting calculated doses or Unit 2 without TPC is gi en in Table 3-17.

Doses or adults, teens, children, and in ants are in millirem (mrem). Population doses are in man-rem.

The estimated annual li uid 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 Radioacti e E luent Reports to the NRC) with the guidelines gi en by NRC in 10 CFR 50, Appendi I are compared in Table 3-18. These guidelines are designed to assure that releases o radioacti e material rom nuclear power reactors to unrestricted areas during normal conditions, including e pected occurrences, are ept as low as practicable.

Final Supplemental En ironmental Impact Statement 81

Completion and Operation o Watts Bar Nuclear Plant Unit 2 GPM = Gallons per Minute Figure 3- . Plant Liquid ffluent Path ays and Release Points 82 Final Supplemental En ironmental Impact Statement

Chapter 3 Figure 3- . Watts ar uclear Plant Liquid Rad aste System Final Supplemental En ironmental Impact Statement 83

Completion and Operation o Watts Bar Nuclear Plant Unit 2 Table 3-1 . Watts ar uclear Plant Doses From Liquid ffluents er Unit for ear 2 (mrem) 1 ADULT TB Bone GIT2 Thyroid Li er idney Lung S in 0.72 0.56 0.132 0.88 0.96 0.352 0.136 0.031 T TB Bone GIT Thyroid Li er idney Lung S in 0.44 0.6 0.104 0.8 1 0.356 0.152 0.031 C LD TB Bone GIT Thyroid Li er idney Lung S in 0.188 0.76 0.06 0.92 0.88 0.312 0.128 0.031 FA T TB Bone GIT Thyroid Li er idney Lung S in 0.032 0.036 0.033 0.264 0.036 0.034 0.032 0.031 (man-rem) 3 POP DOS TB Bone GIT Thyroid Li er idney Lung S in 1.14 1.24 1 10.8 1.5 0.98 0.73 0.222 TB Bone GIT Thyroid Li er idney Lung S in POP DOS 2 1.619 1.761 1.420 15.336 2.130 1.392 1.037 0.315 1

Total body 2

Gastro intestinal tract 3

Population Table 3-1 . Com arison of stimated Annual Liquid Releases and Resulting Doses er Unit at W

Unit 1 1 CFR 5 1 2F S Unit 1 Unit 2 Units 1 2 1 year A endi (Table 2. -2) FSAR aluation Combined O erational uidelines A erage er Unit Tritium Released (Ci)1 1.46E+02 3.33E+03 1.25E+03 4.58E+03 707 N/A2 Acti ity Released (Ci)1 3.2E-01 4.84 4.84 9.68 2.2E-01 10 Total ody Dose (mrem)3 1.7E-02 7.2E-01 7.2E-01 1.44E+00 3.1E-02 3 a imum Organ Dose (mrem)3 5.5E-02 1.0 E+00 1.0E+00 2.0E+00 4.25E-02 10 1

Ci = Curies 2

N/A = Not Applicable 3

mrem = millirem 84 Final Supplemental En ironmental Impact Statement

Chapter 3 Se eral conclusions can be drawn rom the data in Table 3-18 x The Unit 2 estimates, e en though based on ery conser ati e (worst-case) assumptions, indicate that estimated doses would continue to meet the per unit dose guideline gi en in 10 CFR Part 50, Appendi I.

x Recent WBN operational data or li uid e luents indicated that actual releases and resulting dose estimates to the public are a small raction o the Appendi I guidelines (a eraging about two percent or less). Based on these conclusions, the analyses o radiological impact to humans rom li uid releases in the TVA FES continue to be alid, and operation o WBN Unit 2 would not materially change the result.

Radionuclides in Gaseous E luents The e posure pathways used in the current analyses o the impact o radioacti e material released in gaseous e luents are e panded rom those used in the 1972 FES. The pathways considered are illustrated in Figure 3-6. These pathways include e ternal 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, li er, total body, gastrointestinal tract, idney, and lung) actual land use sur ey results are used (shown in Table 3-19) and the population data are pro ected through the year 2040. Current analyses o potential doses to members o the public due to releases o radioacti ity in gaseous e luents are calculated using the models presented in NUREG-0133 (NRC 1996b) and 11 1 (NRC 1977) These models are those used in the TVA FES, and are based on the 2 Trans er coe icients, consumption rates, and bioaccumulation actors used are those presented in the documents listed abo e, or more recent data, i a ailable. The models and input ariable used are those presented in the which was appro ed by the NRC on uly 26, 1994. The estimated gaseous radioacti e releases used in the analysis are gi en in Table 3-20.

Final Supplemental En ironmental Impact Statement 85

Completion and Operation o Watts Bar Nuclear Plant Unit 2 Table 3 Rece tors from Actual Land Use Sur ey Results Used for Potential aseous Releases From W Unit 2 Rece tor Rece tor Distance Sector umber Ty e (meters)

1. Nearest Resident N 2134

2. Nearest Resident NNE 3600

3. Nearest Resident NE 3353

4. Nearest Resident ENE 2414

5. Nearest Resident E 3268

6. Nearest Resident ESE 4416

7. Nearest Resident SE 1372

8. Nearest Resident SSE 1524

9. Nearest Resident S 1585

10. Nearest Resident SSW 1979

11. Nearest Resident SW 4230

12. Nearest Resident WSW 1829

13. Nearest Resident W 2896

14. Nearest Resident WNW 1646

15. Nearest Resident NW 2061

16. Nearest Resident NNW 4389

17. Nearest Garden N 7664

18. Nearest Garden NNE 6173

19. Nearest Garden NE 3353

20. Nearest Garden ENE 4927

21. Nearest Garden E 6372

22. Nearest Garden ESE 4758

23. Nearest Garden SE 4633

24. Nearest Garden SSE 7454

25. Nearest Garden S 2254

26. Nearest Garden SSW 1979

27. Nearest Garden SW 8100

28. Nearest Garden WSW 4667

29. Nearest Garden W 5120

30. Nearest Garden WNW 5909

31. Nearest Garden NW 3170

32. Nearest Garden NNW 4602

33. Mil Cow ESE 6706

34. Mil Cow SSW 2286

35. Mil Cow SSW 3353 86 Final Supplemental En ironmental Impact Statement

Chapter 3 Table 3 W Total annual aseous discharge Per O erating Unit (curies year reactor)

Containment Au iliary Turbine uclide Total uilding uilding uilding r-85m 3.72E+00 4.53E+00 1.23E+00 9.48E+00 r-85 6.69E+02 7.05E+00 1.86E+00 6.78E+02 r-87 4.48E-01 4.27E+00 1.09E+00 5.81E+00 r-88 3.10E+00 7.95E+00 2.13E+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-41 3.40E+01 0.00E+00 0.00E+00 3.40E+01 Br-84 8.16E-07 5.02E-02 4.81E-04 5.07E-02 I-131 6.74E-03 1.39E-01 7.08E-03 1.53E-01 I-132 1.36E-04 6.56E-01 1.70E-02 6.73E-01 I-133 2.36E-03 4.35E-01 2.03E-02 4.57E-01 I-134 4.26E-05 1.06E+00 1.47E-02 1.07E+00 I-135 8.80E-04 8.10E-01 3.13E-02 8.42E-01 H-3 1.39E+02 0.00E+00 0.00E+00 1.39E+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 Ru-103 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 3.95E-05 C-14 2.80E+00 4.50E+00 0.00E+00 7.30E+00 Final Supplemental En ironmental Impact Statement 87

Completion and Operation o Watts Bar Nuclear Plant Unit 2 Auxiliary Building Vent (common) and Containment Continuous Vents Figure 3- . Watts ar uclear Plant aseous ffluent Release Points 88 Final Supplemental En ironmental Impact Statement

Chapter 3 A tabulation o the resulting calculated gaseous doses to indi iduals per operational unit is gi en in Table 3-21.

Table 3-21 W Doses From aseous ffluent for Unit 2 Without Tritium Production for ear 2 ffluent Path ay uideline* Location Dose Ma imum E posed Noble Gases  Air dose 10 mrad 0.801 mrad/year Indi idual1 Ma imum E posed

 Air dose 20 mrad 2.710 mrad/year Indi idual1 Total body 5 mrem Ma imum Residence2,3 0.571 mrem/year Iodines/

S in 15 mrem Ma imum Residence2,3 1.540 mrem/year Particulate Bone 9.15 mrem/year 15 mrem Ma imum Real Pathway4 (critical organ)

Brea down o Iodine/Particulate Doses (mrem/yr)

Total Vegetable Ingestion 6.57 Inhalation 0.0704 Ground Contamination 0.0947 Submersion 0.130 Bee Ingestion5 2.28 Total 9.145 Guidelines are de ined in Appendi I to 10 CFR Part 50.

1 Ma imum e posure point is at 1250 meters in the ESE sector.

2 Dose rom air submersion.

3 Ma imum e posed residence is at 1372 meters in the SE sector.

4 Ma imum e posed indi idual is a child at 1979 meters in the SSW sector.

5 Ma imum 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 Radioacti e E luent Reports to the NRC) with NRC guidelines gi en in 10 CFR 50 Appendi I are compared in Table 3-22. These guidelines are designed to assure that releases o radioacti e material rom nuclear power reactors to unrestricted areas during normal conditions, including e pected occurrences, are ept as low as practicable.

Final Supplemental En ironmental Impact Statement 89

Completion and Operation o Watts Bar Nuclear Plant Unit 2 Table 3 Com arison of stimated Annual Airborne Releases and Resulting Doses Unit 1 10CFR50 1972 Unit 1 Unit 2 Units 1 2 10-year Appendi I (Table 2.4-2) FSAR E aluation Combined Operational Guidelines A erage per Unit Particulate Acti ity 1 3.00E-01 4.71E-01 4.71E-01 9.42E-01 9.29E-05 10 (Ci )

oble as Acti ity 2 7.00E+03 4.84E+03 4.84E+03 9.68E+03 2.70E-03 N/A (Ci1) ternal Dose 6.60E+00 2.71E+00 3.50E+00 6.21E+00 3.69E-01 10 (mrad3) 3.50E+00 1.86E+01 Organ Dose 9.41E+00 9.15E+00 8.30E-02 (inhalation and (all 15 (mrem4) (all pathways) (all pathways) (all pathways) mil only) pathways) 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 x The Unit 2 FSAR estimates, e en though based on ery conser ati e (worst-case) assumptions, indicate that estimated doses continue to meet the per unit dose guidelines gi en in 10 CFR Part 50, Appendi I.

x Historical WBN operational data or airborne e luents indicate that actual releases and resulting dose estimates (e ternal and organ) to the public are a small raction o the Appendi I guideline (a eraging 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 Doses TVA has estimated the radiological impact rom the normal operation o WBN Unit 2 using a 50-mile regional population pro ection 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 radioacti e E luent Reports to the NRC) are presented in Table 3-23.

Table 3 stimated Po ulation Doses From O eration of Watts ar uclear Plant Unit 1 10-year 10 CFR 50 1972 Unit 1 Unit 2 Units 1 2 Operational Appendi I (Table 2.4-4) FSAR E aluation Combined A erage Guidelines 3.10E+01 4.35E+00 6.66E+01 1.10E+01 3.38E-01 N/A 90 Final Supplemental En ironmental Impact Statement

Chapter 3 Releases to Sanitary Sewers Releases to sanitary sewage systems rom WBN would continue to be sampled or radioacti ity.

Any identi ied radioacti ity will be e aluated or its source. I the source o the radioacti ity is determined to be rom plant operation, the sewage would not be released to the sewer system, but will be treated as radioacti e waste.

3.1 . Radioacti e Waste The 1995 FSER described changes in plans or the radioacti e water treatment systems, which had occurred since the 1970s (TVA 1995b). Many o the systems described in that document were based on TVA s e perience rom S N, which are comparable to the systems in use at WBN Unit 1. The updates in this section are based on TVA s operating e perience at WBN Unit 1. Since hazardous waste handling e uipment is either shared between units or would be similar, the processing o radioacti e waste produced by the operation o Unit 2 would be per ormed in the same manner as Unit 1. Only minor changes ha e been made to the radioacti e waste treatment system at WBN Unit 1 since 1995, and these changes do not alter the conclusions pre iously reached.

Liquid Radioacti e Waste Treatment Systems The 1995 FSER discussed attributes such as separation and processing o tritiated and nontritiated li uids, laboratory sample processing, and processing o waste rom regeneration o condensate polishing demineralizer and spent resin. Since 1995, the boric acid e aporators and condensate demineralizer waste e aporator (CDWE) system ha e been deacti ated and the unctions ha e 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 (re ised rom Figure 4-1, TVA 1995b). The conclusion in the FSER that any releases rom these systems would meet the re uirements 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 Radioacti e Waste Treatment Systems The gaseous waste processing system is designed to remo e 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 e uipment or operation ha e occurred and, there ore, the conclusions remain alid.

Final Supplemental En ironmental Impact Statement 91

Completion and Operation o Watts Bar Nuclear Plant Unit 2 Figure 3-1 . Liquid Rad aste Processing System Sim lified Flo Diagram for Tritiated Water 92 Final Supplemental En ironmental Impact Statement

Chapter 3 Figure 3-11. Liquid Rad aste Processing System Sim lified Flo Diagram for ontritiated Water Final Supplemental En ironmental Impact Statement 93

Completion and Operation o Watts Bar Nuclear Plant Unit 2 Solid Radioacti e Wastes Radioacti e 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 pac ages the dry and wet solid radioacti e waste produced through power generation or o site shipment and disposal. The dry acti e 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, al es, piping, and other large radioacti e components. The wet acti e wastes (WAW) consist o spent resins and ilters. Radwaste is classi ied as either A, B, or C, with Class A being the least hazardous and Class C being the 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 sa e shutdown o one unit while the other unit is e periencing an accident. Some minor changes to the SRDS ha e occurred since 1995.

The 1995 FSER discusses solidi ication o resins and e aporator concentrates using cement and ermiculite. E aporator concentrates are no longer generated at WBN due to the deacti ation o the CDWE (see Li uid Radioacti e Waste Treatment Systems, abo e). Handling o resins has not changed.

In 1995, TVA planned to send low-le el radwaste to Barnwell, South Carolina, until a new disposal acility at Wa e 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 Cli e, Utah, or disposal. Following 2008, Class A WAW will also be shipped to Cli e, Utah. Class B and C waste will be shipped either to S N, which is licensed to recei e and store low le el 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 pre ious en ironmental re iews.

Trans ortation of Solid Waste In the 1995 FSER, TVA used records documenting radioacti e e luents and the results o o -site radiological monitoring at S N to con irm the 1972 FES conclusion that insigni icant en ironmental ris would result rom the transportation o low-le el waste to o -site disposal grounds is still alid. The e posures in Table 4-1 o the 1972 FSER were calculated rom an estimated 43 shipments and 15,119 cubic eet o waste rom S N. WBN now has o er 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 there ore, it can be e pected that e posures to the truc dri er and to the public would also range rom 37.2 percent and 73.1 percent o the e posure estimated in the 1995 FSER. The 1995 FSER con irmed the conclusion in the 1972 FES that the en ironmental ris rom transportation o low-le el waste to o -site disposal grounds would be insigni icant. Gi en that the number and size o shipments per year are less than pre iously pro ected, this conclusion is not changed.

94 Final Supplemental En ironmental Impact Statement

Chapter 3 Table 3-2 . a imum Antici ated T o-Unit Annual Solid Rad aste to be Processed olume Waste Ty e (cubic feet)

Spent Resins and Filter Sludges 720 Filter Cartridges 240 Compactable and Noncompactable Trash 10,000 Contaminated Oil 100 Total 11, 3.15. S ent Fuel Storage The 1972 FES assumed that spent uel would be shipped to the reprocessing plant in Barnwell, South Carolina. The 1993 re iew o the FES noted that reprocessing was no longer li ely, and that TVA then e pected 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 re ised plan was or TVA to pro ide additional storage capacity on site, i needed, until a licensed DOE acility became a ailable. On-site storage o spent uel was mentioned in the 1995 FES, but not in the 1995 FSER.

The need to e pand 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, S N Units 1 and 2, and WBN Unit 1 and included a thorough re iew o the en ironmental e ects o constructing and operating an on-site independent spent uels storage installation (ISFSI). The present FSEIS incorporates by re erence 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 re uired 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 e pansion 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 cas s 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 pro ide an estimated total number o cas s that would be needed or 40 years o operation i WBN Unit 2 were completed. Although S N has recei ed licensing appro al to use cas s that can contain 32 spent uel assemblies, this e aluation uses the more conser ati e 24- uel assembly cas design capacity. Note that the data or WBN Unit 2 re lects the di erence between a unit producing tritium (Unit 1) and one that would not produce tritium (Unit 2).

Final Supplemental En ironmental Impact Statement 95

Completion and Operation o Watts Bar Nuclear Plant Unit 2 Table 3-25. Data for umber of SFS Cas s Determination Data Parameter W Unit 1 W Unit 2 Operating cycle length 18 months 18 months Fresh uel assemblies per cycle no tritium 80 80 Fresh uel assemblies per cycle ma imum tritium 136 N/A Increase in resh uel assemblies due to tritium 56 N/A Number o operating cycles in 40 years1 27 27 Number o additional uel assemblies or tritium 1512 N/A Number o ISFSI dry cas s needed to store uel assemblies due to 63 0 tritium production acti ities Number o uel assemblies or 40 year operation 2160 2160 Number o ISFSI dry cas s needed to store uel assemblies or 27 90 spent uel pool (SFP) capacity short all, 2 3 Number o ISFSI dry cas s needed to store uel or each unit. b 90 90 Total number of SFS dry cas s required for W site, t o-unit 1

o eration 1

Forty years o operation co ers 26 re ueling outages and 27 operating cycles. Spent uel is discharged 27 times rom each unit.

2 Number is based on 24 uel assembly cas designs.

3 SFP capacity short all is based on e isting SFP usable capacity o 1363 storage cells. The number o cas s tabulated abo e or Unit 1 SFP capacity short all has been reduced rom le el pro ected in the CLWR FEIS to re lect actual tritium generation rates o uel assemblies being less than originally estimated (56).

A number o ISFSI dry storage designs ha e been licensed by the NRC and are in operation in the United States, including acilities at TVA s S N and BFN. Licensed designs include the metal cas s and concrete cas s. The ma ority o these operating ISFSIs use concrete cas s. Concrete cas s consist o either a ertical or a horizontal concrete structure housing a bas et and metal cas that con ines 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. Howe er, since the Holtec design is currently being used at TVA s S N and is representati e o all other designs, the en ironmental impact o using the Holtec concrete dry storage ISFSI design has been addressed. As stated abo e, although the multipurpose canister (MPC)-32 is being used at S N, this update has ta en a more conser ati e approach using the MPC-24, since it would re uire more cas s and correspondingly more concrete and steel.

The en ironmental analysis o spent uel storage in the CLWR FEIS, which ocused on dry storage cas s, is still alid. The ollowing sections update in ormation about the e uipment 96 Final Supplemental En ironmental Impact Statement

Chapter 3 endors and processes currently used at WBN and pro ide analysis o the e ects 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 S N. 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 S N 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 cas s (see Table 3-25). Using the S N ISFSI as a basis or calculating an appropriately sized pad, an area o appro imately 55,800 s uare eet would be needed to store the 180 cas s re uired to support a two-unit operation at WBN or 40 years. Assuming a proportionate ratio o area re uired or construction disturbance, nuisance encing, and transport acti ities, a pro ected net disturbed area o appro imately 2.2 acres would be re uired. The di erences between constructions o an ISFSI or Unit 1 alone as compared to an ISFSI that would ser e 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 en ironmental e ects. 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 Com ared to Construction of oth Units 1 and 2 n ironmental Unit 1 Units 1 2 Parameter (from 1 CLWR F S)

E ternal appearance 63 Horizontal storage modules 180 Vertical cylindrical storage Rectangular cubes 19 9.7 eet modules (cas s) placed on a concrete constructed on three concrete cas cas oundation pad o an oundation pads appro imately 116.4 appro imate area o 55,800 s uare 38 eet eet and 2 eet thic . Each cas would be a nominal 12 eet in diameter and 21 eet tall.

1 1 Health and sa ety (only Dose rate 0.5 mrem per hour Dose Rate 0.5 mrem per hour construction wor per ormed subse uent to Total dose during construction 47.25 Total dose during construction 135 the loading o any person-rem person-rem storage modules with spent uel may result in wor er e posures rom direct and s yshine radiation in the icinity o the loaded horizontal storage modules)

Size o disturbed area ISFSI ootprint 1.3 acres ISFSI ootprint 1.3 acres Disturbed 5.3 acres Disturbed 2.2 acres Materials (appro imate) Concrete 10,618 tons Concrete 27,675 tons Steel 1,208 tons Steel 3150 tons 1

DOE 1999 Final Supplemental En ironmental Impact Statement 97

Completion and Operation o Watts Bar Nuclear Plant Unit 2 3.15.2. I The NUHOMS horizontal storage module dry cas system described in the CLWR FEIS was designed and licensed to remo e up to 24 ilowatts ( W) o decay heat sa ely rom spent uel by natural air con ection. The Holtec HI-STORM dry cas storage system currently in use at S N is licensed to remo e up to 28 W o decay heat sa ely.

Conser ati e calculations ha e shown that, or 24 W o decay heat, air entering the cas at a temperature o 70qF would be heated to a temperature o 161qF. For a 28- W ma imum heat load, and assuming similar air mass low rate through the cooling ents, the resulting temperature would be appro imately 176 F. The en ironmental 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 150 bra e horsepower engine (Bosch 1976). The heat released by an a erage automobile is the e ui alent o as ew as 12 ISFSI cas s at their design ma imum heat load o 28 W. There ore, the decay heat released to the atmosphere rom the spent nuclear uel ISFSI is e ui alent to the heat released to the atmosphere rom appro imately 15 a erage cars.

S N has proposed and the NRC is re iewing the use o storage cas s with a licensed ma imum heat load o up to 40 W. The use o this higher allowable ma imum heat load cas would result in an increase rom the alues reported in the paragraph abo e. For e ample, or a 40 W ma imum heat load, and assuming similar air mass low rate through the cooling ents results in a pro ected temperature o appro imately 221 F. The heat released by an a erage automobile is the e ui alent o as ew as nine ISFSI cas s at their proposed higher design ma imum heat load o 40 W. The decay heat released to the atmosphere rom the spent nuclear uel ISFSI would be e ui alent to the heat released to the atmosphere rom appro imately 20 a erage cars. I appro ed, this type o cas could be used at WBN.

The CLWR FEIS concluded that the heat emitted rom the WBN ISFSI would ha e no e ect on the en ironment 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 pro ected ISFSI, e en at the ma imum design-licensed decay heat le el or each cas o 28 W, would be appro imately 5000 W (i.e., 180 cas s 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 en ironment rom any o the proposed nuclear power plants on 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 o er a 40-year period would not generate the ull ISFSI heat until 40 years a ter the initial operation.

The proposed use o cas s with higher allowable ma imum heat load (40 W) would result in an increase rom the alues reported abo e. For e ample, or a 40- W ma imum heat load, a site total o 7200 W would represent about 0.15 percent o the heat released to the en ironment rom any o the proposed nuclear power plants. There ore, or the proposed 40- W cas design, no noticeable e ects on the en ironment or climate would be e pected.

The di erences between the operation o an ISFSI or Unit 1 alone as compared to an ISFSI that would ser e 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 wor ers rom ISFSI 98 Final Supplemental En ironmental Impact Statement

Chapter 3 operation would be minor. In general, the operational e ects o the HI-STORM modules would be similar to that described in the CLWR FEIS or the NUHOMS-24P, as would be the en ironmental e ects.

Table 3-2 . SFS O eration for Watts ar uclear Plant Unit 1 as Com ared to O eration of oth Units 1 and 2 n ironmental Unit 1 (from CLWR F S) Units 1 and 2 Parameter E ui alent to heat emitted into the atmosphere E ects o operation E ui alent to heat emitted into the atmosphere by appro imately 15 a erage size cars, or 20 o the heat by appro imately 2-6 a eraged-sized cars. cars i the higher ma imum heat load cas dissipation system proposed at S N is used.

Trans er cas decontamination water Trans er cas decontamination water Facility water use consumption o less than 946 cubic eet. consumption o less than 2703 cubic eet.

Wor er e posure As the result o daily Wor er e posure As the result o daily inspection o cas s, during a 40-year li e cycle, inspection o cas s, during a 40-year li e cycle, wor ers would be e posed to 58.8 person-rem. wor ers would be e posed to 168 person-rem.

Radiological impact rom routine Public e posure The regulatory limit or public Public e posure The regulatory limit or public operation e posure is 25 mrem per year. Doses recei ed e posure is 25 mrem per year. Doses recei ed by a member o the public li ing in the icinity o by a member o the public li ing in the icinity o the ISFSI would be well below the regulatory the ISFSI would be well below the regulatory re uirements. re uirements.

Cas loading and decontamination operation Cas loading and decontamination operation Radwaste and generates less than 126 cubic eet o low-le el generates less than 360 cubic eet o low-le el source terms radioacti e waste. radioacti e waste.

Small (appro imately 0.1 percent o the nuclear Climatological Small (less than 0.1 percent o the nuclear power plant s heat emission to the atmosphere, impact power plant s heat emission to the atmosphere) or appro imately .15 percent i 40 W cas are used)

The horizontal storage module sur ace is not Impact o runo rom The storage cas sur ace is not contaminated.

contaminated. No contaminated runo is operation No contaminated runo is e pected.

e pected.

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 appro imately 50 mrem or less or di erent scenarios, were compared with the natural radiation dose o about 300 mrem annually recei ed by each person in the United States (DOE 1999). The storage cas s 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 e ent would be consistent with doses pre iously determined.

3.1 . Trans ortation of Radioacti e aterials The e ects o transporting nuclear uels and radioacti e wastes are addressed in the 1972 FES. The 1995 FSER addressed the transportation o spent uels and radioacti e waste.

The transportation o radioacti e waste and spent uel are addressed brie ly 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 re ueling. As the FES e plained, relati ely low le els o radiation are emitted rom Final Supplemental En ironmental Impact Statement 99

Completion and Operation o Watts Bar Nuclear Plant Unit 2 unirradiated new uel assemblies. There ore, the only e posure to people rom the routine shipment o new uel would be in direct iew and to the indi idual truc dri ers assigned.

The e posure in the cab o the uel transport truc was estimated to be 0.1 mrem per hour, and e posure to transportation personnel was estimated to be less than 1 mrem per shipment. This le el would not cause any ad erse e ects. The FES also discussed accident potential, concluding that there would be no signi icant en ironmental ris s rom radiation resulting rom an accident in ol ing a shipment o new uel (TVA 1972).

In the re iew 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 re ueling to occur e ery 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 e ects would be small compared to the e ects 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 li ely be shipped by truc , although transport by barge or rail was also considered. An estimated 10 shipments per year were e pected, with up to se en shipping containers per load, each containing two uel assemblies or a ma imum o 14 assemblies per truc shipment. The FES discussed si shipping routes. Currently, TVA recei es se en shipments per reload with a ma imum number o assemblies per truc o 12, pac ed in si shipping containers.

Westinghouse is de eloping new shipping containers and will only be able to ship 10 assemblies per truc in 10 shipping containers. They e pect to be re uired to start using the new containers in 2009.

The (AEC 1972) and 1 (NRC 1975) e aluated the en ironmental e ects o transportation o uel and waste or light water reactors and ound the impacts to be small.

These analyses pro ided the basis or Table S-4 in 10 CFR 51.52, which summarizes the en ironmental impacts o transportation o uel and radioacti e wastes to and rom a re erence reactor. Both normal conditions o transport and accidents are addressed in the table.

Subparagraph 10 CFR 51.52(a)(5) re uires that unirradiated uel be shipped to the reactor site by truc . A condition that the truc shipments not e ceed 73,000 pounds as go erned 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. E ery 18 months, re ueling would re uire an a erage o 80 uel assemblies. The uel assemblies, which are abricated at a uel abrication plant, would be shipped by truc to WBN shortly be ore they are re uired. Truc shipments would not e ceed the applicable ederal or state gross ehicle weight.

I WBN Unit 2 were completed, TVA would comply with all NRC, state, and ederal re uirements or transport o unirradiated uel, as it does with uel deli eries or Unit 1. The impacts o such deli eries on human health and the en ironment are e pected to be minimal.

100 Final Supplemental En ironmental Impact Statement

Chapter 3 3.1 . Decommissioning Post-operational impact considerations were addressed in the 1972 FES (TVA 1972) under short-term ersus long-term producti ity and irre ersible and irretrie able commitment o resources. Decommissioning is also addressed in the 1995 NRC FES (NRC 1995a) and TVA s 1995 FSER (TVA 1995b). As these documents e plain, at the end o the operating li e o the WBN units, TVA would see the termination o its operating license rom NRC.

Termination re uires that the units be decommissioned, a process that ensures the units are sa ely remo ed rom ser ice and the site made sa e or unrestricted use. Consistent with the 1995 FSER, TVA is not proposing a decommissioning plan now. A decommissioning plan would be de eloped or appro al by NRC, with appropriate en ironmental re iews, when TVA applies or decommissioning o these units in the uture.

ethods The three NRC-appro ed methods o decommissioning nuclear power acilities described in the 1995 FSER are still iable alternati es. These are

1. D CO . The DECON option calls or the prompt remo al o radioacti e material at the end o the plant li e. Under DECON, all uel assemblies, nuclear source material, radioacti e ission and corrosion products, and all other radioacti e and contaminated materials abo e NRC-restricted release le els are remo ed rom the plant. The reactor pressure essel and internals would be remo ed along with remo al and demolition o the remaining systems, structures, and components with contamination control employed as re uired. This is the most e pensi e o the three options.

2. SAFSTOR. SAFSTOR is a de erred decontamination strategy that ta es ad antage o the natural dissipation o almost all o the radiation. A ter all uel assemblies, nuclear source material, radioacti e li uid, and solid wastes are remo ed 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 le els a ter a period o up to 60 years, and the site would be released or unrestricted use. Although this option ma es the site una ailable or alternate uses or an e tended period, wor er and public doses would be much smaller than under DECON, as would the need or radioacti e waste disposal.

3. TO . As the name implies, this method in ol es encasing all radioacti e materials on site rather than remo ing them. Under ENTOMB, radioacti e structures, systems, and components are encased in a structurally long-li ed substance, such as concrete.

The entombed structure is appropriately maintained and monitored until radioacti ity decays to a le el that permits termination o the license. This option reduces wor er and public doses, but because most power reactors will ha e radionuclides in concentrations e ceeding the limits or unrestricted use e en a ter 100 years, this option may not be easible under current regulation.

It is e pected that by the time WBN is decommissioned, new, impro ed technologies, including use o robotics, will ha e been de eloped and appro ed by NRC.

Cost In 1995, NRC estimated that it would cost up to 200 million to decommission a pressurized water reactor li e WBN Units 1 and 2. NRC currently estimates that decommissioning Final Supplemental En ironmental Impact Statement 101

Completion and Operation o Watts Bar Nuclear Plant Unit 2 would cost up to 366 million in today s dollars. TVA maintains a nuclear decommissioning trust to pro ide money or the ultimate decommissioning o its nuclear power plants. The und is in ested in securities generally designed to achie e a return in line with o erall e uity mar et per ormance. In une 1994, this und had accumulated 50 million. Since then, unds ha e been accumulated to co er the cost o decommissioning TVA s 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 TVA s operating nuclear units. The present alue is calculated by escalating the decommissioning cost in today s dollars by 4 percent per year through decommissioning. This liability is then discounted at a 5 percent real rate o return.

This e uates 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 belie es that, o er the long term and be ore cessation o nuclear plant operations and commencement o decommissioning acti ities, ade uate unds rom in estments will be a ailable 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 ma e any necessary contributions to the und to co er the costs o uture decommissioning.

Potential m acts to the n ironment En ironmental issues associated with decommissioning were analyzed in the

, NUREG 1437 (NRC 1996a 1999). The generic en ironmental impact statement included a determination o whether the analysis o the en ironmental 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-speci ic analysis is re uired by NRC, unless new and signi icant in ormation is identi ied. Category 2 issues are those that do not meet one or more o the criteria o Category 1 and there ore re uire additional plant-speci ic re iew. En ironmental analysis o the uture decommissioning plan or WBN would tier rom this or the appropriate NRC document in e ect at the time.

TVA has not identi ied any signi icant new in ormation during this en ironmental re iew that would indicate the potential or decommissioning impacts not pre iously re iewed.

There ore, TVA does not at this time anticipate any ad erse e ects rom the decommissioning process. As stated earlier, urther en ironmental re iews would be conducted at the time a decommissioning plan or WBN is proposed.

102 Final Supplemental En ironmental Impact Statement

Enclosure 3 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.