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| #REDIRECT [[CNL-18-113, Response to Request for Additional Information Regarding Application to Revise Watts Bar Unit 2 Technical Specification 4.2.1, Fuel Assemblies, and Watts Bar Units 1 and 2 Technical Specifications Related to Fuel Storage (WBN-TS-17-028) .]]
| | {{Adams |
| | | number = ML18283A107 |
| | | issue date = 10/04/2018 |
| | | title = Response to Request for Additional Information Regarding Application to Revise Watts Bar Unit 2 Technical Specification 4.2.1, Fuel Assemblies, and Watts Bar Units 1 and 2 Technical Specifications Related to Fuel Storage (WBN-TS-17-028) ... |
| | | author name = Henderson E K |
| | | author affiliation = Tennessee Valley Authority |
| | | addressee name = |
| | | addressee affiliation = NRC/Document Control Desk, NRC/NRR |
| | | docket = 05000390, 05000391 |
| | | license number = NPF-090, NPF-091 |
| | | contact person = |
| | | case reference number = CNL-18-113, EPID L-2017-LLA-0427, WBN-TS-17-028 |
| | | document type = Letter, Response to Request for Additional Information (RAI) |
| | | page count = 21 |
| | | project = EPID:L-2017-LLA-0427 |
| | | stage = Response to RAI |
| | }} |
| | |
| | =Text= |
| | {{#Wiki_filter:Response to Request for Additional Information Regarding Application to Revise Watts Bar Unit 2 Technical Specification 4.2.1, "Fuel Assemblies," and Watts Bar Units 1 and 2 Technical Specifications Related to Fuel Storage (WBN-TS-17-028) (EPID L-2017-LLA-0427) |
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| | Response to Request for Additional Information Regarding Application to Revise Watts Bar Unit 2 Technical Specification 4.2.1, "Fuel Assemblies," and Watts Bar Units 1 and 2 Technical Specifications Related to Fuel Storage (WBN-TS-17-028) (EPID L-2017-LLA-0427) |
| | By application dated December 20, 2017 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML17354B282), as supplemented February 15, and April 9, 2018 (ADAMS Accession Nos. ML18047A181 and ML18100A953, respectively), Tennessee Valley Authority (TVA or the licensee) submitted a proposed license amendment request (LAR) to authorize up 1,792 tritium producing burnable absorber rods (TPBARs) that can be irradiated in the reactor for Watts Bae [sic] Nuclear Plant (WBN), Unit 2. In addition, the proposed LAR requests changes to WBN Unit 1 and 2 Technical Specifications (TSs) related to fuel storage. |
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| | The requested changes would revise WBN Unit 2 TS 4.2.1, "Fuel Assemblies," to authorize up to 1,792 Tritium Producing Burnable Absorber Rods (TPBARs) that can be irradiated in the reactor. |
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| | Specifically, the requested changes revise WBN Units 1 and 2 TS 3.7.15, "Spent Fuel Assembly Storage," to simplify the fuel storage limitations on fuel assemblies by eliminating the burnup-related criteria. The requested changes add WBN Units 1 and 2 TS 3.7.18, "Fuel Storage Pool Boron Concentration," to specify the minimum fuel storage pool boron concentration when fuel is stored in the pool. The requested changes revise WBN Units 1 and 2 TS 3.9.9, "Spent Fuel Pool Boron Concentration," to modify the minimum fuel storage pool boron concentration during refueling operations when fuel is stored in the pool. The requested changes revise WBN Units 1 and 2 TS 4.3, "Fuel Storage," to replace the storage limitations on fuel assembly burnup and storage with a single requirement to maintain a specified boron concentration in the spent fuel pool (SFP). The requested changes add WBN Units 1 and 2 TS 5.7.2.21, "Spent Fuel Storage Rack Neutron Absorber Monitoring Program." |
| | The NRC staff has reviewed TVA's submittal, as well as supplements, and determined that additional information is required to enable the U.S. Nuclear Regulatory Commission (NRC) staff to make an independent assessment regarding its technical review.ARCB-RAI-1 In the application on page E1-23 of 116 in the Primary and Secondary Coolant Concentrations section it states: |
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| | The concentration of tritium for a TPC was calculated using the same methodology as used for WBN U1, which involved 1,792 TPBARs with a permeation rate of 5 Ci/TPBAR/year and two failures - The total annual tritium expected from TPBARs is based on 1792 TPBARs and a permeation rate of 5 Ci/TPBAR/year (8960 Ci/year). This results in an average tritium concentration of 11.4 Ci/gm. The concentration with 2 TPBAR failures was determined by adding the inventory of 2 TPBARs to the average amount of tritium in the RCS and dividing by the RCS mass. The average amount of tritium was determined by multiplying the average tritium concentration determined above by the RCS mass. Each TPBAR is assumed to have a maximum of 11,600 Ci at the end of a cycle. This resulted in an expected tritium concentration in the primary coolant of approximately 120 Ci/gm for 2 TPBAR failures. |
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| | In the application it is also states numerous times that this LAR is based on WBN unit 1 license amendment 40. However, WBN unit 1 license amendment 40 has been superseded by license amendment 107 and in supplement to the application dated March 31, 2016 (ADAMS Accession number ML16095A064) on page Enclosure 2, page 8 of 40, it states: |
| | Non-LOCA Accident Source Term: This source term is used for evaluation of abnormal operational occurrences (AOOs) and postulated accidents (PAs). It was updated to reflect a new permeation rate of 10 Ci/TPBAR/year, which bounds the realistic permeation rate with 100% margin. It also has increased margin by assuming ~40% more TPBARs are loaded (i.e., 2,500 TPBARs). It continues to retain conservatism regarding the inclusion of two failed TPBARs. This bounding approach to source term assumptions for accidents is consistent with the accident evaluation methodology. The modified source term provides sufficient margin to bound AOO and PA cases. |
| | Furthermore, Enclosure 2, page 37 of 40 states: |
| | -the source term is the primary and secondary coolant activity. The primary and secondary coolant activities are in accordance with ANSI/ANS-18.1-1984, except for tritium. ... This source term was updated to reflect a new permeation rate of 10 Ci/TPBAR/year, which bounds the realistic permeation rate with 100% margin. It continues to retain conservatism regarding the inclusion of two failed TPBARs. - WBN Unit 1 License Amendment 40 and the current licensing basis determined the expected tritium concentration assuming a permeation rate of 1 Ci/TPBAR/year, 2,304 total TPBARs, and two failed TPBARs. ... The assumed RCS tritium activity to support the requested changes is based on 2,500 TPBARs with an assumed permeation rate of 10 Ci/TPBAR/year and two failed TPBARs. This results in a concentration of 124.9 Ci/gm. The design basis accident assumptions for WBN Unit 1 appears to be different from that stated for WBN Unit 2, and the NRC staff is unclear which one is being requested in this license amendment request. |
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| | Please clarify, for the DBAs that assume primary and secondary coolant concentrations as their source term, what reactor coolant system tritium concentration is assumed and what is it based on, such as a permeation rate, total TPBARs, and how many failed TPBARs.TVA Response to ARCB-RAI-1 |
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| | ARCB-RAI-2 In the application on page E1-26 of 116 it states: |
| | Table 4.1-6 and 4.1-7 contain a tabulation of common control room parameters and the atmospheric dispersion factors, respectively, used in each of the design basis analyses. These are the same parameters that supported the review for NUREG-0847 Supplement 25 except for the control room isolation time, which has been corrected to account for an error. |
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| | Table 4.1-7, Atmospheric Dispersion Factors states: |
| | 1 - This is used for the Containment FHA [Fuel Handling Accident] 2 - This is used for the Containment FHA after containment is isolated and for the Auxiliary Building FHA In NUREG-0847 Supplement 25 Tables 15.5 and 15.6 it states that the control room atmospheric dispersion factor for the FHA in closed containment, FHA inside open containment, and FHA in the Auxiliary Building for the time period 0 to 2 hours is 2.59E-3 seconds per cubic meter. This control room atmospheric dispersion factor is different from those stated in the license amendment request for the FHA. |
| | Explain which control room atmospheric dispersion factor(s) for the FHA are being requested in this license amendment. If they differ from the current licensing basis as stated in Tables 15.5 and 15.6 of NUREG-0847 Supplement 25 then provide the technical basis for the change.TVA Response to ARCB-RAI-2 |
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| | MCCB RAI #1: Title 10 of the Code of Federal Regulations (10 CFR), Section 50.68, "Criticality accident requirements," provides the regulatory requirements for maintaining sub-criticality in the spent fuel pool (SFP). Specifically, 10 CFR 50.68(b)(4) states that the k-effective in the SFP: |
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| | -must not exceed 0.95, at a 95 percent probability, 95 percent confidence level, if flooded with borated water, and the k-effective must remain below 1.0 (subcritical), at a 95 percent probability, 95 confidence level, if flooded with unborated water. |
| | In the proposed Technical Specification (TS) 5.7.2.21 "Spent Fuel Storage Rack Neutron Absorber Monitoring Program," the licensee states that the program will be used to verify the "-neutron absorber density is consistent with the assumptions in the spent fuel pool [SFP] criticality analysis." However, the Boron-10 (B-10) areal density (AD) is the main property of the neutron absorbing material (NAM) that needs to be verified with respect to the SFP criticality analysis, not the neutron absorber density. Explain why the density of the NAM is specifically cited in the proposed TS, instead of the B-10 AD, which is more important assumption used in the SFP criticality analysis.TVA Response to MCCB RAI #1 |
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| | DORL RAI #1 In the submittal dated December 20, 2017, Enclosure 6 contains a commitment to replace the Containment Isolation Thermal Relief Check Valves on the WBN Unit 2 supply lines to Containment for the Component Cooling Water (CCW) System and Essential Raw Cooling Water (ERCW) System with simple relief valves. TVA states that the simple relief valves will be installed prior to loading TPBARs in the WBN Unit 2 reactor core. The WBN Unit 2 Facility Operating License (FOL) NPF-96 expires October 21, 2055. There are numerous refueling outages (RFOs) between now and the end of the FOL. Has TVA scheduled a RFO to replace the Containment Isolation Thermal Relief Check Valves with simple relief valves? If so, which RFO is this work planned to be completed? If the valves are not replaced prior to the completion of this LAR, the NRC will add this as a license condition to FOL NPR-96. TVA Response to DORL RAI #1 DORL RAI #2 In the submittal dated December 20, 2017, TVA requests that the license amendment be implemented prior to startup from the outage where any number of TPBARs is inserted in the WBN Unit 2 reactor core. The WBN Unit 2 FOL expires October 21, 2055. There are numerous RFOs between now and the end of the FOL. Potentially, this amendment could be effective but remain not implemented for decades. Does TVA have a schedule to install TPBARs in WBN Unit 2? If so, which RFO is the TPBARs scheduled to be installed for WBN Unit 2? Are the WBN Unit 2 TPBARs scheduled to be installed during the Cycle 4 RFO in the fall of 2020? Is there a contingency plan if the TPBARs are not installed in WBN Unit 2 as planned that RFO? For example, if TVA plans to install TPBARs in WBN Unit 2 during the Cycle 4 RFO in the fall of 2020, but for some reason is not able to, what is TVA's contingency plan? TVA Response to DORL RAI #2 DORL RAI #3 What was the permeation rate for Cycle 13 of WBN Unit 1? What was the permeation rate of Cycle 14 of WBN Unit 1? What has TVA learned from the testing of the TPBARs from Cycles 13 and 14? |
| | TVA Response to DORL RAI #3 Tritium Permeation Rate for TPBARs in Cycle 13 and Cycle 14 Total Cycle Last 365 Days of Cycle |
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| | TTotal (t) = TCurrent RCS Inventory (t) |
| | + TRemoved Letdown (t) |
| | Tnon-TPBAR (t) |
| | = TSoluble Boron (t) |
| | + TLithium (t) |
| | + TFuel Rods (t) |
| | + TBurnable Absorbers (t) |
| | + TControl Rods (t) |
| | + TSecondary Source Rods (t) |
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| | TTPBAR (t) = TTotal (t) - Tnon-TPBAR (t) |
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| | Summary of WBN Unit 1 Cycle 13 and Cycle 14 PIE on the Lead Use/Surveillance TPBARs WBN Unit 1 Cycle TPBAR Design Number of Rods Examined Focus of Examinations |
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| | SNPB RAI #1 During the acceptance review of this LAR, NRC staff requested supplemental information and TVA responded on February 15, 2018 in a letter CNL-18-018. The supplemental information requested was to clarify the discrepancy between the fluence results from WCAP-18191-NP and WCAP-17035-NP for Watts Bar Unit 2 regarding the change reported inside surface neutron fluence for the RPV at 32 EFPY (1861 E+19 n/cm 2 from WCAP-18191-NP versus 3.17 E+19 n/cm 2 from WCAP-17035-NP). The TVA response provides a comparison of the power distribution of Cycle 7 in WCAP-18191 (low leakage pattern) and the radial power distribution used in WCAP-17035 (out-in pattern) in Tables 1 and 2. It was shown that the average of the relative power in the peripheral assemblies for low leakage pattern used in WCAP-18192 for Cycle 7 is 0.590 (Table 1) while the average of the relative power in the peripheral assemblies for out-in pattern used in WCAP-17035 is 0.97. However, a vast majority of the relative powers of the interior assemblies in Table 1 show increased relative powers compared to those listed in Table 2. Please provide an explanation for why the relative powers of the interior assemblies in Table 1 is greater than those of the Table 2. |
| | TVA Response to SNPB RAI #1 |
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| | SNPB RAI #2 It is stated in TVA response (CNL-18-018) that the average peripheral power increases the number of TPBARs. Also the maximum RPV flux increases from 1.351E10 n/cm 2-s to 1.687E10 n/cm2-s between Cycle 3 and Cycle 4. Furthermore, the maximum RPV flux further increases in Cycle 5 to about 1.95E10 n/cm2-s through Cycle 7. While these increases in maximum RPV flux cannot be solely associated with the implementation of TPBARs, the anticipated loading patterns including TPBARs (Cycles 4 through7) will impart a greater maximum flux on the reactor vessel than Cycle 3 which does not include TPBARs. |
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| | (a) Please describe the factors that contribute to the increase in RPV flux as the number of TBBARs increase. |
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| | Provide data on the flux values from both out-in pattern and low leakage patterns used in WCAP-18191 and WCAP-17035, respectively. TVA Response to SNPB RAI #2 |
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| | Calculated Maximum Fast Neutron Exposure Rate Excerpted from Table 2-4 of WCAP-18191 Cycle Neutron Flux (E > 1.0 MeV) [n/cm2-s]}} |
Letter Sequence Response to RAI |
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EPID:L-2017-LLA-0427, Application to Revise Watts Bar Unit 2 Technical Specification 4.2.1, Fuel Assemblies, and Watts Bar Units 1 and 2 Technical Specifications Related to Fuel Storage (WBN-TS-17-028) (Approved, Closed) |
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MONTHYEARML17263A1332017-05-26026 May 2017 Submittal of NEI 16-03, Guidance for Monitoring of Fixed Neutron Absorbers in Spent Fuel Pools Project stage: Request CNL-17-144, Application to Revise Watts Bar Unit 2 Technical Specification 4.2.1, Fuel Assemblies, and Watts Bar Units 1 and 2 Technical Specifications Related to Fuel Storage (WBN-TS-17-028)2017-12-20020 December 2017 Application to Revise Watts Bar Unit 2 Technical Specification 4.2.1, Fuel Assemblies, and Watts Bar Units 1 and 2 Technical Specifications Related to Fuel Storage (WBN-TS-17-028) Project stage: Request CNL-17-154, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 342017-12-27027 December 2017 Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 34 Project stage: Request ML18031A6592018-02-0606 February 2018 Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment to Revise Technical Specification 4.2.1 and Technical Specifications Related to Fuel Storage Project stage: Acceptance Review CNL-18-018, Supplement to Application to Revise Watts Bar Unit 2 Technical Specification 4.2.1, Fuel Assemblies, and Watts Bar Units 1 and 2 Technical Specifications Related to Fuel Storage (WBN-TS-17-028)2018-02-15015 February 2018 Supplement to Application to Revise Watts Bar Unit 2 Technical Specification 4.2.1, Fuel Assemblies, and Watts Bar Units 1 and 2 Technical Specifications Related to Fuel Storage (WBN-TS-17-028) Project stage: Supplement ML18060A0542018-03-0101 March 2018 Acceptance of Requested Licensing Action Amendment to Revise Technical Specification 4.2.1, Fuel Assemblies, and Technical Specifications Related to Fuel Storage Project stage: Acceptance Review CNL-18-051, Correction to Application to Revise Watts Bar Unit 2 Technical Specification 4.2.1, Fuel Assemblies, and Watts Bar Units 1 and 2 Technical Specifications Related to Fuel Storage (WBN-TS-17-028)2018-04-0909 April 2018 Correction to Application to Revise Watts Bar Unit 2 Technical Specification 4.2.1, Fuel Assemblies, and Watts Bar Units 1 and 2 Technical Specifications Related to Fuel Storage (WBN-TS-17-028) Project stage: Request CNL-18-049, Clinch River Nuclear Site, Response to NRC Request for Additional Information 12 in Support of Early Site Permit Application for Clinch River Nuclear Site2018-04-0909 April 2018 Clinch River Nuclear Site, Response to NRC Request for Additional Information 12 in Support of Early Site Permit Application for Clinch River Nuclear Site Project stage: Response to RAI CNL-18-069, Tennessee Valley Authority - Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revisions 35 and 362018-05-0808 May 2018 Tennessee Valley Authority - Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revisions 35 and 36 Project stage: Request ML18128A2932018-05-30030 May 2018 Letter, Individual Notice of Consideration of Issuance of Amendment to Facility Operating License and Opportunity for Hearing Project stage: Other ML18128A3062018-06-0404 June 2018 Federal Register Notice on Watts Bar Nuclear Plant, Units 1 and 2, License Amendment Application; Opportunity to Request a Hearing and to Petition for Leave to Intervene; Order Imposing Procedures (Docket Nos. 50-390 and 50-391; NRC-2018-01 Project stage: Other ML18240A0702018-08-27027 August 2018 NRR E-mail Capture - RAI for Watts Bar Unit 2 Tpbars LAR and Watts Bar Units 1 and 2 LAR Related to Fuel Storage Project stage: RAI CNL-18-113, Response to Request for Additional Information Regarding Application to Revise Watts Bar Unit 2 Technical Specification 4.2.1, Fuel Assemblies, and Watts Bar Units 1 and 2 Technical Specifications Related to Fuel Storage (WBN-TS-17-028) .2018-10-0404 October 2018 Response to Request for Additional Information Regarding Application to Revise Watts Bar Unit 2 Technical Specification 4.2.1, Fuel Assemblies, and Watts Bar Units 1 and 2 Technical Specifications Related to Fuel Storage (WBN-TS-17-028) ... Project stage: Response to RAI ML17291A5472018-11-0808 November 2018 Clinch River Early Site Permit Safety Evaluation, Section 17.0 Project stage: Request ML18332A0142019-02-0606 February 2019 Environmental Assessment and Finding of No Significant Impact Related to Application to Revise Watts Bar Unit 2 Technical Specification 4.2.1, Fuel Assemblies, Project stage: Other ML18332A0132019-02-0606 February 2019 Federal Register Notice Project stage: Request ML18347B3302019-05-22022 May 2019 Issuance of Amendment Regarding Revision to Watts Bar Unit 2 Technical Specification 4.2.1 Fuel Assemblies, and Watts Bar Units 1 and 2 Technical Specifications Related to Fuel Storage Project stage: Approval 2018-03-01
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Category:Letter
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Includes EPDP-3, Revision 3, Emergency Plan Exercises and Preparedness Drills IR 05000390/20230112023-07-24024 July 2023 Quadrennial Focused Engineering Inspection (FEI) Commercial Grade Dedication Report 05000390 2023011 and 05000391 2023011 CNL-23-053, Tennessee Valley Authority - Radiological Emergency Plan Revisions2023-07-18018 July 2023 Tennessee Valley Authority - Radiological Emergency Plan Revisions CNL-23-020, Application to Revise Technical Specifications to Adopt TSTF-501-A, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control (WBN-TS-22-06)2023-06-28028 June 2023 Application to Revise Technical Specifications to Adopt TSTF-501-A, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control (WBN-TS-22-06) CNL-23-049, Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan .2023-06-26026 June 2023 Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan . ML23122A2322023-06-0707 June 2023 Issuance of Amendment Nos. 162 and 69 Regarding Change to Date in Footnotes for Technical Specification 3.7.11, Control Room Emergency Air Temperature Control System (Creatcs) CNL-23-044, Transmittal of Revision 3 to WCAP-18774-P and WCAP-18774-NP, Addendum to the Rotterdam Dockyard Company Final Stress Report for 173 P.W.R. Vessels TVA III & IV (Report No. 30749-B-030, Rev. 3) - Evaluation of One Closure Stud Out2023-06-0101 June 2023 Transmittal of Revision 3 to WCAP-18774-P and WCAP-18774-NP, Addendum to the Rotterdam Dockyard Company Final Stress Report for 173 P.W.R. Vessels TVA III & IV (Report No. 30749-B-030, Rev. 3) - Evaluation of One Closure Stud Out IR 05000390/20234032023-05-30030 May 2023 Cyber Security Inspection Report 05000390/2023403 and 05000391/2023403 ML23131A1812023-05-23023 May 2023 Correction to Amendment No. 161 to Facility Operating License No. NPF-90 CNL-23-042, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-05-16016 May 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions IR 05000390/20220032023-05-0909 May 2023 Reissue Watts Bar Nuclear Plant - Integrated Inspection Report 05000390/2022003 and 05000391/2022003 ML23125A2202023-05-0505 May 2023 Issuance of Amendment No. 161 Regarding a Change to Footnotes for Technical Specification Table 1.1-1 Modes (Emergency Circumstances) IR 05000390/20230012023-05-0404 May 2023 Integrated Inspection Report 05000390/2023001 and 05000391/2023001 CNL-23-043, Emergency License Amendment Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical Specification Table 1.1-1, Modes (WBN-TS-23-09)2023-05-0404 May 2023 Emergency License Amendment Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical Specification Table 1.1-1, Modes (WBN-TS-23-09) CNL-23-032, Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 412023-04-27027 April 2023 Clinch River, Sequoyah, Units 1 and 2, Watts Bar, Unit 1 and 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 41 CNL-23-030, Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status Update2023-04-27027 April 2023 Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status Update CNL-23-033, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revision2023-04-24024 April 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revision CNL-23-029, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-04-11011 April 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions ML23072A0652023-04-0505 April 2023 Units 1 and 2 Issuance of Amendment Nos. 364 and 358; 160 and 68 Regarding a Revision to Technical Specification 3.4.12 ML23073A2762023-04-0303 April 2023 Individual Notice of Consideration of Issuance of Amendments to Facility Operating Licenses, Proposed No Significant Hazards Consideration Determination, and Opportunity for a Hearing (EPID L-2023-LLA-0029) (Letter) CNL-23-023, Annual Insurance Status Report2023-03-30030 March 2023 Annual Insurance Status Report CNL-23-024, TVA Guarantee of Payment of Deferred Premiums - 2022 Annual Report2023-03-29029 March 2023 TVA Guarantee of Payment of Deferred Premiums - 2022 Annual Report 2024-01-09
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARCNL-23-009, Response to Request for Additional Information Request to Revise Technical Specification 3.4.122023-01-0404 January 2023 Response to Request for Additional Information Request to Revise Technical Specification 3.4.12 CNL-22-085, Response to Request for Additional Information Regarding Sequoyah Nuclear Plant (Sqn), Units 1 and 2 and Watts Bar Nuclear Plant (Wbn), Units 1 and 2, American Society of Mechanical Engineers Operation and Maintenance Code, Request for Al2022-09-0202 September 2022 Response to Request for Additional Information Regarding Sequoyah Nuclear Plant (Sqn), Units 1 and 2 and Watts Bar Nuclear Plant (Wbn), Units 1 and 2, American Society of Mechanical Engineers Operation and Maintenance Code, Request for Alte CNL-22-064, Response to Request for Additional Information Regarding Tennessee Valley Authority License Amendment Request to Revise Emergency Plan Implementing Procedure Regarding Seismic Event Emergency Action Level Change2022-06-0909 June 2022 Response to Request for Additional Information Regarding Tennessee Valley Authority License Amendment Request to Revise Emergency Plan Implementing Procedure Regarding Seismic Event Emergency Action Level Change CNL-22-043, Response to Request for Additional Information and Confirmation of Information Regarding Application to Modify Watts Bar Nuclear Plant Units 1 and 2 Technical Specification 3.7.8 to Support Shutdown Board.2022-05-0202 May 2022 Response to Request for Additional Information and Confirmation of Information Regarding Application to Modify Watts Bar Nuclear Plant Units 1 and 2 Technical Specification 3.7.8 to Support Shutdown Board. CNL-22-060, Response to Request for Additional Information and Clarification Regarding Request for Exemption from Requirements of 10 CFR 26.205(d)(4), 26.205(d)(6) and 26.205(d)(7), Fitness for Duty Programs - Work Hours2022-04-25025 April 2022 Response to Request for Additional Information and Clarification Regarding Request for Exemption from Requirements of 10 CFR 26.205(d)(4), 26.205(d)(6) and 26.205(d)(7), Fitness for Duty Programs - Work Hours WBL-22-010, Response to Request for Confirmation of Information Regarding the Watts Bar Nuclear Plant, Unit 2, Cycle 4 Mid-Cycle Outage Generic Letter 95-05 Final Report2022-03-0202 March 2022 Response to Request for Confirmation of Information Regarding the Watts Bar Nuclear Plant, Unit 2, Cycle 4 Mid-Cycle Outage Generic Letter 95-05 Final Report CNL-21-098, Supplement to Response to Request for Additional Information Regarding Application to Modify Technical Specifications Steam Generator Inspection/Repair Program Provisions and Operating License Condition 2.C.(4)2022-01-0505 January 2022 Supplement to Response to Request for Additional Information Regarding Application to Modify Technical Specifications Steam Generator Inspection/Repair Program Provisions and Operating License Condition 2.C.(4) CNL-21-075, Response to Request for Additional Information Regarding Expedited Application to Modify Technical Specification 3.7.12, Auxiliary Building Gas Treatment System, for One-Time Exception to Permit Opening2021-09-0808 September 2021 Response to Request for Additional Information Regarding Expedited Application to Modify Technical Specification 3.7.12, Auxiliary Building Gas Treatment System, for One-Time Exception to Permit Opening CNL-21-070, Response to Request for Additional Information Regarding Application to Modify Watts Bar Nuclear Plant, Unit 2 Technical Specifications Steam Generator Inspection/Repair Program Provisions and Unit 2 Facility Operating License Condition 22021-08-11011 August 2021 Response to Request for Additional Information Regarding Application to Modify Watts Bar Nuclear Plant, Unit 2 Technical Specifications Steam Generator Inspection/Repair Program Provisions and Unit 2 Facility Operating License Condition 2.C CNL-21-043, Response to Request for Additional Information Regarding Expedited Application for Approval to Use a Growth Rate Temperature Adjustment When Implementing the Generic Letter 95-05 Analysis for the Watts Bar Nuclear Plant2021-05-14014 May 2021 Response to Request for Additional Information Regarding Expedited Application for Approval to Use a Growth Rate Temperature Adjustment When Implementing the Generic Letter 95-05 Analysis for the Watts Bar Nuclear Plant CNL-21-041, Response to RAI Re Application to Modify the Watts Bar Nuclear Plant Technical Specifications 5.7.2.19, Containment Leakage Rate Testing Program (WBN-TS-19-01)2021-04-29029 April 2021 Response to RAI Re Application to Modify the Watts Bar Nuclear Plant Technical Specifications 5.7.2.19, Containment Leakage Rate Testing Program (WBN-TS-19-01) CNL-21-021, Response to Request for Additional Information Regarding Application to Revise Watts Bar Nuclear Plant (Wbn), Unit 1 Technical Specifications for Steam Generator Tube Inspection Frequency and to Adopt TSTF-510, .2021-03-30030 March 2021 Response to Request for Additional Information Regarding Application to Revise Watts Bar Nuclear Plant (Wbn), Unit 1 Technical Specifications for Steam Generator Tube Inspection Frequency and to Adopt TSTF-510, . CNL-21-005, Response to Request for Additional Info Re License Amendment Request to Adopt TSTF-490, Deletion of E Bar Definition & Revision to RCS Specific Activity Tech Spec (WBN-TS-20-07)2021-01-22022 January 2021 Response to Request for Additional Info Re License Amendment Request to Adopt TSTF-490, Deletion of E Bar Definition & Revision to RCS Specific Activity Tech Spec (WBN-TS-20-07) CNL-21-014, Response to Request for Additional Information for Expedited Application for Approval to Use an Alternate Method of Determining Probability of Detection for the Watts Bar Nuclear Plant, Unit 2 Steam Generators (WBN TS-391-20-024)2021-01-19019 January 2021 Response to Request for Additional Information for Expedited Application for Approval to Use an Alternate Method of Determining Probability of Detection for the Watts Bar Nuclear Plant, Unit 2 Steam Generators (WBN TS-391-20-024) CNL-20-074, Submittal of Additional Supplement to License Amendment Request for Measurement Uncertainty Recapture Power Uprate (WBN-TS-19-06)2020-08-28028 August 2020 Submittal of Additional Supplement to License Amendment Request for Measurement Uncertainty Recapture Power Uprate (WBN-TS-19-06) CNL-20-030, Response to Request for Additional Information to License Amendment Request for Measurement Uncertainty Recapture Power Uprate (WBN-TS-19-06)2020-04-29029 April 2020 Response to Request for Additional Information to License Amendment Request for Measurement Uncertainty Recapture Power Uprate (WBN-TS-19-06) CNL-19-124, Response to Request for Additional Information to Application to Modify Watts Bar Nuclear Plant Unit 2 Technical Specifications 3.7.8 to Extend the Completion Time for an Inoperable Essential Raw Cooling Water Train on a One-Time Basis (W2020-01-13013 January 2020 Response to Request for Additional Information to Application to Modify Watts Bar Nuclear Plant Unit 2 Technical Specifications 3.7.8 to Extend the Completion Time for an Inoperable Essential Raw Cooling Water Train on a One-Time Basis (WBN CNL-19-108, Response to NRC Second Request for Additional Information Regarding Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2019-10-28028 October 2019 Response to NRC Second Request for Additional Information Regarding Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors CNL-19-105, Supplemental Response to Second-Round NRC Request for Additional Information Regarding Application to Revise Technical Specifications Regarding DC Electrical Systems TSTF-500, Revision 2 (WBN-TS-18-09)2019-10-10010 October 2019 Supplemental Response to Second-Round NRC Request for Additional Information Regarding Application to Revise Technical Specifications Regarding DC Electrical Systems TSTF-500, Revision 2 (WBN-TS-18-09) CNL-19-062, Response to Second-Round NRC Request for Additional Information Regarding Application to Revise Technical Specifications Regarding DC Electrical Systems TSTF-500, Revision 2 (WBN-TS-18-09)2019-09-0404 September 2019 Response to Second-Round NRC Request for Additional Information Regarding Application to Revise Technical Specifications Regarding DC Electrical Systems TSTF-500, Revision 2 (WBN-TS-18-09) CNL-19-069, Final Response to NRC Request for Additional Information Regarding Watts Bar Nuclear Plant, Units 1 and 2, Application to Adopt 10 CFR 50.69,Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Pow2019-07-29029 July 2019 Final Response to NRC Request for Additional Information Regarding Watts Bar Nuclear Plant, Units 1 and 2, Application to Adopt 10 CFR 50.69,Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power CNL-19-068, Response to Request for Additional Information Regarding the Sequoyah Nuclear Plant (SQN) Units 1 and 2 and Watts Bar Nuclear Plant (WBN) Units 1 and 2, American Society of Mechanical Engineers Operation and Maintenance Code, Request for2019-07-22022 July 2019 Response to Request for Additional Information Regarding the Sequoyah Nuclear Plant (SQN) Units 1 and 2 and Watts Bar Nuclear Plant (WBN) Units 1 and 2, American Society of Mechanical Engineers Operation and Maintenance Code, Request for .. CNL-19-065, Partial Response to NRC Request for Additional Information Regarding Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors2019-07-15015 July 2019 Partial Response to NRC Request for Additional Information Regarding Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors CNL-19-056, Response to NRC Request for Additional Information Regarding Application to Revise Technical Specifications Regarding DC Electrical Systems TSTF-500, Revision 2, DC Electrical Rewrite - Update to TSTF-3602019-06-0707 June 2019 Response to NRC Request for Additional Information Regarding Application to Revise Technical Specifications Regarding DC Electrical Systems TSTF-500, Revision 2, DC Electrical Rewrite - Update to TSTF-360 CNL-19-033, Revised Response to Request for Additional Information Regarding Application to Modify Technical Specifications 3.8.9 Regarding Alternating Current (AC) Vital Buses (WBN-TS-17-19)2019-03-21021 March 2019 Revised Response to Request for Additional Information Regarding Application to Modify Technical Specifications 3.8.9 Regarding Alternating Current (AC) Vital Buses (WBN-TS-17-19) CNL-18-121, Response to Request for Additional Information Regarding Application to Modify Watts Bar Nuclear Plant, Units 1 and 2 Technical Specifications 3.8.9 Regarding Alternating Current (AC) Vital Buses (WBN-TS-17-19)2018-11-0909 November 2018 Response to Request for Additional Information Regarding Application to Modify Watts Bar Nuclear Plant, Units 1 and 2 Technical Specifications 3.8.9 Regarding Alternating Current (AC) Vital Buses (WBN-TS-17-19) CNL-18-128, Response to Request for Additional Information Regarding Application to Revise Technical Specifications for Use of Voltage-Based Alternate Repair Criteria in Accordance with Generic Letter 95-05 (391-WBN2-TS-17-30)2018-11-0808 November 2018 Response to Request for Additional Information Regarding Application to Revise Technical Specifications for Use of Voltage-Based Alternate Repair Criteria in Accordance with Generic Letter 95-05 (391-WBN2-TS-17-30) CNL-18-116, Response to Request for Additional Information Regarding the Application to Revise Watts Bar Nuclear Plant Unit 2 - License Condition 2.C(4) PAD4TCD (391-WBN-TS-18-03)2018-10-11011 October 2018 Response to Request for Additional Information Regarding the Application to Revise Watts Bar Nuclear Plant Unit 2 - License Condition 2.C(4) PAD4TCD (391-WBN-TS-18-03) CNL-18-113, Response to Request for Additional Information Regarding Application to Revise Watts Bar Unit 2 Technical Specification 4.2.1, Fuel Assemblies, and Watts Bar Units 1 and 2 Technical Specifications Related to Fuel Storage (WBN-TS-17-028) .2018-10-0404 October 2018 Response to Request for Additional Information Regarding Application to Revise Watts Bar Unit 2 Technical Specification 4.2.1, Fuel Assemblies, and Watts Bar Units 1 and 2 Technical Specifications Related to Fuel Storage (WBN-TS-17-028) ... CNL-18-104, Submittal of Revised Response to Request for Additional Information Regarding Application to Modify Plant Technical Specifications to Extend Surveillance Requirements 3.3.1.5, 3.3.2.2 and 3.3.6.2 Specified Intervals2018-07-30030 July 2018 Submittal of Revised Response to Request for Additional Information Regarding Application to Modify Plant Technical Specifications to Extend Surveillance Requirements 3.3.1.5, 3.3.2.2 and 3.3.6.2 Specified Intervals CNL-18-102, Response to Request for Additional Information Regarding Application to Modify Watts Bar Nuclear Plant Unit 1 Technical Specifications to Extend Surveillance Requirement 3.3.1.5, 3.3.2.2, and 3.3.6.2 Specified ...2018-07-24024 July 2018 Response to Request for Additional Information Regarding Application to Modify Watts Bar Nuclear Plant Unit 1 Technical Specifications to Extend Surveillance Requirement 3.3.1.5, 3.3.2.2, and 3.3.6.2 Specified ... ML18155A4872018-06-0404 June 2018 Response to Request for Additional Information Regarding Cycle 1 Steam Generator Tube Inspection Report CNL-18-061, Response to NRC Request for Supplemental Information Related to Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools2018-05-31031 May 2018 Response to NRC Request for Supplemental Information Related to Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools CNL-18-058, Supplement to Application to Revise Watts Bar Nuclear Plant Unit 2 - License Condition 2.C(4) PAD4TCD (391-WBN-TS-18-03)2018-04-27027 April 2018 Supplement to Application to Revise Watts Bar Nuclear Plant Unit 2 - License Condition 2.C(4) PAD4TCD (391-WBN-TS-18-03) NL-18-044, Browns Ferry Units 1, 2, and 3; Sequoyah Units 1 and 2; Watts Bar Units 1 and 2 - Tennessee Valley Authority Response to NRC Request for Additional Information Related to Topical Report TVA-NPG-AWA16, TVA Overall Basin Probable Maximum Pre2018-04-19019 April 2018 Browns Ferry Units 1, 2, and 3; Sequoyah Units 1 and 2; Watts Bar Units 1 and 2 - Tennessee Valley Authority Response to NRC Request for Additional Information Related to Topical Report TVA-NPG-AWA16, TVA Overall Basin Probable Maximum Prec CNL-18-044, Tennessee Valley Authority Response to NRC Request for Additional Information Related to Topical Report TVA-NPG-AWA16, TVA Overall Basin Probable Maximum Precipitation.2018-04-19019 April 2018 Tennessee Valley Authority Response to NRC Request for Additional Information Related to Topical Report TVA-NPG-AWA16, TVA Overall Basin Probable Maximum Precipitation. CNL-18-018, Supplement to Application to Revise Watts Bar Unit 2 Technical Specification 4.2.1, Fuel Assemblies, and Watts Bar Units 1 and 2 Technical Specifications Related to Fuel Storage (WBN-TS-17-028)2018-02-15015 February 2018 Supplement to Application to Revise Watts Bar Unit 2 Technical Specification 4.2.1, Fuel Assemblies, and Watts Bar Units 1 and 2 Technical Specifications Related to Fuel Storage (WBN-TS-17-028) CNL-18-012, Response to Request for Additional Information and Revision 1 to Technical Specification Change - Reactor Coolant Temperature Indicator Inoperable - Exigent Amendment (391-WBN-TS-2018-01)2018-01-17017 January 2018 Response to Request for Additional Information and Revision 1 to Technical Specification Change - Reactor Coolant Temperature Indicator Inoperable - Exigent Amendment (391-WBN-TS-2018-01) CNL-17-108, Response to Request for Additional Information Regarding Request to Modify Technical Specification 3.3.1, Reactor Protection System Instrumentation2017-08-31031 August 2017 Response to Request for Additional Information Regarding Request to Modify Technical Specification 3.3.1, Reactor Protection System Instrumentation CNL-17-098, Revised Response to NRC Request for Additional Information Related to TVA Fleet License Amendment Request to Adopt NEI 99-01 Revision 6 Emergency Action Levels2017-07-27027 July 2017 Revised Response to NRC Request for Additional Information Related to TVA Fleet License Amendment Request to Adopt NEI 99-01 Revision 6 Emergency Action Levels CNL-17-093, Revised Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specification 3.7.12, Auxiliary Building Gas Treatment System (ABGTS)2017-07-21021 July 2017 Revised Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specification 3.7.12, Auxiliary Building Gas Treatment System (ABGTS) CNL-17-091, Response to Request for Additional Information Regarding Request for Approval of a Relief from the ASME Section XI Coverage Examinations for Preservice Inspection (PSI) - Number WBN-2/PSI-1, Revision 1, and Submittal of the Wbn..2017-07-14014 July 2017 Response to Request for Additional Information Regarding Request for Approval of a Relief from the ASME Section XI Coverage Examinations for Preservice Inspection (PSI) - Number WBN-2/PSI-1, Revision 1, and Submittal of the Wbn.. CNL-17-085, Response to NRC Request for Additional Information Related to TVA Fleet License Amendment Request to Adopt NEI 99-01 Revision 6 Emergency Action Levels2017-07-0707 July 2017 Response to NRC Request for Additional Information Related to TVA Fleet License Amendment Request to Adopt NEI 99-01 Revision 6 Emergency Action Levels CNL-17-071, Seismic Probabilistic Risk Assessment, Response to NRC Request for Information Pursuant to 10CFR50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2017-06-30030 June 2017 Seismic Probabilistic Risk Assessment, Response to NRC Request for Information Pursuant to 10CFR50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident CNL-17-066, Response to Request for Additional Information Regarding License Amendment Request for One-Time Extension of Technical Specification Surveillance Requirements Group 2 (LAR Encl. 1 Attachments 5, 6, 7, 9, 12, 13, 14, 15, 16, and 17)2017-06-0909 June 2017 Response to Request for Additional Information Regarding License Amendment Request for One-Time Extension of Technical Specification Surveillance Requirements Group 2 (LAR Encl. 1 Attachments 5, 6, 7, 9, 12, 13, 14, 15, 16, and 17) CNL-17-062, Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications Regarding Ice Condenser Containment Ice Mass Requirements2017-05-19019 May 2017 Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications Regarding Ice Condenser Containment Ice Mass Requirements CNL-17-044, Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specification 3.7.12, Auxiliary Building Gas Treatment System (Abgts), for Watts Bar Nuclear Plant, Units 1 and 22017-05-0505 May 2017 Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specification 3.7.12, Auxiliary Building Gas Treatment System (Abgts), for Watts Bar Nuclear Plant, Units 1 and 2 CNL-17-039, Response to NRC Request for Information, Per 10CFR50.54(f) Regarding Recommendations 2.1, 2.3 and 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident - Withdrawal of Regulatory..2017-03-10010 March 2017 Response to NRC Request for Information, Per 10CFR50.54(f) Regarding Recommendations 2.1, 2.3 and 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident - Withdrawal of Regulatory.. CNL-17-029, Response to Request for Additional Information Regarding License Amendment Request for a One-Time Extension of Technical Specification Surveillance Requirements for AC Sources2017-03-0606 March 2017 Response to Request for Additional Information Regarding License Amendment Request for a One-Time Extension of Technical Specification Surveillance Requirements for AC Sources CNL-17-020, Response to RAI Regarding License Amendment Request for One-Time Extension of Technical Specification Surveillance Requirements Group 1 - LAR Attachments 8, 10, and 112017-02-16016 February 2017 Response to RAI Regarding License Amendment Request for One-Time Extension of Technical Specification Surveillance Requirements Group 1 - LAR Attachments 8, 10, and 11 2023-01-04
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Response to Request for Additional Information Regarding Application to Revise Watts Bar Unit 2 Technical Specification 4.2.1, "Fuel Assemblies," and Watts Bar Units 1 and 2 Technical Specifications Related to Fuel Storage (WBN-TS-17-028) (EPID L-2017-LLA-0427)
Response to Request for Additional Information Regarding Application to Revise Watts Bar Unit 2 Technical Specification 4.2.1, "Fuel Assemblies," and Watts Bar Units 1 and 2 Technical Specifications Related to Fuel Storage (WBN-TS-17-028) (EPID L-2017-LLA-0427)
By application dated December 20, 2017 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML17354B282), as supplemented February 15, and April 9, 2018 (ADAMS Accession Nos. ML18047A181 and ML18100A953, respectively), Tennessee Valley Authority (TVA or the licensee) submitted a proposed license amendment request (LAR) to authorize up 1,792 tritium producing burnable absorber rods (TPBARs) that can be irradiated in the reactor for Watts Bae [sic] Nuclear Plant (WBN), Unit 2. In addition, the proposed LAR requests changes to WBN Unit 1 and 2 Technical Specifications (TSs) related to fuel storage.
The requested changes would revise WBN Unit 2 TS 4.2.1, "Fuel Assemblies," to authorize up to 1,792 Tritium Producing Burnable Absorber Rods (TPBARs) that can be irradiated in the reactor.
Specifically, the requested changes revise WBN Units 1 and 2 TS 3.7.15, "Spent Fuel Assembly Storage," to simplify the fuel storage limitations on fuel assemblies by eliminating the burnup-related criteria. The requested changes add WBN Units 1 and 2 TS 3.7.18, "Fuel Storage Pool Boron Concentration," to specify the minimum fuel storage pool boron concentration when fuel is stored in the pool. The requested changes revise WBN Units 1 and 2 TS 3.9.9, "Spent Fuel Pool Boron Concentration," to modify the minimum fuel storage pool boron concentration during refueling operations when fuel is stored in the pool. The requested changes revise WBN Units 1 and 2 TS 4.3, "Fuel Storage," to replace the storage limitations on fuel assembly burnup and storage with a single requirement to maintain a specified boron concentration in the spent fuel pool (SFP). The requested changes add WBN Units 1 and 2 TS 5.7.2.21, "Spent Fuel Storage Rack Neutron Absorber Monitoring Program."
The NRC staff has reviewed TVA's submittal, as well as supplements, and determined that additional information is required to enable the U.S. Nuclear Regulatory Commission (NRC) staff to make an independent assessment regarding its technical review.ARCB-RAI-1 In the application on page E1-23 of 116 in the Primary and Secondary Coolant Concentrations section it states:
The concentration of tritium for a TPC was calculated using the same methodology as used for WBN U1, which involved 1,792 TPBARs with a permeation rate of 5 Ci/TPBAR/year and two failures - The total annual tritium expected from TPBARs is based on 1792 TPBARs and a permeation rate of 5 Ci/TPBAR/year (8960 Ci/year). This results in an average tritium concentration of 11.4 Ci/gm. The concentration with 2 TPBAR failures was determined by adding the inventory of 2 TPBARs to the average amount of tritium in the RCS and dividing by the RCS mass. The average amount of tritium was determined by multiplying the average tritium concentration determined above by the RCS mass. Each TPBAR is assumed to have a maximum of 11,600 Ci at the end of a cycle. This resulted in an expected tritium concentration in the primary coolant of approximately 120 Ci/gm for 2 TPBAR failures.
In the application it is also states numerous times that this LAR is based on WBN unit 1 license amendment 40. However, WBN unit 1 license amendment 40 has been superseded by license amendment 107 and in supplement to the application dated March 31, 2016 (ADAMS Accession number ML16095A064) on page Enclosure 2, page 8 of 40, it states:
Non-LOCA Accident Source Term: This source term is used for evaluation of abnormal operational occurrences (AOOs) and postulated accidents (PAs). It was updated to reflect a new permeation rate of 10 Ci/TPBAR/year, which bounds the realistic permeation rate with 100% margin. It also has increased margin by assuming ~40% more TPBARs are loaded (i.e., 2,500 TPBARs). It continues to retain conservatism regarding the inclusion of two failed TPBARs. This bounding approach to source term assumptions for accidents is consistent with the accident evaluation methodology. The modified source term provides sufficient margin to bound AOO and PA cases.
Furthermore, Enclosure 2, page 37 of 40 states:
-the source term is the primary and secondary coolant activity. The primary and secondary coolant activities are in accordance with ANSI/ANS-18.1-1984, except for tritium. ... This source term was updated to reflect a new permeation rate of 10 Ci/TPBAR/year, which bounds the realistic permeation rate with 100% margin. It continues to retain conservatism regarding the inclusion of two failed TPBARs. - WBN Unit 1 License Amendment 40 and the current licensing basis determined the expected tritium concentration assuming a permeation rate of 1 Ci/TPBAR/year, 2,304 total TPBARs, and two failed TPBARs. ... The assumed RCS tritium activity to support the requested changes is based on 2,500 TPBARs with an assumed permeation rate of 10 Ci/TPBAR/year and two failed TPBARs. This results in a concentration of 124.9 Ci/gm. The design basis accident assumptions for WBN Unit 1 appears to be different from that stated for WBN Unit 2, and the NRC staff is unclear which one is being requested in this license amendment request.
Please clarify, for the DBAs that assume primary and secondary coolant concentrations as their source term, what reactor coolant system tritium concentration is assumed and what is it based on, such as a permeation rate, total TPBARs, and how many failed TPBARs.TVA Response to ARCB-RAI-1
ARCB-RAI-2 In the application on page E1-26 of 116 it states:
Table 4.1-6 and 4.1-7 contain a tabulation of common control room parameters and the atmospheric dispersion factors, respectively, used in each of the design basis analyses. These are the same parameters that supported the review for NUREG-0847 Supplement 25 except for the control room isolation time, which has been corrected to account for an error.
Table 4.1-7, Atmospheric Dispersion Factors states:
1 - This is used for the Containment FHA [Fuel Handling Accident] 2 - This is used for the Containment FHA after containment is isolated and for the Auxiliary Building FHA In NUREG-0847 Supplement 25 Tables 15.5 and 15.6 it states that the control room atmospheric dispersion factor for the FHA in closed containment, FHA inside open containment, and FHA in the Auxiliary Building for the time period 0 to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> is 2.59E-3 seconds per cubic meter. This control room atmospheric dispersion factor is different from those stated in the license amendment request for the FHA.
Explain which control room atmospheric dispersion factor(s) for the FHA are being requested in this license amendment. If they differ from the current licensing basis as stated in Tables 15.5 and 15.6 of NUREG-0847 Supplement 25 then provide the technical basis for the change.TVA Response to ARCB-RAI-2
MCCB RAI #1: Title 10 of the Code of Federal Regulations (10 CFR), Section 50.68, "Criticality accident requirements," provides the regulatory requirements for maintaining sub-criticality in the spent fuel pool (SFP). Specifically, 10 CFR 50.68(b)(4) states that the k-effective in the SFP:
-must not exceed 0.95, at a 95 percent probability, 95 percent confidence level, if flooded with borated water, and the k-effective must remain below 1.0 (subcritical), at a 95 percent probability, 95 confidence level, if flooded with unborated water.
In the proposed Technical Specification (TS) 5.7.2.21 "Spent Fuel Storage Rack Neutron Absorber Monitoring Program," the licensee states that the program will be used to verify the "-neutron absorber density is consistent with the assumptions in the spent fuel pool [SFP] criticality analysis." However, the Boron-10 (B-10) areal density (AD) is the main property of the neutron absorbing material (NAM) that needs to be verified with respect to the SFP criticality analysis, not the neutron absorber density. Explain why the density of the NAM is specifically cited in the proposed TS, instead of the B-10 AD, which is more important assumption used in the SFP criticality analysis.TVA Response to MCCB RAI #1
DORL RAI #1 In the submittal dated December 20, 2017, Enclosure 6 contains a commitment to replace the Containment Isolation Thermal Relief Check Valves on the WBN Unit 2 supply lines to Containment for the Component Cooling Water (CCW) System and Essential Raw Cooling Water (ERCW) System with simple relief valves. TVA states that the simple relief valves will be installed prior to loading TPBARs in the WBN Unit 2 reactor core. The WBN Unit 2 Facility Operating License (FOL) NPF-96 expires October 21, 2055. There are numerous refueling outages (RFOs) between now and the end of the FOL. Has TVA scheduled a RFO to replace the Containment Isolation Thermal Relief Check Valves with simple relief valves? If so, which RFO is this work planned to be completed? If the valves are not replaced prior to the completion of this LAR, the NRC will add this as a license condition to FOL NPR-96. TVA Response to DORL RAI #1 DORL RAI #2 In the submittal dated December 20, 2017, TVA requests that the license amendment be implemented prior to startup from the outage where any number of TPBARs is inserted in the WBN Unit 2 reactor core. The WBN Unit 2 FOL expires October 21, 2055. There are numerous RFOs between now and the end of the FOL. Potentially, this amendment could be effective but remain not implemented for decades. Does TVA have a schedule to install TPBARs in WBN Unit 2? If so, which RFO is the TPBARs scheduled to be installed for WBN Unit 2? Are the WBN Unit 2 TPBARs scheduled to be installed during the Cycle 4 RFO in the fall of 2020? Is there a contingency plan if the TPBARs are not installed in WBN Unit 2 as planned that RFO? For example, if TVA plans to install TPBARs in WBN Unit 2 during the Cycle 4 RFO in the fall of 2020, but for some reason is not able to, what is TVA's contingency plan? TVA Response to DORL RAI #2 DORL RAI #3 What was the permeation rate for Cycle 13 of WBN Unit 1? What was the permeation rate of Cycle 14 of WBN Unit 1? What has TVA learned from the testing of the TPBARs from Cycles 13 and 14?
TVA Response to DORL RAI #3 Tritium Permeation Rate for TPBARs in Cycle 13 and Cycle 14 Total Cycle Last 365 Days of Cycle
TTotal (t) = TCurrent RCS Inventory (t)
+ TRemoved Letdown (t)
Tnon-TPBAR (t)
= TSoluble Boron (t)
+ TLithium (t)
+ TFuel Rods (t)
+ TBurnable Absorbers (t)
+ TControl Rods (t)
+ TSecondary Source Rods (t)
TTPBAR (t) = TTotal (t) - Tnon-TPBAR (t)
Summary of WBN Unit 1 Cycle 13 and Cycle 14 PIE on the Lead Use/Surveillance TPBARs WBN Unit 1 Cycle TPBAR Design Number of Rods Examined Focus of Examinations
SNPB RAI #1 During the acceptance review of this LAR, NRC staff requested supplemental information and TVA responded on February 15, 2018 in a letter CNL-18-018. The supplemental information requested was to clarify the discrepancy between the fluence results from WCAP-18191-NP and WCAP-17035-NP for Watts Bar Unit 2 regarding the change reported inside surface neutron fluence for the RPV at 32 EFPY (1861 E+19 n/cm 2 from WCAP-18191-NP versus 3.17 E+19 n/cm 2 from WCAP-17035-NP). The TVA response provides a comparison of the power distribution of Cycle 7 in WCAP-18191 (low leakage pattern) and the radial power distribution used in WCAP-17035 (out-in pattern) in Tables 1 and 2. It was shown that the average of the relative power in the peripheral assemblies for low leakage pattern used in WCAP-18192 for Cycle 7 is 0.590 (Table 1) while the average of the relative power in the peripheral assemblies for out-in pattern used in WCAP-17035 is 0.97. However, a vast majority of the relative powers of the interior assemblies in Table 1 show increased relative powers compared to those listed in Table 2. Please provide an explanation for why the relative powers of the interior assemblies in Table 1 is greater than those of the Table 2.
TVA Response to SNPB RAI #1
SNPB RAI #2 It is stated in TVA response (CNL-18-018) that the average peripheral power increases the number of TPBARs. Also the maximum RPV flux increases from 1.351E10 n/cm 2-s to 1.687E10 n/cm2-s between Cycle 3 and Cycle 4. Furthermore, the maximum RPV flux further increases in Cycle 5 to about 1.95E10 n/cm2-s through Cycle 7. While these increases in maximum RPV flux cannot be solely associated with the implementation of TPBARs, the anticipated loading patterns including TPBARs (Cycles 4 through7) will impart a greater maximum flux on the reactor vessel than Cycle 3 which does not include TPBARs.
(a) Please describe the factors that contribute to the increase in RPV flux as the number of TBBARs increase.
Provide data on the flux values from both out-in pattern and low leakage patterns used in WCAP-18191 and WCAP-17035, respectively. TVA Response to SNPB RAI #2
Calculated Maximum Fast Neutron Exposure Rate Excerpted from Table 2-4 of WCAP-18191 Cycle Neutron Flux (E > 1.0 MeV) [n/cm2-s]