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Category:Letter
MONTHYEARIR 05000390/20250102024-11-0404 November 2024 Notification of an NRC (FPTI) (NRC Inspection Report 05000390/2025010 0500039/ 2025010) (RFI) CNL-24-074, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-10-23023 October 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions IR 05000390/20243012024-10-17017 October 2024 Operator Licensing Examination Approval 05000390/2024301 and 05000391/2024301 ML24282B0412024-10-15015 October 2024 Request for Withholding Information from Public Disclosure for Sequoyah Nuclear Plant, Units 1 and 2 and Watts Bar Nuclear Plant, Units 1 and 2 ML24261C0062024-10-0404 October 2024 Correction to Amendment No. 134 to Facility Operating License No. NPF-90 and Amendment No. 38 to Facility Operating License No. NPF-96 ML24260A1682024-10-0404 October 2024 Regulatory Audit Summary Related to Request to Add and Revise Notes Related to Technical Specification Table 3.3.2-1, Function 5 ML24284A1072024-09-26026 September 2024 Affidavit for Request for Withholding Information from Public Disclosure for Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2 CNL-24-060, Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description2024-09-24024 September 2024 Supplement to Request for Approval of the Tennessee Valley Authority Nuclear Quality Assurance Program Description CNL-24-047, Decommitment of Flood Mode Mitigation Improvement Systems2024-09-24024 September 2024 Decommitment of Flood Mode Mitigation Improvement Systems ML24262A0602024-09-23023 September 2024 Summary of August 19, 2024, Meeting with Tennessee Valley Authority Regarding a Proposed Supplement to the Tennessee Valley Authority Nuclear Quality Assurance Plan CNL-24-065, Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-09-18018 September 2024 Tennessee Valley Authority – Central Emergency Control Center Emergency Plan Implementing Procedure Revisions 05000390/LER-2024-002, Automatic Reactor Trip Due to Main Generator Protection Relay Actuation2024-09-0505 September 2024 Automatic Reactor Trip Due to Main Generator Protection Relay Actuation IR 05000390/20240052024-08-28028 August 2024 Updated Inspection Plan and Assessment Follow-Up Letter for Watts Bar Nuclear Plant, Units 1 and 2 - Report 05000390-2024005 and 05000391-2024005 ML24218A1442024-08-27027 August 2024 Issuance of Amendment Nos. 169 and 75 Regarding Technical Specification Surveillance Requirement 3.9.5.1 to Reduce the Residual Heat Removal Flow Rate IR 05000390/20244022024-08-20020 August 2024 – Security Baseline Inspection Report 05000390-2024402 and 05000391/2024402 - Public CNL-24-061, Supplement to Application to Revise Function 5 of Technical Specification Table 3.3.2-1, ‘Engineered Safety Feature Actuation System Instrumentation,’ for the Sequoyah and Watts Bar (SQN-TS-23-02 and WBN-TS-23-08),2024-08-19019 August 2024 Supplement to Application to Revise Function 5 of Technical Specification Table 3.3.2-1, ‘Engineered Safety Feature Actuation System Instrumentation,’ for the Sequoyah and Watts Bar (SQN-TS-23-02 and WBN-TS-23-08), ML24219A0262024-08-12012 August 2024 Request for Withholding Information from Public Disclosure IR 05000390/20240022024-08-0707 August 2024 Integrated Inspection Report 05000390/2024002 and 05000391/2024002 Rev ML24204A2652024-07-25025 July 2024 Regulatory Audit Summary Related to Request to Revise Technical Specification Surveillance Requirement 3.9.5.1 to Reduce the Residual Heat Removal Flow Rate ML24199A0012024-07-22022 July 2024 Clarification and Correction to Exemption from Requirement of 10 CFR 37.11(c)(2) ML24172A1342024-07-15015 July 2024 Exemptions from 10 CFR 37.11(C)(2) (EPID L-2023-LLE-0024) - Letter ML24170A8002024-07-15015 July 2024 Issuance of Amendment Nos. 168 and 74 Regarding Revision to Technical Specification Table 1.1-1 for Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Bolts IR 05000390/20244402024-07-12012 July 2024 95001 Supplemental Inspection Supplemental Report 05000390-2024440 and 05000391-2024440 and Follow-Up Assessment Letter 05000391/LER-2024-003, Inoperability of Both Trains of Unit 2 Low Head Safety Injection2024-07-11011 July 2024 Inoperability of Both Trains of Unit 2 Low Head Safety Injection ML24131A0012024-07-0202 July 2024 Issuance of Amendment Nos. 167 and 73 Regarding Adoption of Technical Specification Task Force Traveler TSTF-427-A, Revision 2 CNL-24-052, Response to Request for Additional Information Regarding Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14)2024-06-27027 June 2024 Response to Request for Additional Information Regarding Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14) CNL-24-018, License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-276-A, Revision 2, Regarding TS 3.8.1 AC Sources – Operating to Clarify Requirements for Diesel Generator Testing (WBN-TS2024-06-25025 June 2024 License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-276-A, Revision 2, Regarding TS 3.8.1 AC Sources – Operating to Clarify Requirements for Diesel Generator Testing (WBN-TS ML24089A1152024-06-21021 June 2024 Transmittal Letter, Environmental Assessments and Findings of No Significant Impact Related to Exemption Requests from 10 CFR 37.11(c)(2) ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc ML24100A7642024-05-16016 May 2024 Issuance of Amendment No. 166 Regarding Revision to Technical Specification 3.8.2, AC Sources-Shutdown, to Remove Reference to C-S Diesel Generator (CNL-23-062) IR 05000390/20240012024-05-14014 May 2024 Integrated Inspection Report 05000390/2024001 and 05000391/2024001 CNL-24-040, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-05-0808 May 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions 05000391/LER-2024-002, Re Automatic Reactor Trip Due to Steam Generator 3 Level LO-LO2024-05-0606 May 2024 Re Automatic Reactor Trip Due to Steam Generator 3 Level LO-LO IR 05000391/20240072024-04-30030 April 2024 Assessment Follow-up Letter for Watts Bar Nuclear Plant, Unit 2 – Report 05000391/2024007 ML24120A1182024-04-29029 April 2024 – Notification of NRC Supplemental Inspection (95001) and Request for Information CNL-24-037, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 422024-04-22022 April 2024 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 42 ML24087A1912024-04-18018 April 2024 Exemption from Select Requirements of 10 CFR Part 73, Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting CNL-24-010, License Amendment Request to Recapture Low-Power Testing Time (WBN-TS-23-19)2024-04-17017 April 2024 License Amendment Request to Recapture Low-Power Testing Time (WBN-TS-23-19) CNL-24-033, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2024-04-17017 April 2024 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-24-024, Hydrologic Engineering Center River Analysis System Project Milestone Status Update2024-04-17017 April 2024 Hydrologic Engineering Center River Analysis System Project Milestone Status Update ML24072A0052024-04-15015 April 2024 Issuance of Amendment Nos. 165 and 72 Regarding Increase in the Maximum Number of Tritium Producing Burnable Absorber Rods and Supporting Changes, and Revision to the Updated Final Safety Analysis Report CNL-24-004, Application to Modify the Watts Bar Nuclear Plant, Unit 1 and Unit 2 Technical Specifications for Main Control Room Chiller Completion Time Extension (WBN-TS-23-13)2024-04-0404 April 2024 Application to Modify the Watts Bar Nuclear Plant, Unit 1 and Unit 2 Technical Specifications for Main Control Room Chiller Completion Time Extension (WBN-TS-23-13) IR 05000390/20244012024-04-0202 April 2024 – Security Baseline Inspection Report 05000390/2024401 and 05000391/2024401 - (Public) CNL-24-020, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Units 1 and 2, Request for Approval of Quality Assurance Program Description and Application to Revise the Technical Specifications Associated with QAPD Requirements2024-04-0101 April 2024 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Units 1 and 2, Request for Approval of Quality Assurance Program Description and Application to Revise the Technical Specifications Associated with QAPD Requirements CNL-24-007, Annual Insurance Status Report2024-03-27027 March 2024 Annual Insurance Status Report CNL-24-008, Guarantee of Payment of Deferred Premiums - 2023 Annual Report2024-03-27027 March 2024 Guarantee of Payment of Deferred Premiums - 2023 Annual Report 05000391/LER-2024-001, Automatic Reactor Trip Due to Main Generator Protection Relay Actuation2024-03-27027 March 2024 Automatic Reactor Trip Due to Main Generator Protection Relay Actuation CNL-24-025, Notice of Intent to Pursue License Renewal for Watts Bar Nuclear Plant, Unit 1 - Submittal Schedule2024-03-25025 March 2024 Notice of Intent to Pursue License Renewal for Watts Bar Nuclear Plant, Unit 1 - Submittal Schedule ML24081A0262024-03-21021 March 2024 Emergency Plan Implementing Procedure Revisions ML24079A0312024-03-19019 March 2024 Wb 2024-301, Corporate Notification Letter (210-day Ltr) 2024-09-05
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Tennessee Valley Authority, Post Office Box 2000, Spring City, Tennessee 37381-2000 August 22, 2011 10 CFR 50 Appendix I 10 CFR 51.92 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 Request for Additional Information on the Determination of the 50 Mile Population Dose
References:
- 1. 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
- 2. TVA letter to NRC dated July 28, 2011, Watts Bar Nuclear Plant (WBN)
Unit 2 - Results from Cost-Benefit Analysis of Radwaste System Enhancements
- 3. Draft U.S. NRC Regulatory Guide 1.111 Revision 1, Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactor, draft dated July 1977
- 4. U.S. NRC Regulatory Guide 1.109 Revision 1, Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I, dated October 1977 The purpose of this letter is to respond to a verbal request for additional information from the NRC staff on the need to provide additional conservatism in the calculation of the 50 mile population dose through the inclusion of terrain adjustment factors. The population dose is discussed in Chapter 11 of the Final Safety Analysis Report (FSAR), Section 3.13 of the Final Supplemental Environmental Impact Statement (FSEIS) (Reference 1), and was used in Reference 2 to determine the potential benefit of various modifications to the WBN radwaste processing systems. The enclosure provides the basis for concluding that the current FSAR and FSEIS population dose values are adequate and conservative.
U.S. Nuclear Regulatory Commission Page 2 August 22, 2011 There are no new commitments in this letter.
If you have any questions, please contact Bill Crouch at (423) 365-2004. I declare under penalty of perjury that the foregoing is true and correct. Executed on the 22 nd day of August, 2011.
Respectfully, David Stinson Watts Bar Unit 2 Vice President
Enclosure:
x/as for Routine Releases cc (Enclosure):
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 TVA Letter Dated August 22, 2011 X/Qs for Routine Releases NRC asked if terrain adjustment factors were applied to the X/Q values used to determine the total population dose within 50 miles of the site and if not why not.
Response
TVA uses the Gaseous Effluent Licensing Code (GELC) computer code to calculate X/Q and D/Q values as well as the offsite dose due to routine releases for the WBN site. GELC uses a Gaussian straight-line trajectory model to determine the dispersion characteristics based on wind speed and atmospheric stability. During licensing of Unit 1, terrain adjustment factors (TAF) were developed and used to account for topography and diurnal related factors in determining the dose to the maximum exposed individual. These factors were applied to the receptors within approximately 5 miles of the plant as shown in FSAR Table 3.11-8. TVA developed these TAFs using the variable trajectory computer code MESOPUFF II to calculate X/Qs for the same near site locations. MESOPUFF II was the code used by EPA at the time for determining dispersion coefficients. The TAFs were calculated by dividing the MESOPUFF II X/Q values by the GELC X/Q values. The GELC X/Q values were then multiplied by the appropriate ratio. If the ratio was less than one, the multiplier was set to one.
TAFs were not applied to the X/Q values used for determining the 50-mile total population dose for licensing Unit 1. Licensing submittals for Unit 2 were developed on the same basis as Unit 1, and TAFs were not used in determining the 50-mile population dose.
For determining population doses to the 50-mile population around the plant, a circle with a radius of 50 miles around the plant is divided into 22.5 degree sectors centered on the 16 main compass points. Each compass sector is then broken down into 10 elements. The midpoint distance of each element from the site is determined and ranges from 0.8 miles to 45 miles.
Dispersion factors are calculated for the midpoint of each sector element. For each of these sector elements, an average dose is calculated and then multiplied by the population in that sector element. The average dose is determined by multiplying the maximum individual dose for the sector by a ratio of the average ingestion rates to the maximum ingestion rates for each age group. The doses are then multiplied by the fraction of the population belonging to each age group in that sector element. The 50-mile population dose for a given organ (thyroid and total body) is the sum of the population doses for each age group and pathway over all sector elements. This is done in accordance with the methodology that is recommended in Regulatory Guide 1.109 (Reference 4).
TAFs for all 50-mile receptors were evaluated using the same technique used for near the plant receptors to determine if the use of TAFs was warranted in determining the population doses.
MESOPUFF II runs were made for all 160 receptors within 50 miles of the plant. As shown in FSAR Table 11.3-8, TAFs with values greater than one were calculated for most receptors within the low population zone (i.e., within approximately 5 miles of the site). Four of 16 elements with centers located at 7.5 miles from the site had TAF values greater than 1.0.
Once the distance from the plant exceeded 7.5 miles, the X/Q values from MESOPUFF II were equal to or lower than the X/Q values calculated by GELC. The MESOPUFF II X/Q values for receptors 30 or more miles from the plant were approximately two to three orders of magnitude lower than the values calculated by GELC. Less than two percent of the total 50 mile population resides within 10 miles of the site. Chattanooga and Knoxville, where most of the population within 50 miles of the WBN site resides, are located about 50 miles from the plant.
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Enclosure TVA Letter Dated August 22, 2011 X/Qs for Routine Releases Dose to the Projected Population in 2040 within 50 Miles of Watts Bar Nuclear Plant Analysis Total Body Dose Thyroid Dose (person-rem) (person-rem)
Current FSAR Source Term & 6.68 13.0 X/Q values Current FSAR Source Term & 6.98 13.8 Highest X/Q values from MESOPUFF II or GELC Current FSAR Source Term & 1.86 4.35 MESOPUFF II X/Q Actual 2010 Source & 8.70E-02 8.95E-02 MESOPUFF II X/Q Four separate cases were considered. The first is the current FSAR and FSEIS analysis using X/Qs calculated by GELC. The second case uses the highest X/Q value from either MESOPUFF II or GELC with the FSAR Chapter 11 source term. The third case shows the results for the FSAR source term with X/Q values from MESOPUFF II, a variable trajectory code. Reference 3 states that the preferred model is one that among other attributes best simulates atmospheric transport in the region of interest. MESOPUFF II is a more physically realistic model than GELC. The last case presented shows the projected 50-mile population dose using the actual plant releases for 2010.
These evaluations show that the 50 mile population doses as presented in the FSAR are sufficiently conservative, and no additional correction factors (i.e., near site TAFs) need to be included. In regard to the specific need to include terrain adjustment factors, Reference 3 states the following: adjustments to Equation (3) may be necessary to prevent misrepresentation of actual atmospheric transport and diffusion characteristics that could result in substantial underestimates of actual exposure to an individual or population (emphasis added). A comparison of case 2 to case 1 shows that there is not a substantial underestimate of the population dose. Case 3 shows the FSAR results do not underestimate the dose but have significant margin for the given source term. The conclusions from the cost benefit analysis (Reference 2) remain valid and no additional enhancements need to be considered. The more accurate X/Qs for case 3 would have allowed gaseous releases to have been screened out in the cost benefit study and no enhancements would have needed to be considered. The last case shows the actual margin in the FSAR (case 1) analyses. The current FSAR and FSEIS population dose values are adequate and conservative and do not need to be revised to include TAFs for the receptor locations out to 50 miles.
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