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| | issue date = 04/19/2018 | | | issue date = 04/19/2018 |
| | title = Request for Proposed Technical Specification (TS) Change TS-519 License Amendment Request - Change to Unit 1 License Condition 2.C(18)(a)3, Supplement 1 | | | title = Request for Proposed Technical Specification (TS) Change TS-519 License Amendment Request - Change to Unit 1 License Condition 2.C(18)(a)3, Supplement 1 |
| | author name = Shea J W | | | author name = Shea J |
| | author affiliation = Tennessee Valley Authority | | | author affiliation = Tennessee Valley Authority |
| | addressee name = | | | addressee name = |
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| =Text= | | =Text= |
| {{#Wiki_filter:, 1101 Market Street, Chattanooga, Tennessee 37402 CNL-18-0 62 April 19 , 201 8 10 CFR 50.90 ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, D.C. 20555 | | {{#Wiki_filter:Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402 CNL-18-062 April 19, 2018 10 CFR 50.90 ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Browns Ferry Nuclear Plant, Unit 1 Renewed Facility Operating License No. DPR-33 NRC Docket No. 50-259 |
| -0001 Browns Ferry Nuclear Plant, Unit 1 Renewed Facility Operating License No. DPR-33 NRC Docket No. | |
| 50-259 | |
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| ==Subject:== | | ==Subject:== |
| | Request for Proposed Technical Specification (TS) Change TS-519 License Amendment Request - Change to Unit 1 License Condition 2.C(18)(a)3, Supplement 1 |
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| ==References:== | | ==References:== |
| : 1. NRC Letter to TVA, "Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Issuance of Amendments Regarding Extended Power Uprate (CAC Nos. MF6741, MF6742, and MF6743)," dated August 14, 2017 (ML17032A120) | | : 1. NRC Letter to TVA, Browns Ferry Nuclear Plant, Units 1, 2, and 3 - |
| : 2. TVA Letter to NRC, "Request for Proposed Technical Specification (TS) Change TS-519 License Amendment Request - Change to Unit 1 License Condition 2.C(18)(a)3," dated March 16, 2018 By the Reference 1 letter, the NRC issued License Amendment Nos. 299, 323, and 283 to the BFN Renewed Facility Operating Licenses (RFOLs) to increase the authorized maximum power level from 3458 megawatts thermal (MWt) to 3952 MWt. The amendments included specific license conditions that required certain monitoring, evaluation, and response actions to potential adverse flow effects as a result of the EPU on plant structures, systems and components (including verifying the continued structural integrity of the replacement steam dryer (RSD)) during the initial EPU power ascension. One aspect of the License Condition 2.C(18)(a)3 for Unit 1 requires the submittal of a revised BFN Unit 1 RSD analysis utilizing the BFN Unit 3 on-dryer strain gauge based end | | Issuance of Amendments Regarding Extended Power Uprate (CAC Nos. MF6741, MF6742, and MF6743), dated August 14, 2017 (ML17032A120) |
| -to-end bias and uncertainties (B | | : 2. TVA Letter to NRC, Request for Proposed Technical Specification (TS) |
| &Us) at EPU conditions "at least 90 days prior to the start of the BFN Unit 1 EPU outage." | | Change TS-519 License Amendment Request - Change to Unit 1 License Condition 2.C(18)(a)3, dated March 16, 2018 By the Reference 1 letter, the NRC issued License Amendment Nos. 299, 323, and 283 to the BFN Renewed Facility Operating Licenses (RFOLs) to increase the authorized maximum power level from 3458 megawatts thermal (MWt) to 3952 MWt. The amendments included specific license conditions that required certain monitoring, evaluation, and response actions to potential adverse flow effects as a result of the EPU on plant structures, systems and components (including verifying the continued structural integrity of the replacement steam dryer (RSD)) during the initial EPU power ascension. One aspect of the License Condition 2.C(18)(a)3 for Unit 1 requires the submittal of a revised BFN Unit 1 RSD analysis utilizing the BFN Unit 3 on-dryer strain gauge based end-to-end bias and uncertainties (B&Us) at EPU conditions at least 90 days prior to the start of the BFN Unit 1 EPU outage. |
| By the Reference 2 letter, Tennessee Valley Authority (TVA) submitted a request for approval of a license amendment to reduce the time before the Browns Ferry Nuclear Plant (BFN) Unit 1 Extended Power Uprate (EPU) outage that TVA was required to submit the revised analysis of the RSD. | | By the Reference 2 letter, Tennessee Valley Authority (TVA) submitted a request for approval of a license amendment to reduce the time before the Browns Ferry Nuclear Plant (BFN) Unit 1 Extended Power Uprate (EPU) outage that TVA was required to submit the revised analysis of the RSD. |
| U.S. Nuclear Regulatory Commission CNL-18-062 Page 2 April 19, 2018 Based on delays associated with the BFN Unit 3 power ascension and the extensive review and analyses required of the BFN Unit 3 RSD power ascension test results , TVA is unable to submit the revised BFN Unit 1 RSD analysis 90 days prior to the planned October 13, 2018, start of the BFN Unit 1 EPU outage as requi r ed by the current BFN Unit 1 License Condition 2.C(18)(a)3. | | |
| The purpose of this supplement is to revise the proposed word i ng of BFN Unit 1 License Condition 2.C(18)(a)3 to reflect submittal of the revised BFN Unit 1 RSD analysis 60 days prior to exceeding 3458 MWt after the BFN Unit 1 EPU outage. A revised evaluation of the proposed change is provided in the Enclosure to this letter. Attachment 1 to the enclosure provides a revised markup of the affected renewed facility operating license page indicating the proposed change. Attachment 2 to the enclosure provides a revised retype of the affected renewed facility operating license page with the proposed change incorporated. As discussed with NRC staff, NRC approval of this LAR is needed to ensure continued compliance wi th operating license requirements. | | U. S. Nuclear Regulatory Commission CNL-18-062 Page 2 April 19, 2018 Based on delays associated with the BFN Unit 3 power ascension and the extensive review and analyses required of the BFN Unit 3 RSD power ascension test results, TVA is unable to submit the revised BFN Unit 1 RSD analysis 90 days prior to the planned October 13, 2018, start of the BFN Unit 1 EPU outage as required by the current BFN Unit 1 License Condition 2.C(18)(a)3. The purpose of this supplement is to revise the proposed word ing of BFN Unit 1 License Condition 2.C(18)(a)3 to reflect submittal of the revised BFN Unit 1 RSD analysis 60 days prior to exceeding 3458 MWt after the BFN Unit 1 EPU outage. A revised evaluation of the proposed change is provided in the Enclosure to this letter. Attachment 1 to the enclosure provides a revised markup of the affected renewed facility operating license page indicating the proposed change. Attachment 2 to the enclosure provides a revised retype of the affected renewed facility operating license page with the proposed change incorporated . |
| This request is purely adm i nistrative in nature, in that it will only change the schedule for the BFN Unit 1 submittal. | | As discussed with NRC staff, NRC approval of this LAR is needed to ensure continued compliance with operating license requirements. This request is purely adm inistrative in nature, in that it will only change the schedule for the BFN Unit 1 submittal. |
| TVA has determined that there are no si gnificant hazards considerations associated with the proposed changes and that the Technical Specification changes qualify for a categorical exclusion from environmental review pursuant to the provisions of 1 O CFR 51.22(c)(9). | | TVA has determined that there are no significant hazards considerations associated with the proposed changes and that the Technical Specification changes qualify for a categorical exclusion from environmental review pursuant to the provisions of 10 CFR 51.22(c)(9). |
| Additionally , in accordance with 1 O CFR 50.91 (b)(1 ), TVA is sending a copy of this letter and the enclosure to the Alabama State Department of Public Health. The BFN Plant Operations Review Committee has reviewed this proposed change and determined that operation of BFN in accordance with the proposed change will not endanger the health and safety of the public. TVA requests approval of the proposed amendment by July 15, 2018 , which is 90 days prior to the start of the BFN Unit 1 refueling outage, i.e., October 13 , 2018. There are no new regulatory commitments associated with this submittal. | | Additionally, in accordance with 10 CFR 50.91 (b)(1 ), TVA is sending a copy of this letter and the enclosure to the Alabama State Department of Public Health . |
| If there are any questions or if additional information is needed, please contact Mr. Edward Schrull at (423) 751-3850. I declare under penalty of perjury that the foregoing is true and correct. Executed on the 19th day of April 2018 . . Shea Vice Pres i dent , Nuclear Regulatory Affairs and Support Services | | The BFN Plant Operations Review Committee has reviewed this proposed change and determined that operation of BFN in accordance with the proposed change will not endanger the health and safety of the public. |
| | TVA requests approval of the proposed amendment by July 15, 2018, which is 90 days prior to the start of the BFN Unit 1 refueling outage, i.e. , October 13, 2018. |
| | There are no new regulatory commitments associated with this submittal. If there are any questions or if additional information is needed, please contact Mr. Edward Schrull at (423) 751-3850. |
| | I declare under penalty of perjury that the foregoing is true and correct. Executed on the 19th day of April 2018 . |
| | . Shea Vice President, Nuclear Regulatory Affairs and Support Services |
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| ==Enclosure:== | | ==Enclosure:== |
| Evaluation of Proposed Change cc: See page 3 U. S. Nuclear Regulatory Commission CNL-18-062 Page 3 April 19, 2018 cc (Enclosure): | | Evaluation of Proposed Change cc: See page 3 |
| NRC Regional Administrator - Region II NRC Senior Resident Inspector - Browns Ferry Nuclear Plant State Health Officer, Alabama State Department of Public Health Enclosure Browns Ferry Nuclear Plant Unit 1
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| Renewed Facility Operating License No. DPR
| | U. S. Nuclear Regulatory Commission CNL-18-062 Page 3 April 19, 2018 cc (Enclosure): |
| -33 NRC Docket No. 50 | | NRC Regional Administrator - Region II NRC Senior Resident Inspector - Browns Ferry Nuclear Plant State Health Officer, Alabama State Department of Public Health |
| -259 License Amendment Request TS-519, Supplement 1
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| EVALUATION OF PROPOSED CHANGE | | Enclosure Browns Ferry Nuclear Plant Unit 1 Renewed Facility Operating License No. DPR-33 NRC Docket No. 50-259 License Amendment Request TS-519, Supplement 1 EVALUATION OF PROPOSED CHANGE |
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| Evaluation of Proposed Change Enclosure 1 of 5 | | Evaluation of Proposed Change TABLE OF CONTENTS |
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| ==SUBJECT:== | | ==SUBJECT:== |
| Reduction of Time Period Required for Submittal of the Revised Browns Ferry Nuclear Plant Unit 1 Replacement Steam Dryer Analysis 1.0 | | Reduction of Time Period Required for Submittal of the Revised Browns Ferry Nuclear Plant Unit 1 Replacement Steam Dryer Analysis 1.0 |
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| ==SUMMARY== | | ==SUMMARY== |
| DESCRIPTION | | DESCRIPTION 2.0 DETAILED DESCRIPTION |
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| 2.0 DETAILED DESCRIPTION | |
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| ==3.0 TECHNICAL EVALUATION==
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| ==4.0 REGULATORY EVALUATION== | | ==3.0 TECHNICAL EVALUATION== |
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| 4.1 APPLICABLE REGULATORY REQUIREMENTS/CRITERIA | | ==4.0 REGULATORY EVALUATION== |
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| 4.2 PRECEDENT 4.3 NO SIGNIFICANT HAZARDS CONSIDERATION | | 4.1 APPLICABLE REGULATORY REQUIREMENTS/CRITERIA 4.2 PRECEDENT 4.3 NO SIGNIFICANT HAZARDS CONSIDERATION |
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| ==4.4 CONCLUSION== | | ==4.4 CONCLUSION== |
| S | | S |
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| ==5.0 ENVIRONMENTAL CONSIDERATION== | | ==5.0 ENVIRONMENTAL CONSIDERATION== |
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| ==6.0 REFERENCES== | | ==6.0 REFERENCES== |
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| Attachments: | | Attachments: |
| : 1. Proposed Renewed Facility Operating License Change (Markup) | | : 1. Proposed Renewed Facility Operating License Change (Markup) |
| : 2. Retyped Proposed Renewed Facility Operating License Change | | : 2. Retyped Proposed Renewed Facility Operating License Change Enclosure 1 of 5 |
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| Evaluation of Proposed Change Enclosure 2 of 5 Tennessee Valley Authority (TVA) requests a license amendment to reduce the time, from 90 days before the outage to 60 days prior to exceeding 3458 MWt after the outage, that the revised Browns Ferry Nuclear Plant (BFN) Unit 1 replacement steam dryer analysis must be submitted. | | Evaluation of Proposed Change 1.0 |
| The BFN Unit 1 Extended Power Uprate (EPU) outage is scheduled to start on October 13, 2018, and based on the current BFN Unit 1 outage and power ascension schedule, BFN Unit 1 would first reach 3458 MWt after the EPU outage on November 25, 2018.
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| By the Reference 1 letter dated August 14, 2017, the NRC issued License Amendment Nos. 299, 323, and 283 to the BFN Renewed Facility Operating Licenses to increase the authorized maximum power level from 3458 megawatts thermal (MWt) to 3952 MWt.
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| The amendments included specific license conditions that required certain monitoring, evaluation, and response actions to potential adverse flow effects as a result of the EPU on plant structures, systems and components (including verifying the continued structural integrity of the replacement steam dryer (RSD)) during the initial EPU power ascension.
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| One aspec t of the new License Condition 2.C(18)(a)3 for BFN Unit 1 requires the submittal of a revised BFN Unit 1 RSD analysis utilizing the Unit 3 on
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| -dryer strain gauge based end
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| -to-end bias and uncertainties (B
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| &Us) at EPU conditions "at least 90 days prior to the start of the BFN Unit 1 EPU outage." Based on delays associated with the BFN Unit 3 power ascension and the extensive review and analyses required of the BFN Unit 3 RSD power ascension test results, TVA is unable to submit the revised BFN Unit 1 RSD analysis 90 days prior to the planned October 13, 2018, start of the BFN Unit 1 EPU outage as required by the current BFN Unit 1 License Condition 2.C(18)(a)3.
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| | ==SUMMARY== |
| | DESCRIPTION Tennessee Valley Authority (TVA) requests a license amendment to reduce the time, from 90 days before the outage to 60 days prior to exceeding 3458 MWt after the outage, that the revised Browns Ferry Nuclear Plant (BFN) Unit 1 replacement steam dryer analysis must be submitted. The BFN Unit 1 Extended Power Uprate (EPU) outage is scheduled to start on October 13, 2018, and based on the current BFN Unit 1 outage and power ascension schedule, BFN Unit 1 would first reach 3458 MWt after the EPU outage on November 25, 2018. |
| | By the Reference 1 letter dated August 14, 2017, the NRC issued License Amendment Nos. 299, 323, and 283 to the BFN Renewed Facility Operating Licenses to increase the authorized maximum power level from 3458 megawatts thermal (MWt) to 3952 MWt. The amendments included specific license conditions that required certain monitoring, evaluation, and response actions to potential adverse flow effects as a result of the EPU on plant structures, systems and components (including verifying the continued structural integrity of the replacement steam dryer (RSD)) during the initial EPU power ascension. One aspect of the new License Condition 2.C(18)(a)3 for BFN Unit 1 requires the submittal of a revised BFN Unit 1 RSD analysis utilizing the Unit 3 on-dryer strain gauge based end-to-end bias and uncertainties (B&Us) at EPU conditions "at least 90 days prior to the start of the BFN Unit 1 EPU outage." |
| | Based on delays associated with the BFN Unit 3 power ascension and the extensive review and analyses required of the BFN Unit 3 RSD power ascension test results, TVA is unable to submit the revised BFN Unit 1 RSD analysis 90 days prior to the planned October 13, 2018, start of the BFN Unit 1 EPU outage as required by the current BFN Unit 1 License Condition 2.C(18)(a)3. |
| TVA requests an administrative revision to BFN Unit 1 Renewed Facility Operating License Condition 2.C(18)(a)3 to reduce the time, from 90 days prior to the outage to 60 days prior to exceeding 3458 MWt after the outage, for submittal of the revised analysis. | | TVA requests an administrative revision to BFN Unit 1 Renewed Facility Operating License Condition 2.C(18)(a)3 to reduce the time, from 90 days prior to the outage to 60 days prior to exceeding 3458 MWt after the outage, for submittal of the revised analysis. |
| The BFN Unit 1 License Condition 2.C(18)(a)3 currently states: | | 2.0 DETAILED DESCRIPTION The BFN Unit 1 License Condition 2.C(18)(a)3 currently states: |
| At least 90 days prior to the start of the BFN Unit 1 EPU outage, TVA shall revise the BFN Unit 1 replacement steam dryer (RSD) analysis utilizing the Unit 3 on | | At least 90 days prior to the start of the BFN Unit 1 EPU outage, TVA shall revise the BFN Unit 1 replacement steam dryer (RSD) analysis utilizing the Unit 3 on-dryer strain gauge based end-to-end bias and uncertainties (B&Us) at EPU conditions, and submit the information including the updated limit curves and a list of dominant frequencies for BFN Unit 1, to the NRC as a report in accordance with 10 CFR 50.4. |
| -dryer strain gauge based end | | The proposed change is to change the '90 days prior to the start of the BFN Unit 1 EPU outage' to '60 days prior to exceeding 3458 MWt after the BFN Unit 1 EPU outage' and the revised statement of the license condition would read: |
| -to-end bias and uncertainties (B | | At least 60 days prior to exceeding 3458 MWt after the BFN Unit 1 EPU outage, TVA shall revise the BFN Unit 1 replacement steam dryer (RSD) analysis utilizing the Unit 3 on-dryer strain gauge based end-to-end bias and uncertainties (B&Us) at EPU conditions, and submit the information including the updated limit curves and a list of dominant frequencies for BFN Unit 1, to the NRC as a report in accordance with 10 CFR 50.4. |
| &Us) at EPU conditions, and submit the information including the updated limit curves and a list of dominant frequencies for BFN Unit 1, to the NRC as a report in accordance with 10 CFR 50.4. | | Enclosure 2 of 5 |
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| The proposed change is to change the '90 days prior to the start of the BFN Unit 1 EPU outage
| | Evaluation of Proposed Change |
| ' to '60 days prior to exceeding 3458 MWt after the BFN Unit 1 EPU outage' and the revised statement of the license condition would read:
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| At least 60 days prior to exceeding 3458 MWt after the BFN Unit 1 EPU outage, TVA shall revise the BFN Unit 1 replacement steam dryer (RSD) analysis utilizing the Unit 3 on-dryer strain gauge based end
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| -to-end bias and uncertainties (B
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| &Us) at EPU conditions, and submit the information including the updated limit curves and a list
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| of dominant frequencies for BFN Unit 1, to the NRC as a report in accordance with 10 CFR 50.4.
| | ==3.0 TECHNICAL EVALUATION== |
| Evaluation of Proposed Change Enclosure 3 of 5 The request for reducing the time, from 90 days before the outage to 60 days prior to exceeding 3458 MWt after the outage, at which the revised analysis must be submitted is not a technical or safety issue. The license condition requirement is to submit the revised analysis to the NRC. There is no requirement for review and approval of the revised analysis to satisfy the license condition. Therefore, the proposed change is purely an administrative change. When proposing the current license condition, TVA had anticipated a more compact BFN Unit 3 power ascension schedule, even considering time for the required NRC reviews of the interim stress data.
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| Based on the current BFN Unit 3 power ascension test schedule, BFN Unit 3 will not reach full EPU power until July 9, 2018. The BFN Unit 3 on | | The request for reducing the time, from 90 days before the outage to 60 days prior to exceeding 3458 MWt after the outage, at which the revised analysis must be submitted is not a technical or safety issue. The license condition requirement is to submit the revised analysis to the NRC. There is no requirement for review and approval of the revised analysis to satisfy the license condition. Therefore, the proposed change is purely an administrative change. |
| -dryer and main steam line (MSL) measurements will be available shortly after this time. Using this measured MSL data from BFN Unit 3, General Electric - Hitachi Nuclear Energy (GEH) will develop PBLE02 load definition s and re-perform the stress analysis for BFN Unit 3 RSD using the BFN | | When proposing the current license condition, TVA had anticipated a more compact BFN Unit 3 power ascension schedule, even considering time for the required NRC reviews of the interim stress data. |
| -specific bias and uncertainty and transfer function at EPU conditions. The required duration for performance of the BFN Unit 3 PBLE02 analysis of the RSD by GEH is from July 9, 2018, to September 26, 2018. Once available, the Minimum Alternating Stress Ratio from BFN Unit 3 PBLE02 analysis and the on | | Based on the current BFN Unit 3 power ascension test schedule, BFN Unit 3 will not reach full EPU power until July 9, 2018. The BFN Unit 3 on-dryer and main steam line (MSL) measurements will be available shortly after this time. Using this measured MSL data from BFN Unit 3, General Electric - Hitachi Nuclear Energy (GEH) will develop PBLE02 load definitions and re-perform the stress analysis for BFN Unit 3 RSD using the BFN-specific bias and uncertainty and transfer function at EPU conditions. The required duration for performance of the BFN Unit 3 PBLE02 analysis of the RSD by GEH is from July 9, 2018, to September 26, 2018. Once available, the Minimum Alternating Stress Ratio from BFN Unit 3 PBLE02 analysis and the on-dryer pressure loads developed from BFN Unit 3 MSL EPU measurements will be used by GEH for revising the BFN Unit 1 RSD analysis and developing updated BFN Unit 1 RSD limit curves. GEH will develop and provide a report including the revised BFN Unit 1 RSD analysis, including updated limit curves and a list of dominant frequencies, to TVA by October 8, 2018. Upon receipt of the report from GEH, TVA will develop, review, and process the NRC submittal in accordance with TVA procedures. This report is expected to be submitted to NRC in accordance with 10 CFR 50.4, Written communications, by October 10, 2018. Therefore, based on the current BFN Unit 1 EPU outage and power ascension schedule and the proposed revised wording of the BFN Unit License Condition 2.C(18)(a)3, BFN Unit 1 would remain at 3458 MWt until the 60-day time period has elapsed (i.e., December 9, 2018). |
| -dryer pressure loads developed from BFN Unit 3 MSL EPU measurements will be used by GEH for revising the BFN Unit 1 RSD analysis and developing updated BFN Unit 1 RSD limit curves. GEH will develop and provide a report including the revised BFN Unit 1 RSD analysis, including updated limit curves and a list of dominant frequencies, to TVA by October 8, 2018. Upon receipt of the report from GEH, TVA will develop, review, and process the NRC submittal in accordance with TVA procedures. | | The proposed change ensures that current delays in the BFN Unit 3 power ascension testing do not delay the start of the BFN Unit 1 EPU outage or startup to the previous license thermal power of 3458 MWt after the outage, while providing the NRC with a 60-day time period for review of the revised BFN Unit 1 RSD analysis. |
| This report is expected to be submitted to NRC in accordance with 10 CFR 50.4, Written communications, by October 10, 2018. Therefore, based on the current BFN Unit 1 EPU outage and power ascension schedule and the proposed revised wording of the BFN Unit License Cond ition 2.C(18)(a)3, BFN Unit 1 would remain at 3458 MWt until the 60 | | The timing for submittal of the revised analysis is a requirement of a license condition included in the Renewed Facility Operating License. As such, a change to the timing for submittal of the revised analysis is a change to the operating license for the unit. |
| -day time period has elapsed (i.e., December 9, 2018). | |
| The proposed change ensures that current delays in the BFN Unit 3 power ascension testing do not delay the start of the BFN Unit 1 EPU outage or startup to the previous license thermal power of 3458 MWt after the outage, while providing the NRC with a 60 | |
| -day time period for review of the revised BFN Unit 1 RSD analysis. The timing for submittal of the revised analysis is a requirement of a license condition included in the Renewed Facility Operating License. | |
| As such, a change to the timing for submittal of the revised analysis is a change to the operating license for the unit. | |
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| 4.1 APPLICABLE REGULATORY REQUIREMENTS/CRITERIA The proposed change has been evaluated to determine whether applicable regulations and requirements continue to be met. | | ==4.0 REGULATORY EVALUATION== |
| TVA has determined that the proposed change does not require any exemptions or relief from regulatory requirements other than the operating license.
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| | 4.1 APPLICABLE REGULATORY REQUIREMENTS/CRITERIA The proposed change has been evaluated to determine whether applicable regulations and requirements continue to be met. TVA has determined that the proposed change does not require any exemptions or relief from regulatory requirements other than the operating license. |
| The following applicable regulations and regulatory requirements were reviewed in making this determination: | | The following applicable regulations and regulatory requirements were reviewed in making this determination: |
| permit Evaluation of Proposed Change Enclosure 4 of 5 omment; State consultation 4.2 PRECEDENT | | * 10 CFR 50.90, Application for amendment of license, construction permit, or early site permit Enclosure 3 of 5 |
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| License Amendment No. 305 to Renewed Facility Operating License No. DPR | | Evaluation of Proposed Change |
| -56 for the Peach Bottom Atomic Power Station Unit 3, approved by the NRC on August 11, 2015 (ML15189A185), involved a reduction I relaxation of a required submittal schedule for the revised replacement steam dryer analysis from "at least 90 days prior to the start of the Peach Bottom Unit 3 EPU outage-" to "at least 30 days prior to the start of the Peach Bottom Unit 3 EPU outage..." | | * 10 CFR 50.91, Notice for public comment; State consultation |
| | | * 10 CFR 50.92, Issuance of amendment 4.2 PRECEDENT License Amendment No. 305 to Renewed Facility Operating License No. DPR-56 for the Peach Bottom Atomic Power Station Unit 3, approved by the NRC on August 11, 2015 (ML15189A185), involved a reduction I relaxation of a required submittal schedule for the revised replacement steam dryer analysis from at least 90 days prior to the start of the Peach Bottom Unit 3 EPU outage to at least 30 days prior to the start of the Peach Bottom Unit 3 EPU outage... |
| 4.3 NO SIGNIFICANT HAZARDS CONSIDERATION | | 4.3 NO SIGNIFICANT HAZARDS CONSIDERATION Tennessee Valley Authority (TVA) has evaluated whether or not a significant hazards consideration is involved with the proposed amendment by focusing on the three standards set forth in 10 CFR 50.92, "Issuance of amendment," as discussed below: |
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| Tennessee Valley Authority (TVA) has evaluated whether or not a significant hazards consideration is involved with the proposed amendment by focusing on the three standards set forth in 10 CFR 50.92, "Issuance of amendment," as discussed below: | |
| : 1. Does the proposed amendment involve a significant increase in the probability or consequences of an accident previously evaluated? | | : 1. Does the proposed amendment involve a significant increase in the probability or consequences of an accident previously evaluated? |
| Response: No. | | Response: No. |
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| : 2. Does the proposed amendment create the possibility of a new or different kind of accident from any accident previously evaluated? | | : 2. Does the proposed amendment create the possibility of a new or different kind of accident from any accident previously evaluated? |
| Response: No. | | Response: No. |
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| The proposed license amendment reduces the length of time, from 90 days prior to the outage to 60 days prior to exceeding 3458 MWt after the outage, by which a revised analysis of the BFN Unit 1 RSD must be submitted to the NRC for information. The proposed amendment is purely administrative and has no technical or safety aspects. Therefore, the proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated. | | The proposed license amendment reduces the length of time, from 90 days prior to the outage to 60 days prior to exceeding 3458 MWt after the outage, by which a revised analysis of the BFN Unit 1 RSD must be submitted to the NRC for information. The proposed amendment is purely administrative and has no technical or safety aspects. Therefore, the proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated. |
| | Enclosure 4 of 5 |
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| Evaluation of Proposed Change Enclosure 5 of 5 3. Does the proposed amendment involve a significant reduction in a margin of safety? | | Evaluation of Proposed Change |
| | : 3. Does the proposed amendment involve a significant reduction in a margin of safety? |
| Response: No. | | Response: No. |
| The proposed license amendment reduces the length of time, from 90 days prior to the outage to 60 days prior to exceeding 3458 MWt after the outage, by which a revised analysis of the BFN Unit 1 RSD must be submitted to the NRC for information. | | The proposed license amendment reduces the length of time, from 90 days prior to the outage to 60 days prior to exceeding 3458 MWt after the outage, by which a revised analysis of the BFN Unit 1 RSD must be submitted to the NRC for information. The proposed amendment is purely administrative and has no technical or safety aspects. Therefore, the proposed change does not involve a significant reduction in a margin of safety. |
| The proposed amendment is purely administrative and has no technical or safety aspects. Therefore, th e proposed change does not involve a significant reduction in a margin of safety. | |
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| Based on the above, TVA concludes that the proposed amendment does not involve a significant hazards consideration under the standards set forth in 10 CFR 50.92(c) and, accordingly, a finding of no significant hazards consideration is justified. | | Based on the above, TVA concludes that the proposed amendment does not involve a significant hazards consideration under the standards set forth in 10 CFR 50.92(c) and, accordingly, a finding of no significant hazards consideration is justified. |
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| ==4.4 CONCLUSION== | | ==4.4 CONCLUSION== |
| S | | S In conclusion, based on the considerations discussed above, (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public. |
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| | ==5.0 ENVIRONMENTAL CONSIDERATION== |
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| | A review has determined that the proposed amendment does not change any technical requirement with respect to the installation or use of a facility component located within the restricted area, as defined in 10 CFR 20, and does not change any inspection or surveillance requirement. The proposed amendment does not involve (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amounts of any effluent that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure. Accordingly, the proposed amendment meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(10). Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the proposed amendment. |
| | 6.0 REFERENCE |
| | : 1. Letter from NRC to TVA, Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Issuance of Amendments Regarding Extended Power Uprate (CAC Nos. MF6741, MF6742, and MF6743), dated August 14, 2017 (ML17032A120). |
| | Enclosure 5 of 5 |
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| | ATTACHMENT 1 Proposed Renewed Facility Operating License Change (Markup) |
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| | exceeding 3458 MWt after |
| | -6a-active MSL strain gauges is less than two strain gauges (180 degrees apart) at any of the eight MSL locations, TVA will stop power ascension and repair/replace the damaged strain gauges and only then resume 60 power ascension. |
| | : 3. At least 90 days prior to the start of the BFN Unit 1 EPU outage, TVA shall revise the BFN Unit 1 replacement steam dryer (RSD) analysis utilizing the BFN Unit 3 on-dryer strain gauge based end-to-end bias and uncertainties (B&Us) at EPU conditions, and submit the information including the updated limit curves and a list of dominant frequencies for BFN Unit 1, to the NRC as a report in accordance with 10 CFR 50.4. |
| | : a. If the on-dryer instrumentation was not available when BFN Unit 3 reached a power level of 3458 MWt and the BFN-specific bias and uncertainty data and transfer function could not be developed, the predicted dryer loads during the BFN Unit 1 power ascension will be calculated with the Plant Based Load Evaluation Method 2 transfer function used in the steam dryer design analyses for EPU. The acceptance limits will be based on BFN Unit 3 steam dryer confirmatory stress analysis results using the MSL strain gauge data collected at EPU conditions. The acceptance limits will ensure the steam dryer stress margins remain above the minimum alternating stress ratio (MASR) determined in the BFN Unit 3 steam dryer EPU confirmatory analyses. |
| | : 4. TVA shall evaluate the BFN Unit 1 limit curves prepared in item (a)3 above based on new MSL strain gauge data collected following the BFN Unit 1 EPU outage at or near 3458 MWt. If the limit curves change, the new post-EPU outage limit curves shall be provided to the NRC Project Manager. TVA shall not increase power above 3458 MWt for at least 96 hours after the NRC Project Manager confirms receipt of the reports unless, prior to expiration of the 96 hour period, the NRC Project Manager advises that the NRC staff has no objections to the continuation of power ascension. |
| | : 5. TVA shall monitor the MSL strain gauges during power ascension above 3458 MWt for increasing pressure fluctuations in the steam lines. Upon the initial increase of power above 3458 MWt until reaching 3952 MWt, TVA shall collect data from the MSL strain gauges at nominal 2.5 percent of 3458 MWt (approximately 86 MWt) increments and evaluate steam dryer performance based on this data. |
| | : 6. During power ascension at each nominal 2.5 percent power level above 3458 MWt (approximately 86 MWt), TVA shall compare the MSL data to the approved limit curves based on end-to-end B&Us from the BFN Unit 3 benchmarking at EPU conditions and determine the MASR. |
| | BFN-UNIT 1 Renewed License No. DPR-33 Amendment No. 299 |
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| In conclusion, based on the considerations discussed above, (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public. A review has determined that the proposed amendment does not change any technical requirement with respect to the installation or use of a facility component located within the restricted area, as defined in 10 CFR 20, and does not change any inspection or surveillance requirement. The proposed amendment does not involve (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amounts of any effluent that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure. Accordingly, the proposed amendment meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(10). Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the proposed amendment.
| | ATTACHMENT 2 Retyped Proposed Renewed Facility Operating License Change |
| : 1. Letter from NRC to TVA, "Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Issuance of Amendments Regarding Extended Power Uprate (CAC Nos. MF6741, MF6742, and MF6743)," dated August 14, 2017 (ML17032A120).
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| BFN-UNIT 1 -6a-active MSL strain gauges is less than two strain gauges (180 degrees apart) at any of the eight MSL locations, TVA will stop power ascension and repair/replace the damaged strain gauges and only then resume power ascension.
| | -6a-active MSL strain gauges is less than two strain gauges (180 degrees apart) at any of the eight MSL locations, TVA will stop power ascension and repair/replace the damaged strain gauges and only then resume power ascension. |
| : 3. At least 90 days prior to the start of the BFN Unit 1 EPU outage, TVA shall revise the BFN Unit 1 replacement steam dryer (RSD) analysis utilizing the BFN Unit 3 on-dryer strain gauge based end-to-end bias and uncertainties (B&Us) at EPU conditions, and submit the information including the updated limit curves and a list of dominant frequencies for BFN Unit 1, to the NRC as a report in accordance with 10 CFR 50.4. a. If the on-dryer instrumentation was not available when BFN Unit 3 reached a power level of 3458 MWt and the BFN-specific bias and uncertainty data and transfer function could not be developed, the predicted dryer loads during the BFN Unit 1 power ascension will be calculated with the Plant Based Load Evaluation Method 2 transfer function used in the steam dryer design analyses for EPU. The acceptance limits will be based on BFN Unit 3 steam dryer confirmatory stress analysis results using the MSL strain gauge data collected at EPU conditions. | | : 3. At least 60 days prior to exceeding 3458 MWt after the BFN Unit 1 EPU outage, TVA shall revise the BFN Unit 1 replacement steam dryer (RSD) analysis utilizing the BFN Unit 3 on-dryer strain gauge based end-to-end bias and uncertainties (B&Us) at EPU conditions, and submit the information including the updated limit curves and a list of dominant frequencies for BFN Unit 1, to the NRC as a report in accordance with 10 CFR 50.4. |
| The acceptance limits will ensure the steam dryer stress margins remain above the minimum alternating stress ratio (MASR) determined in the BFN Unit 3 steam dryer EPU confirmatory analyses. | | : a. If the on-dryer instrumentation was not available when BFN Unit 3 reached a power level of 3458 MWt and the BFN-specific bias and uncertainty data and transfer function could not be developed, the predicted dryer loads during the BFN Unit 1 power ascension will be calculated with the Plant Based Load Evaluation Method 2 transfer function used in the steam dryer design analyses for EPU. The acceptance limits will be based on BFN Unit 3 steam dryer confirmatory stress analysis results using the MSL strain gauge data collected at EPU conditions. The acceptance limits will ensure the steam dryer stress margins remain above the minimum alternating stress ratio (MASR) determined in the BFN Unit 3 steam dryer EPU confirmatory analyses. |
| : 4. TVA shall evaluate the BFN Unit 1 limit curves prepared in item (a)3 above based on new MSL strain gauge data collected following the BFN Unit 1 EPU outage at or near 3458 MWt. If the limit curves change, the new post-EPU outage limit curves shall be provided to the NRC Project Manager. TV A shall not increase power above 3458 MWt for at least 96 hours after the NRC Project Manager confirms receipt of the reports unless, prior to expiration of the 96 hour period, the NRC Project Manager advises that the NRC staff has no objections to the continuation of power ascension. | | : 4. TVA shall evaluate the BFN Unit 1 limit curves prepared in item (a)3 above based on new MSL strain gauge data collected following the BFN Unit 1 EPU outage at or near 3458 MWt. If the limit curves change, the new post-EPU outage limit curves shall be provided to the NRC Project Manager. TV A shall not increase power above 3458 MWt for at least 96 hours after the NRC Project Manager confirms receipt of the reports unless, prior to expiration of the 96 hour period, the NRC Project Manager advises that the NRC staff has no objections to the continuation of power ascension. |
| : 5. TVA shall monitor the MSL strain gauges during power ascension above 3458 MWt for increasing pressure fluctuations in the steam lines. Upon the initial increase of power above 3458 MWt until reaching 3952 MWt, TVA shall collect data from the MSL strain gauges at nominal 2.5 percent of 3458 MWt (approximately 86 MWt) increments and evaluate steam dryer performance based on this data. 6. During power ascension at each nominal 2.5 percent power level above 3458 MWt (approximately 86 MWt), TVA shall compare the MSL data to the approved limit curves based on end-to-end B&Us from the BFN Unit 3 benchmarking at EPU conditions and determine the MASR. Renewed License No. DPR-33 Amendment No. 299}} | | : 5. TVA shall monitor the MSL strain gauges during power ascension above 3458 MWt for increasing pressure fluctuations in the steam lines. Upon the initial increase of power above 3458 MWt until reaching 3952 MWt, TVA shall collect data from the MSL strain gauges at nominal 2.5 percent of 3458 MWt (approximately 86 MWt) increments and evaluate steam dryer performance based on this data. |
| | : 6. During power ascension at each nominal 2.5 percent power level above 3458 MWt (approximately 86 MWt), TVA shall compare the MSL data to the approved limit curves based on end-to-end B&Us from the BFN Unit 3 benchmarking at EPU conditions and determine the MASR. |
| | BFN-UNIT 1 Renewed License No. DPR-33 Amendment No.}} |
Letter Sequence Supplement |
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Initiation
- Request, Request, Request, Request, Request, Request, Request
- Acceptance, Acceptance, Acceptance
- Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement
Administration
- Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance
- Meeting, Meeting, Meeting
Results
Other: CNL-16-008, Update on Progress of Facility Modifications for MSIV Leak Rate, CNL-18-112, Extended Power Uprate - Flow Induced Vibration Summary Report, CNL-18-124, Extended Power Uprate - Replacement Steam Dryer Final Load Definition and Stress Reports, CNL-18-134, Extended Power Uprate - Replacement Steam Dryer Revised Analysis and Limit Curves Report, ML16085A301, ML16105A441, ML16168A026, ML16176A316
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MONTHYEARML15282A2352015-09-21021 September 2015 RHR Heat Exchange K-values Utilities in EPU Containment Analyses Project stage: Request ML15282A1812015-09-21021 September 2015 Non-Proprietary - Safety Analysis Report for Browns Ferry, Units 1, 2 and 3, Extended Power Uprate, Attachment 7 Project stage: Request ML15282A1522015-09-21021 September 2015 Submits Proposed Technical Specifications Change TS-505 - Request for License Amendments - Extended Power Uprate Project stage: Request CNL-15-249, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 1, Spent Fuel Pool Criticality Safety Analysis Information2015-12-15015 December 2015 Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 1, Spent Fuel Pool Criticality Safety Analysis Information Project stage: Supplement CNL-15-250, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 2, MICROBURN-B2 Information, Including Enclosures 2, 4, 6, and 72015-12-15015 December 2015 Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 2, MICROBURN-B2 Information, Including Enclosures 2, 4, 6, and 7 Project stage: Supplement CNL-15-261, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 3, Interconnection System Impact Study Information2015-12-18018 December 2015 Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 3, Interconnection System Impact Study Information Project stage: Supplement ML16032A0442016-02-0101 February 2016 FWS to NRC, Updated List of Threatened and Endangered Species that May Occur in Your Proposed Project Location for Browns Ferry EPU Project stage: Request ML16041A3072016-02-18018 February 2016 Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate Project stage: RAI ML16041A0222016-02-25025 February 2016 Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate Project stage: RAI ML16040A2322016-02-25025 February 2016 Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate Project stage: RAI ML16049A4632016-02-29029 February 2016 Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate Project stage: RAI CNL-16-045, Proposed Technical Specifications (Ts)Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 6, Response to Request for Additional Information2016-03-0909 March 2016 Proposed Technical Specifications (Ts)Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 6, Response to Request for Additional Information Project stage: Supplement ML16062A0722016-03-15015 March 2016 Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate Project stage: RAI CNL-16-048, Supplement 7, Responses to Requests for Additional Information, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU)2016-03-24024 March 2016 Supplement 7, Responses to Requests for Additional Information, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) Project stage: Supplement ML16084A3202016-03-25025 March 2016 Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate Project stage: RAI CNL-16-055, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 8, Response to Request for Additional Information2016-03-28028 March 2016 Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 8, Response to Request for Additional Information Project stage: Supplement ML16089A1372016-03-29029 March 2016 NRR E-mail Capture - Correction to Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate Project stage: RAI ML16064A2862016-04-0404 April 2016 Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate Project stage: RAI ML16091A0712016-04-0707 April 2016 Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate Project stage: RAI ML16085A3012016-04-11011 April 2016 Regulatory Audit Plans for April 19 - 21, 2016, Audit at Excel Facility in Rockville, Maryland, in Support of Extended Power Uprate License Amendment Request Project stage: Other ML16085A0792016-04-14014 April 2016 Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate Project stage: RAI ML16102A3392016-04-14014 April 2016 Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate Project stage: RAI CNL-16-069, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 11, Responses to Requests for Additional Information2016-04-14014 April 2016 Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 11, Responses to Requests for Additional Information Project stage: Supplement ML16104A2452016-04-20020 April 2016 Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate Project stage: RAI CNL-16-077, for Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Update (EPU) - Supplement 14, Response to Request for Additional Information2016-04-27027 April 2016 for Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Update (EPU) - Supplement 14, Response to Request for Additional Information Project stage: Supplement ML16105A4412016-04-27027 April 2016 Regulatory Audit Plan for May 10-11, 2016, Audit at Excel Facility in Rockville, Maryland, in Support of Extended Power Uprate License Amendment Request Project stage: Other CNL-16-079, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 15, Responses to Requests for Additional Information2016-05-11011 May 2016 Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 15, Responses to Requests for Additional Information Project stage: Supplement ML16124A9322016-05-12012 May 2016 Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance ML16125A4232016-05-19019 May 2016 Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance CNL-16-008, Update on Progress of Facility Modifications for MSIV Leak Rate2016-05-26026 May 2016 Update on Progress of Facility Modifications for MSIV Leak Rate Project stage: Other CNL-16-091, Brown Ferry, Units 1, 2 & 3, Responses to Requests for Additional Information and Updates Associated with Interconnection System Impact Study Modifications on Proposed Technical Specifications Change TS-505 - Request for License Amendment2016-05-27027 May 2016 Brown Ferry, Units 1, 2 & 3, Responses to Requests for Additional Information and Updates Associated with Interconnection System Impact Study Modifications on Proposed Technical Specifications Change TS-505 - Request for License Amendments Project stage: Response to RAI CNL-16-094, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 20, Responses to Requests for Additional Information2016-06-0909 June 2016 Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 20, Responses to Requests for Additional Information Project stage: Supplement ML16146A6352016-06-13013 June 2016 Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate Project stage: RAI ML16161A0642016-06-15015 June 2016 Notice of Forthcoming Closed Meeting with Tennessee Valley Authority and Its Consultant, GEH, Regarding Steam Dryers Structural Adequacy for Browns Ferry Units 1, 2 & 3 Extended Power Uprate (EPU) License Amendment Request (LAR) Project stage: Meeting CNL-16-093, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate - Supplement 19, Responses to Requests for Additional Information2016-06-17017 June 2016 Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate - Supplement 19, Responses to Requests for Additional Information Project stage: Supplement ML16154A5442016-06-21021 June 2016 Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate Project stage: RAI ML16168A0262016-06-23023 June 2016 Summary Report for the April 19 to 21, 2016 Audit in Support of Replacement Steam Dryer Review Associated to Extended Power Uprate License Amendment Request (CAC Nos. MF6741, MF6742, and MF6743) Project stage: Other CNL-16-105, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 22, Responses to Requests for Additional Information2016-06-24024 June 2016 Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 22, Responses to Requests for Additional Information Project stage: Supplement ML16125A4062016-07-0606 July 2016 Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance ML16127A6092016-07-0606 July 2016 NRC Letter Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance ML16125A0842016-07-0707 July 2016 Approval for Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance ML16130A6002016-07-0707 July 2016 Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance ML16173A0262016-07-0707 July 2016 Approval for Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance ML16176A3162016-07-11011 July 2016 Summary Report for the May 3 to May 5, 2016 Audit in Support Containment Accident Pressure Associated to Extended Power Uprate License Amendment Request Project stage: Other CNL-16-109, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 23, Miscellaneous Updates2016-07-13013 July 2016 Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 23, Miscellaneous Updates Project stage: Supplement CNL-16-119, Brown Ferry Nuclear Plant, Unit 1, 2 and 3 - Proposed Technical Specifications Change TS-505 - Request for License Amendments - Extended Power Uprate - Supplemental Information Related to Replacement Steam Dryers2016-07-13013 July 2016 Brown Ferry Nuclear Plant, Unit 1, 2 and 3 - Proposed Technical Specifications Change TS-505 - Request for License Amendments - Extended Power Uprate - Supplemental Information Related to Replacement Steam Dryers Project stage: Supplement ML16193A4602016-07-21021 July 2016 June 23, 2016, Summary of Closed Meeting with Tennessee Valley Authority Regarding the Structural Adequacy of Steam Dryers for Extended Power Uprate License Amendment Request for Browns Ferry Nuclear Plant, Units 1, 2, and 3 (MF6741, MF6742 Project stage: Meeting ML16194A2292016-07-21021 July 2016 Request for Additional Information Related to License Amendment Request Regarding Extended Power Uprate Project stage: RAI CNL-16-116, Response to Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 252016-07-27027 July 2016 Response to Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 25 Project stage: Supplement CNL-16-118, Response to Request for Additional Information on Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 272016-07-29029 July 2016 Response to Request for Additional Information on Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 27 Project stage: Supplement 2016-04-07
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Category:Letter type:CNL
MONTHYEARCNL-24-017, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions2024-01-17017 January 2024 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure and Emergency Preparedness Department Procedure Revisions CNL-23-071, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-472024-01-11011 January 2024 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-47 CNL-23-070, Submittal of Fifth 10-Year Interval Inservice Testing Program Plan2023-11-29029 November 2023 Submittal of Fifth 10-Year Interval Inservice Testing Program Plan CNL-23-067, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-11-27027 November 2023 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-23-061, Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revision2023-09-20020 September 2023 Tennessee Valley Authority - Central Emergency Control Center Emergency Plan Implementing Procedure Revision CNL-23-057, Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC-EPIP-1, Revision 76 and CECC-EPIP-9, Revision 642023-09-0505 September 2023 Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC-EPIP-1, Revision 76 and CECC-EPIP-9, Revision 64 CNL-23-055, Tennessee Valley Authority - Emergency Preparedness Department Procedure Revision. Includes EPDP-3, Revision 3, Emergency Plan Exercises and Preparedness Drills2023-07-25025 July 2023 Tennessee Valley Authority - Emergency Preparedness Department Procedure Revision. Includes EPDP-3, Revision 3, Emergency Plan Exercises and Preparedness Drills CNL-23-053, Tennessee Valley Authority - Radiological Emergency Plan Revisions2023-07-18018 July 2023 Tennessee Valley Authority - Radiological Emergency Plan Revisions CNL-23-025, American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-472023-07-0303 July 2023 American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-47 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 . CNL-23-046, Revision to Notice of Intent to Pursue Subsequent License Renewal - Schedule Submittal2023-06-0606 June 2023 Revision to Notice of Intent to Pursue Subsequent License Renewal - Schedule Submittal CNL-23-037, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request to Use a Later Edition of the American Society of Mechanical Engineers Operation and Maintenance Code and Alternative Request2023-06-0101 June 2023 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request to Use a Later Edition of the American Society of Mechanical Engineers Operation and Maintenance Code and Alternative Requests 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 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-23-032, 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-23-034, 10 CFR 50.46 Annual Report2023-04-26026 April 2023 10 CFR 50.46 Annual Report 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 CNL-23-018, Request for Amendment Regarding Technical Specification Surveillance Requirements 3.4.3.2 and 3.5.1.11 Regarding Safety Relief Valves (BFN TS-540)2023-03-30030 March 2023 Request for Amendment Regarding Technical Specification Surveillance Requirements 3.4.3.2 and 3.5.1.11 Regarding Safety Relief Valves (BFN TS-540) CNL-23-023, Annual Insurance Status Report2023-03-30030 March 2023 Annual Insurance Status Report CNL-23-027, Second Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505-A, Revision 2, Provide Risk-Informed Extended Completion Times RITSTF Initiative 4b (BFN TS-524)2023-03-29029 March 2023 Second Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505-A, Revision 2, Provide Risk-Informed Extended Completion Times RITSTF Initiative 4b (BFN TS-524) CNL-23-022, Decommissioning Funding Status Report2023-03-29029 March 2023 Decommissioning Funding 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 CNL-23-019, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Request for Alternative BFN-0-ISI-322023-03-11011 March 2023 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Request for Alternative BFN-0-ISI-32 CNL-22-045, Application to Revise Technical Specifications to Adopt TSTF-566-A, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems, and TSTF-580-A, Revision 1, Provide Exception from Entering Mode 42023-03-10010 March 2023 Application to Revise Technical Specifications to Adopt TSTF-566-A, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems, and TSTF-580-A, Revision 1, Provide Exception from Entering Mode 4 CNL-23-021, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2023-03-0808 March 2023 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-22-037, Application to Revise Technical Specifications to Adopt TSTF-541-A, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position (BFN TS-533)2023-01-31031 January 2023 Application to Revise Technical Specifications to Adopt TSTF-541-A, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position (BFN TS-533) CNL-23-003, Browns Nuclear Plant, Units 1, 2 & 3; Sequoyah Nuclear Plant, Units 1 & 2; and Watts Bar Nuclear Plant, Units 1 & 2 - Organizational Topic Report TVA-NPOD89-A2023-01-30030 January 2023 Browns Nuclear Plant, Units 1, 2 & 3; Sequoyah Nuclear Plant, Units 1 & 2; and Watts Bar Nuclear Plant, Units 1 & 2 - Organizational Topic Report TVA-NPOD89-A CNL-23-008, Tennessee Valley Authority Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2022-12-22022 December 2022 Tennessee Valley Authority Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-22-089, License Amendment Request for Adoption of TSTF-478, Revision 2, BWR Technical Specification Changes That Implement the Revised Rule for Combustible Gas Control (BFN TS-546)2022-12-20020 December 2022 License Amendment Request for Adoption of TSTF-478, Revision 2, BWR Technical Specification Changes That Implement the Revised Rule for Combustible Gas Control (BFN TS-546) CNL-22-090, Request to Use a Later Edition of the American Society of Mechanical Engineers Operation and Maintenance Code and Alternative Requests for the Fifth Inservice Testing Interval2022-12-12012 December 2022 Request to Use a Later Edition of the American Society of Mechanical Engineers Operation and Maintenance Code and Alternative Requests for the Fifth Inservice Testing Interval CNL-22-100, to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for Browns Ferry Nuclear Plant Units 1, 2, and 3,in Support of Atrium 11 Fuel Use at Browns Ferry (TS-535)2022-12-0909 December 2022 to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for Browns Ferry Nuclear Plant Units 1, 2, and 3,in Support of Atrium 11 Fuel Use at Browns Ferry (TS-535) CNL-22-097, Response to Request for Additional Information and Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide .2022-12-0101 December 2022 Response to Request for Additional Information and Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide . CNL-22-106, Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revision. Includes CECC EPIP-14, Revision 38, Nuclear Emergency Public Information Organization and Operat2022-11-28028 November 2022 Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revision. Includes CECC EPIP-14, Revision 38, Nuclear Emergency Public Information Organization and Operatio CNL-22-105, Physical Security Plan, Training and Qualification Plan, Safeguards Contingency Plan, and Independent Spent Fuel Storage Installation Security Program, Revision 222022-11-0808 November 2022 Physical Security Plan, Training and Qualification Plan, Safeguards Contingency Plan, and Independent Spent Fuel Storage Installation Security Program, Revision 22 CNL-22-099, Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status Update2022-10-31031 October 2022 Tennessee Valley Authority - Hydrologic Engineering Center River Analysis System Project Milestone Status Update CNL-22-098, Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC EPIP-7, Rev. 45 & CECC EPIP-8, Rev. 552022-10-17017 October 2022 Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions. Includes CECC EPIP-7, Rev. 45 & CECC EPIP-8, Rev. 55 CNL-22-055, Application to Delete Acreage Value Discussion from Technical Specifications (BFN TS-543)2022-09-29029 September 2022 Application to Delete Acreage Value Discussion from Technical Specifications (BFN TS-543) CNL-22-096, to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for Browns Ferry Nuclear Plant Units 1, 2, and 3, in Support of Atrium 11 Fuel Use at Browns Ferry (TS-535)2022-09-29029 September 2022 to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for Browns Ferry Nuclear Plant Units 1, 2, and 3, in Support of Atrium 11 Fuel Use at Browns Ferry (TS-535) CNL-22-083, to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for Browns Ferry Nuclear Plant Units 1, 2, and 3, in Support of Atrium 11 Fuel Use at Browns Ferry (TS-535).2022-09-13013 September 2022 to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for Browns Ferry Nuclear Plant Units 1, 2, and 3, in Support of Atrium 11 Fuel Use at Browns Ferry (TS-535). CNL-22-075, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Unit 2, Request for Alternative, BFN-21-ISI-02, Alternative to American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section Xi,.2022-09-12012 September 2022 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Unit 2, Request for Alternative, BFN-21-ISI-02, Alternative to American Society of Mechanical Engineers, Boiler and Pressure Vessel Code, Section Xi,. CNL-22-025, American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Request for Alternative BFN-0-ISI-322022-08-22022 August 2022 American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Request for Alternative BFN-0-ISI-32 CNL-22-077, Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2022-08-11011 August 2022 Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions CNL-22-065, Response to Request for Confirmation of Information and Additional Information and Second Supplement Regarding Application Requesting NRC Prior Approval of a Proposed Chilled-Water Cross-tie.2022-08-0101 August 2022 Response to Request for Confirmation of Information and Additional Information and Second Supplement Regarding Application Requesting NRC Prior Approval of a Proposed Chilled-Water Cross-tie. CNL-22-076, to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 in Support of Atrium 11 Fuel2022-07-28028 July 2022 to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 in Support of Atrium 11 Fuel CNL-22-066, Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for in Support of Atrium 11 Fuel Use Supplement 3, Response to Request for Additional Information2022-07-18018 July 2022 Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for in Support of Atrium 11 Fuel Use Supplement 3, Response to Request for Additional Information CNL-22-039, Application to Revise Technical Specifications to Adopt TSTF-554-A, Revision 1, Revise Reactor Coolant Leakage Requirements (BFN TS-537) (SQN-21-05) (WBN-TS-21-04)2022-07-13013 July 2022 Application to Revise Technical Specifications to Adopt TSTF-554-A, Revision 1, Revise Reactor Coolant Leakage Requirements (BFN TS-537) (SQN-21-05) (WBN-TS-21-04) CNL-22-008, and Watts Bar Nuclear Plant - Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules (BFN-TS-541, SQN-TS-21-09, and WBN-TS-22-002)2022-06-13013 June 2022 and Watts Bar Nuclear Plant - Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules (BFN-TS-541, SQN-TS-21-09, and WBN-TS-22-002) 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-22-068, Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions2022-06-0808 June 2022 Tennessee Valley Authority - Radiological Emergency Plan and Central Emergency Control Center Emergency Plan Implementing Procedure Revisions 2024-01-17
[Table view] Category:Technical Specification
MONTHYEARML23331A2532023-11-27027 November 2023 Summary Report for 10 CFR 50.9 Evaluations, Technical Specifications Bases Changes, Technical Requirement Manual Changes, and NRC Commitment Revisions CNL-22-045, Application to Revise Technical Specifications to Adopt TSTF-566-A, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems, and TSTF-580-A, Revision 1, Provide Exception from Entering Mode 42023-03-10010 March 2023 Application to Revise Technical Specifications to Adopt TSTF-566-A, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems, and TSTF-580-A, Revision 1, Provide Exception from Entering Mode 4 CNL-22-037, Application to Revise Technical Specifications to Adopt TSTF-541-A, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position (BFN TS-533)2023-01-31031 January 2023 Application to Revise Technical Specifications to Adopt TSTF-541-A, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position (BFN TS-533) CNL-22-089, License Amendment Request for Adoption of TSTF-478, Revision 2, BWR Technical Specification Changes That Implement the Revised Rule for Combustible Gas Control (BFN TS-546)2022-12-20020 December 2022 License Amendment Request for Adoption of TSTF-478, Revision 2, BWR Technical Specification Changes That Implement the Revised Rule for Combustible Gas Control (BFN TS-546) CNL-22-008, and Watts Bar Nuclear Plant - Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules (BFN-TS-541, SQN-TS-21-09, and WBN-TS-22-002)2022-06-13013 June 2022 and Watts Bar Nuclear Plant - Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules (BFN-TS-541, SQN-TS-21-09, and WBN-TS-22-002) ML21335A0672021-11-26026 November 2021 Summary Report for 10 CFR 50.59 Evaluations, Technical Specifications Bases Changes, Technical Requirements Manual Changes, and NRC Commitment Revisions ML24019A1192021-04-0808 April 2021 Technical Specification 3.1.6, Rod Pattern Control CNL-20-003, Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (BFN-TS-516)2020-03-27027 March 2020 Application for Technical Specifications Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (BFN-TS-516) CNL-19-010, Application to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF)-542, Reactor Pressure Vessel Water Inventory Control, Revision 2 (BFN-TS-513)2019-01-25025 January 2019 Application to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF)-542, Reactor Pressure Vessel Water Inventory Control, Revision 2 (BFN-TS-513) CNL-18-130, Revised Application to Modify the Technical Specifications for Unbalanced Voltage Relays2018-11-19019 November 2018 Revised Application to Modify the Technical Specifications for Unbalanced Voltage Relays CNL-18-062, Request for Proposed Technical Specification (TS) Change TS-519 License Amendment Request - Change to Unit 1 License Condition 2.C(18)(a)3, Supplement 12018-04-19019 April 2018 Request for Proposed Technical Specification (TS) Change TS-519 License Amendment Request - Change to Unit 1 License Condition 2.C(18)(a)3, Supplement 1 CNL-18-041, Request for Proposed Technical Specification (TS) Change TS-519 License Amendment Request - Change to License Condition 2.C(18)(a)32018-03-16016 March 2018 Request for Proposed Technical Specification (TS) Change TS-519 License Amendment Request - Change to License Condition 2.C(18)(a)3 CNL-18-042, Proposed Technical Specifications Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus, Supplement 12018-03-0707 March 2018 Proposed Technical Specifications Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus, Supplement 1 ML18079B1402018-02-23023 February 2018 Browns Ferry Nuclear Plant, Units 1, 2, and 3: Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus ML18066A1202018-02-20020 February 2018 Summary Report for 10 CFR 50.59 Evaluations, Technical Specifications Bases Changes, Technical Requirements Manual Changes, and NRC Commitment Revisions - Updated CNL-16-165, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 34, Revised Proposed License Conditions and Technical Specification Change2016-10-31031 October 2016 Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 34, Revised Proposed License Conditions and Technical Specification Change NL-16-165, Browns Ferry Nuclear Plant, Units 1, 2, & 3 - Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 34, Revised Proposed License Conditions and Technical Specificat2016-10-31031 October 2016 Browns Ferry Nuclear Plant, Units 1, 2, & 3 - Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 34, Revised Proposed License Conditions and Technical Specificati CNL-16-169, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 35, Consolidated Power Uprate Safety Analysis Report Revision2016-10-28028 October 2016 Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 35, Consolidated Power Uprate Safety Analysis Report Revision CNL-16-109, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 23, Miscellaneous Updates2016-07-13013 July 2016 Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 23, Miscellaneous Updates CNL-16-077, for Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Update (EPU) - Supplement 14, Response to Request for Additional Information2016-04-27027 April 2016 for Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Update (EPU) - Supplement 14, Response to Request for Additional Information CNL-16-073, Proposed Technical Specifications Change TS-505 - Request for License Amendments - Extended Power Uprate - Supplement 12, Responses to Requests for Additional Information2016-04-22022 April 2016 Proposed Technical Specifications Change TS-505 - Request for License Amendments - Extended Power Uprate - Supplement 12, Responses to Requests for Additional Information CNL-15-240, Proposed Technical Specifications Change TS-505 - Request for License Amendments - Extended Power Uprate - Supplemental Information2015-11-13013 November 2015 Proposed Technical Specifications Change TS-505 - Request for License Amendments - Extended Power Uprate - Supplemental Information CNL-15-187, Response to NRC Request for Additional Information (RAI) Regarding Application to Revise Technical Specifications (TS) 3.3.6.1, Table 3.3.6.1-1 to Require Standby Liquid Control (SLC) System Instrumentation In..2015-09-25025 September 2015 Response to NRC Request for Additional Information (RAI) Regarding Application to Revise Technical Specifications (TS) 3.3.6.1, Table 3.3.6.1-1 to Require Standby Liquid Control (SLC) System Instrumentation In.. NL-15-169, Browns Ferry, Units 1, 2 and 3 - Submits Proposed Technical Specifications Change TS-505 - Request for License Amendments - Extended Power Uprate2015-09-21021 September 2015 Browns Ferry, Units 1, 2 and 3 - Submits Proposed Technical Specifications Change TS-505 - Request for License Amendments - Extended Power Uprate NL-15-169, Browns Ferry, Units 1, 2 and 3 - Proposed Technical Specification Markups, Part 1 of 22015-09-21021 September 2015 Browns Ferry, Units 1, 2 and 3 - Proposed Technical Specification Markups, Part 1 of 2 NL-15-169, Browns Ferry, Units 1, 2 and 3 - License Amendment Request TS-505 Extended Power Uprate, Evaluation of Proposed Changes2015-09-21021 September 2015 Browns Ferry, Units 1, 2 and 3 - License Amendment Request TS-505 Extended Power Uprate, Evaluation of Proposed Changes NL-15-169, Browns Ferry, Units 1, 2 and 3 - Proposed Technical Specification Markups, Part 2 of 22015-09-21021 September 2015 Browns Ferry, Units 1, 2 and 3 - Proposed Technical Specification Markups, Part 2 of 2 NL-15-169, Browns Ferry, Units 1, 2 and 3 - Retyped Proposed Technical Specifications Changes, Attachment 32015-09-21021 September 2015 Browns Ferry, Units 1, 2 and 3 - Retyped Proposed Technical Specifications Changes, Attachment 3 NL-15-169, Browns Ferry, Units 1, 2 and 3 - Proposed Technical Specification Bases Markups, Attachment 42015-09-21021 September 2015 Browns Ferry, Units 1, 2 and 3 - Proposed Technical Specification Bases Markups, Attachment 4 ML15282A1692015-09-21021 September 2015 Proposed Technical Specification Markups, Part 2 of 2 ML15282A1522015-09-21021 September 2015 Submits Proposed Technical Specifications Change TS-505 - Request for License Amendments - Extended Power Uprate NL-15-169, Browns Ferry, Units 1, 2 and 3 - Retyped Technical Specifications Bases Changes, Attachment 52015-09-21021 September 2015 Browns Ferry, Units 1, 2 and 3 - Retyped Technical Specifications Bases Changes, Attachment 5 ML15282A1802015-09-21021 September 2015 Retyped Technical Specifications Bases Changes, Attachment 5 ML15282A1782015-09-21021 September 2015 Retyped Proposed Technical Specifications Changes, Attachment 3 ML15282A1672015-09-21021 September 2015 License Amendment Request TS-505 Extended Power Uprate, Evaluation of Proposed Changes ML15282A1792015-09-21021 September 2015 Proposed Technical Specification Bases Markups, Attachment 4 ML15282A1662015-09-21021 September 2015 Proposed Technical Specification Markups, Part 1 of 2 CNL-15-002, Application to Modify Technical Specification 2.1.1.2, Reactor Core Minimum Critical Power Ratio Saftey Limits (TS-499)2015-03-0606 March 2015 Application to Modify Technical Specification 2.1.1.2, Reactor Core Minimum Critical Power Ratio Saftey Limits (TS-499) CNL-14-166, Application to Revise Technical Specifications 3.3.6.1, Table 3.3.6.1-1, Function 5.g and Bases (BFN-TS-479)2015-02-17017 February 2015 Application to Revise Technical Specifications 3.3.6.1, Table 3.3.6.1-1, Function 5.g and Bases (BFN-TS-479) CNL-14-068, (Bfn), Units 1, 2 and 3 - Supplement to Proposed Technical Specification Change to Revise the Leakage Rate Through MSIVs (TS-485)2015-01-29029 January 2015 (Bfn), Units 1, 2 and 3 - Supplement to Proposed Technical Specification Change to Revise the Leakage Rate Through MSIVs (TS-485) ML12242A4772012-08-28028 August 2012 License Amendment Request to Change Technical Specifications to Delete References to Section XI of the ASME Code and Incorporate References to the ASME OM Code and Allow Application of 25 Percent Extension of Surveillance Intervals to Accel ML1106004082011-02-25025 February 2011 Technical Specification Change TS-429 - Deletion of Low Pressure Coolant Injection Motor-Generator Sets ML1032103342010-11-12012 November 2010 Revised Technical Specifications Change TS-468 - Request to Extend Completion Time for TS 3.8.1 Required Action B.4 - Emergency Diesel Generators a, B, C, D, 3A, 3B, 3C, & 3D ML1024305282010-08-27027 August 2010 Technical Specifications Change TS-474 - Request to Add TS 3.7.3, Control Room Emergency Ventilation (Crev) System, Action to Address Two Crev Subsystems Inoperable Due to Inoperable Crev System High Efficiency Particulate ML1005507002010-02-18018 February 2010 Technical Specifications Change TS-468 - Request to Extend Completion Time for TS 3.8.1 Required Action B.4 - Emergency Diesel Generators a, B, C, D, 3A, 3B, 3C, and 3D ML0933506552009-11-17017 November 2009 Technical Specification Change TS-467-S - Utilization of Areva Fuel & Associated Analysis Methodologies - Non EPU Supplement ML0930801582009-10-23023 October 2009 Technical Specification Change TS-467 - Utilization of Areva Fuel and Associated Analysis Methodologies ML0929503402009-10-20020 October 2009 License Amendment Request for Adoption of TSTF-511, Revision 0, Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26 - Browns Ferry TS Change 469; Sequoyah Change 09-04; and Watts Change 09-19 ML0922904712009-08-11011 August 2009 Technical Specifications Changes TS-431 and TS-418 - Extended Power Uprate - Response to Round 25 - Request for Additional Information - SCVB-82 Through SCVB-86 and Replacement Documentation ML0921101192009-07-27027 July 2009 Technical Specifications Change 465 - Revision of Technical Specifications to Eliminate Unnecessary Water Local Leak Rate Tests 2023-03-10
[Table view] Category:Amendment
MONTHYEARCNL-22-037, Application to Revise Technical Specifications to Adopt TSTF-541-A, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position (BFN TS-533)2023-01-31031 January 2023 Application to Revise Technical Specifications to Adopt TSTF-541-A, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position (BFN TS-533) CNL-22-089, License Amendment Request for Adoption of TSTF-478, Revision 2, BWR Technical Specification Changes That Implement the Revised Rule for Combustible Gas Control (BFN TS-546)2022-12-20020 December 2022 License Amendment Request for Adoption of TSTF-478, Revision 2, BWR Technical Specification Changes That Implement the Revised Rule for Combustible Gas Control (BFN TS-546) CNL-22-008, and Watts Bar Nuclear Plant - Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules (BFN-TS-541, SQN-TS-21-09, and WBN-TS-22-002)2022-06-13013 June 2022 and Watts Bar Nuclear Plant - Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules (BFN-TS-541, SQN-TS-21-09, and WBN-TS-22-002) ML24019A1192021-04-0808 April 2021 Technical Specification 3.1.6, Rod Pattern Control CNL-19-010, Application to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF)-542, Reactor Pressure Vessel Water Inventory Control, Revision 2 (BFN-TS-513)2019-01-25025 January 2019 Application to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF)-542, Reactor Pressure Vessel Water Inventory Control, Revision 2 (BFN-TS-513) CNL-18-062, Request for Proposed Technical Specification (TS) Change TS-519 License Amendment Request - Change to Unit 1 License Condition 2.C(18)(a)3, Supplement 12018-04-19019 April 2018 Request for Proposed Technical Specification (TS) Change TS-519 License Amendment Request - Change to Unit 1 License Condition 2.C(18)(a)3, Supplement 1 ML18079B1402018-02-23023 February 2018 Browns Ferry Nuclear Plant, Units 1, 2, and 3: Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus CNL-16-169, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 35, Consolidated Power Uprate Safety Analysis Report Revision2016-10-28028 October 2016 Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 35, Consolidated Power Uprate Safety Analysis Report Revision CNL-16-077, for Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Update (EPU) - Supplement 14, Response to Request for Additional Information2016-04-27027 April 2016 for Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Update (EPU) - Supplement 14, Response to Request for Additional Information ML15282A1662015-09-21021 September 2015 Proposed Technical Specification Markups, Part 1 of 2 ML15282A1522015-09-21021 September 2015 Submits Proposed Technical Specifications Change TS-505 - Request for License Amendments - Extended Power Uprate ML15282A1672015-09-21021 September 2015 License Amendment Request TS-505 Extended Power Uprate, Evaluation of Proposed Changes ML15282A1692015-09-21021 September 2015 Proposed Technical Specification Markups, Part 2 of 2 NL-15-169, Browns Ferry, Units 1, 2 and 3 - Retyped Technical Specifications Bases Changes, Attachment 52015-09-21021 September 2015 Browns Ferry, Units 1, 2 and 3 - Retyped Technical Specifications Bases Changes, Attachment 5 NL-15-169, Browns Ferry, Units 1, 2 and 3 - Proposed Technical Specification Bases Markups, Attachment 42015-09-21021 September 2015 Browns Ferry, Units 1, 2 and 3 - Proposed Technical Specification Bases Markups, Attachment 4 NL-15-169, Browns Ferry, Units 1, 2 and 3 - Retyped Proposed Technical Specifications Changes, Attachment 32015-09-21021 September 2015 Browns Ferry, Units 1, 2 and 3 - Retyped Proposed Technical Specifications Changes, Attachment 3 NL-15-169, Browns Ferry, Units 1, 2 and 3 - Proposed Technical Specification Markups, Part 2 of 22015-09-21021 September 2015 Browns Ferry, Units 1, 2 and 3 - Proposed Technical Specification Markups, Part 2 of 2 NL-15-169, Browns Ferry, Units 1, 2 and 3 - License Amendment Request TS-505 Extended Power Uprate, Evaluation of Proposed Changes2015-09-21021 September 2015 Browns Ferry, Units 1, 2 and 3 - License Amendment Request TS-505 Extended Power Uprate, Evaluation of Proposed Changes NL-15-169, Browns Ferry, Units 1, 2 and 3 - Proposed Technical Specification Markups, Part 1 of 22015-09-21021 September 2015 Browns Ferry, Units 1, 2 and 3 - Proposed Technical Specification Markups, Part 1 of 2 NL-15-169, Browns Ferry, Units 1, 2 and 3 - Submits Proposed Technical Specifications Change TS-505 - Request for License Amendments - Extended Power Uprate2015-09-21021 September 2015 Browns Ferry, Units 1, 2 and 3 - Submits Proposed Technical Specifications Change TS-505 - Request for License Amendments - Extended Power Uprate ML15282A1802015-09-21021 September 2015 Retyped Technical Specifications Bases Changes, Attachment 5 ML15282A1792015-09-21021 September 2015 Proposed Technical Specification Bases Markups, Attachment 4 ML15282A1782015-09-21021 September 2015 Retyped Proposed Technical Specifications Changes, Attachment 3 CNL-15-002, Application to Modify Technical Specification 2.1.1.2, Reactor Core Minimum Critical Power Ratio Saftey Limits (TS-499)2015-03-0606 March 2015 Application to Modify Technical Specification 2.1.1.2, Reactor Core Minimum Critical Power Ratio Saftey Limits (TS-499) CNL-14-166, Application to Revise Technical Specifications 3.3.6.1, Table 3.3.6.1-1, Function 5.g and Bases (BFN-TS-479)2015-02-17017 February 2015 Application to Revise Technical Specifications 3.3.6.1, Table 3.3.6.1-1, Function 5.g and Bases (BFN-TS-479) ML12242A4772012-08-28028 August 2012 License Amendment Request to Change Technical Specifications to Delete References to Section XI of the ASME Code and Incorporate References to the ASME OM Code and Allow Application of 25 Percent Extension of Surveillance Intervals to Accel ML0933506552009-11-17017 November 2009 Technical Specification Change TS-467-S - Utilization of Areva Fuel & Associated Analysis Methodologies - Non EPU Supplement ML0930801582009-10-23023 October 2009 Technical Specification Change TS-467 - Utilization of Areva Fuel and Associated Analysis Methodologies ML0929503402009-10-20020 October 2009 License Amendment Request for Adoption of TSTF-511, Revision 0, Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26 - Browns Ferry TS Change 469; Sequoyah Change 09-04; and Watts Change 09-19 ML0809103602008-03-27027 March 2008 Technical Specifications (TS) Change 444 - Adoption of Changes to Standard Technical Specifications Under Technical Specification Task Force (TSTF) Change Number - 448, Revision 3, Regarding Control Room Envelope. ML0633900572006-11-28028 November 2006 Tech Spec Pages for Amendment 265 Regarding Removal of License Condition 2.(C)4 (TS-432) ML0626101662006-09-14014 September 2006 Technical Specifications Change TS-453 - Instrument Setpoint Program - Supplement 2 (TAC Nos. MC9518, MC9519, & MC9520) ML0601104742006-01-0909 January 2006 Technical Specification Page for Amendment 295, Revision to Control Room Scram Time Testing Frequency TAC MC8037, TAC MC8038) ML0601104732006-01-0909 January 2006 Technical Specification Page for Amendment 253, Revision to Control Room Scram Time Testing Frequency ML0428701002004-10-12012 October 2004 Technical Specifications Change 438, Revision to Excess Flow Check Valve Surveillance Testing Frequency ML0427303522004-09-27027 September 2004 Technical Spec. Pages, Re. Implementation of Alternative Source Term ML0427303492004-09-27027 September 2004 Technical Spec.Pages Re Implementation of Alternative Source Term ML0427303642004-09-27027 September 2004 Technical Spec.Pages Re Implementation of Alternative Source Term ML0421904312004-08-0202 August 2004 (BFN) Unit 1 - Technical Specification (TS) Change TS 435 - Limiting Condition for Operation (LCO) Time for Containment Atmosphere Dilution (CAD) Subsystem Inoperability ML0421605562004-07-0808 July 2004 Technical Specifications (TS) Change 448 - One Time Frequency Extension for Containment Integrated Leak Rate Test Interval ML0333810122003-12-0101 December 2003 Tech Spec Pages for Amendment No 286 ML0333809912003-12-0101 December 2003 Tech Spec for Unit 3 Amendment No. 244 ML0333809822003-12-0101 December 2003 Tech Spec Pages for Amendment No. 249 ML0304403852003-02-12012 February 2003 Units 1, 2 and 3 - Technical Specifications (TS) Change 405 Supplement 1 - Decay Time ML0224803712002-08-20020 August 2002 (BFN) - Units 2 & 3 - Technical Specifications (TS) Change 417 - Reactor Water Cleanup System - Main Steam Valve Vault (Msvv) Area Temperature - High - Extension of Channel Calibration Surveillance Requirement Frequency ML0210103012002-03-28028 March 2002 Technical Specification Pages for Browns Ferry, Units 2 & 3 ML24019A1341998-09-0303 September 1998 Technical Specification 3.3.2.1, Control Rod Block Instrumentation 2023-01-31
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Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402 CNL-18-062 April 19, 2018 10 CFR 50.90 ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Browns Ferry Nuclear Plant, Unit 1 Renewed Facility Operating License No. DPR-33 NRC Docket No. 50-259
Subject:
Request for Proposed Technical Specification (TS) Change TS-519 License Amendment Request - Change to Unit 1 License Condition 2.C(18)(a)3, Supplement 1
References:
- 1. NRC Letter to TVA, Browns Ferry Nuclear Plant, Units 1, 2, and 3 -
Issuance of Amendments Regarding Extended Power Uprate (CAC Nos. MF6741, MF6742, and MF6743), dated August 14, 2017 (ML17032A120)
- 2. TVA Letter to NRC, Request for Proposed Technical Specification (TS)
Change TS-519 License Amendment Request - Change to Unit 1 License Condition 2.C(18)(a)3, dated March 16, 2018 By the Reference 1 letter, the NRC issued License Amendment Nos. 299, 323, and 283 to the BFN Renewed Facility Operating Licenses (RFOLs) to increase the authorized maximum power level from 3458 megawatts thermal (MWt) to 3952 MWt. The amendments included specific license conditions that required certain monitoring, evaluation, and response actions to potential adverse flow effects as a result of the EPU on plant structures, systems and components (including verifying the continued structural integrity of the replacement steam dryer (RSD)) during the initial EPU power ascension. One aspect of the License Condition 2.C(18)(a)3 for Unit 1 requires the submittal of a revised BFN Unit 1 RSD analysis utilizing the BFN Unit 3 on-dryer strain gauge based end-to-end bias and uncertainties (B&Us) at EPU conditions at least 90 days prior to the start of the BFN Unit 1 EPU outage.
By the Reference 2 letter, Tennessee Valley Authority (TVA) submitted a request for approval of a license amendment to reduce the time before the Browns Ferry Nuclear Plant (BFN) Unit 1 Extended Power Uprate (EPU) outage that TVA was required to submit the revised analysis of the RSD.
U. S. Nuclear Regulatory Commission CNL-18-062 Page 2 April 19, 2018 Based on delays associated with the BFN Unit 3 power ascension and the extensive review and analyses required of the BFN Unit 3 RSD power ascension test results, TVA is unable to submit the revised BFN Unit 1 RSD analysis 90 days prior to the planned October 13, 2018, start of the BFN Unit 1 EPU outage as required by the current BFN Unit 1 License Condition 2.C(18)(a)3. The purpose of this supplement is to revise the proposed word ing of BFN Unit 1 License Condition 2.C(18)(a)3 to reflect submittal of the revised BFN Unit 1 RSD analysis 60 days prior to exceeding 3458 MWt after the BFN Unit 1 EPU outage. A revised evaluation of the proposed change is provided in the Enclosure to this letter. Attachment 1 to the enclosure provides a revised markup of the affected renewed facility operating license page indicating the proposed change. Attachment 2 to the enclosure provides a revised retype of the affected renewed facility operating license page with the proposed change incorporated .
As discussed with NRC staff, NRC approval of this LAR is needed to ensure continued compliance with operating license requirements. This request is purely adm inistrative in nature, in that it will only change the schedule for the BFN Unit 1 submittal.
TVA has determined that there are no significant hazards considerations associated with the proposed changes and that the Technical Specification changes qualify for a categorical exclusion from environmental review pursuant to the provisions of 10 CFR 51.22(c)(9).
Additionally, in accordance with 10 CFR 50.91 (b)(1 ), TVA is sending a copy of this letter and the enclosure to the Alabama State Department of Public Health .
The BFN Plant Operations Review Committee has reviewed this proposed change and determined that operation of BFN in accordance with the proposed change will not endanger the health and safety of the public.
TVA requests approval of the proposed amendment by July 15, 2018, which is 90 days prior to the start of the BFN Unit 1 refueling outage, i.e. , October 13, 2018.
There are no new regulatory commitments associated with this submittal. If there are any questions or if additional information is needed, please contact Mr. Edward Schrull at (423) 751-3850.
I declare under penalty of perjury that the foregoing is true and correct. Executed on the 19th day of April 2018 .
. Shea Vice President, Nuclear Regulatory Affairs and Support Services
Enclosure:
Evaluation of Proposed Change cc: See page 3
U. S. Nuclear Regulatory Commission CNL-18-062 Page 3 April 19, 2018 cc (Enclosure):
NRC Regional Administrator - Region II NRC Senior Resident Inspector - Browns Ferry Nuclear Plant State Health Officer, Alabama State Department of Public Health
Enclosure Browns Ferry Nuclear Plant Unit 1 Renewed Facility Operating License No. DPR-33 NRC Docket No. 50-259 License Amendment Request TS-519, Supplement 1 EVALUATION OF PROPOSED CHANGE
Evaluation of Proposed Change TABLE OF CONTENTS
SUBJECT:
Reduction of Time Period Required for Submittal of the Revised Browns Ferry Nuclear Plant Unit 1 Replacement Steam Dryer Analysis 1.0
SUMMARY
DESCRIPTION 2.0 DETAILED DESCRIPTION
3.0 TECHNICAL EVALUATION
4.0 REGULATORY EVALUATION
4.1 APPLICABLE REGULATORY REQUIREMENTS/CRITERIA 4.2 PRECEDENT 4.3 NO SIGNIFICANT HAZARDS CONSIDERATION
4.4 CONCLUSION
S
5.0 ENVIRONMENTAL CONSIDERATION
6.0 REFERENCES
Attachments:
- 1. Proposed Renewed Facility Operating License Change (Markup)
- 2. Retyped Proposed Renewed Facility Operating License Change Enclosure 1 of 5
Evaluation of Proposed Change 1.0
SUMMARY
DESCRIPTION Tennessee Valley Authority (TVA) requests a license amendment to reduce the time, from 90 days before the outage to 60 days prior to exceeding 3458 MWt after the outage, that the revised Browns Ferry Nuclear Plant (BFN) Unit 1 replacement steam dryer analysis must be submitted. The BFN Unit 1 Extended Power Uprate (EPU) outage is scheduled to start on October 13, 2018, and based on the current BFN Unit 1 outage and power ascension schedule, BFN Unit 1 would first reach 3458 MWt after the EPU outage on November 25, 2018.
By the Reference 1 letter dated August 14, 2017, the NRC issued License Amendment Nos. 299, 323, and 283 to the BFN Renewed Facility Operating Licenses to increase the authorized maximum power level from 3458 megawatts thermal (MWt) to 3952 MWt. The amendments included specific license conditions that required certain monitoring, evaluation, and response actions to potential adverse flow effects as a result of the EPU on plant structures, systems and components (including verifying the continued structural integrity of the replacement steam dryer (RSD)) during the initial EPU power ascension. One aspect of the new License Condition 2.C(18)(a)3 for BFN Unit 1 requires the submittal of a revised BFN Unit 1 RSD analysis utilizing the Unit 3 on-dryer strain gauge based end-to-end bias and uncertainties (B&Us) at EPU conditions "at least 90 days prior to the start of the BFN Unit 1 EPU outage."
Based on delays associated with the BFN Unit 3 power ascension and the extensive review and analyses required of the BFN Unit 3 RSD power ascension test results, TVA is unable to submit the revised BFN Unit 1 RSD analysis 90 days prior to the planned October 13, 2018, start of the BFN Unit 1 EPU outage as required by the current BFN Unit 1 License Condition 2.C(18)(a)3.
TVA requests an administrative revision to BFN Unit 1 Renewed Facility Operating License Condition 2.C(18)(a)3 to reduce the time, from 90 days prior to the outage to 60 days prior to exceeding 3458 MWt after the outage, for submittal of the revised analysis.
2.0 DETAILED DESCRIPTION The BFN Unit 1 License Condition 2.C(18)(a)3 currently states:
At least 90 days prior to the start of the BFN Unit 1 EPU outage, TVA shall revise the BFN Unit 1 replacement steam dryer (RSD) analysis utilizing the Unit 3 on-dryer strain gauge based end-to-end bias and uncertainties (B&Us) at EPU conditions, and submit the information including the updated limit curves and a list of dominant frequencies for BFN Unit 1, to the NRC as a report in accordance with 10 CFR 50.4.
The proposed change is to change the '90 days prior to the start of the BFN Unit 1 EPU outage' to '60 days prior to exceeding 3458 MWt after the BFN Unit 1 EPU outage' and the revised statement of the license condition would read:
At least 60 days prior to exceeding 3458 MWt after the BFN Unit 1 EPU outage, TVA shall revise the BFN Unit 1 replacement steam dryer (RSD) analysis utilizing the Unit 3 on-dryer strain gauge based end-to-end bias and uncertainties (B&Us) at EPU conditions, and submit the information including the updated limit curves and a list of dominant frequencies for BFN Unit 1, to the NRC as a report in accordance with 10 CFR 50.4.
Enclosure 2 of 5
Evaluation of Proposed Change
3.0 TECHNICAL EVALUATION
The request for reducing the time, from 90 days before the outage to 60 days prior to exceeding 3458 MWt after the outage, at which the revised analysis must be submitted is not a technical or safety issue. The license condition requirement is to submit the revised analysis to the NRC. There is no requirement for review and approval of the revised analysis to satisfy the license condition. Therefore, the proposed change is purely an administrative change.
When proposing the current license condition, TVA had anticipated a more compact BFN Unit 3 power ascension schedule, even considering time for the required NRC reviews of the interim stress data.
Based on the current BFN Unit 3 power ascension test schedule, BFN Unit 3 will not reach full EPU power until July 9, 2018. The BFN Unit 3 on-dryer and main steam line (MSL) measurements will be available shortly after this time. Using this measured MSL data from BFN Unit 3, General Electric - Hitachi Nuclear Energy (GEH) will develop PBLE02 load definitions and re-perform the stress analysis for BFN Unit 3 RSD using the BFN-specific bias and uncertainty and transfer function at EPU conditions. The required duration for performance of the BFN Unit 3 PBLE02 analysis of the RSD by GEH is from July 9, 2018, to September 26, 2018. Once available, the Minimum Alternating Stress Ratio from BFN Unit 3 PBLE02 analysis and the on-dryer pressure loads developed from BFN Unit 3 MSL EPU measurements will be used by GEH for revising the BFN Unit 1 RSD analysis and developing updated BFN Unit 1 RSD limit curves. GEH will develop and provide a report including the revised BFN Unit 1 RSD analysis, including updated limit curves and a list of dominant frequencies, to TVA by October 8, 2018. Upon receipt of the report from GEH, TVA will develop, review, and process the NRC submittal in accordance with TVA procedures. This report is expected to be submitted to NRC in accordance with 10 CFR 50.4, Written communications, by October 10, 2018. Therefore, based on the current BFN Unit 1 EPU outage and power ascension schedule and the proposed revised wording of the BFN Unit License Condition 2.C(18)(a)3, BFN Unit 1 would remain at 3458 MWt until the 60-day time period has elapsed (i.e., December 9, 2018).
The proposed change ensures that current delays in the BFN Unit 3 power ascension testing do not delay the start of the BFN Unit 1 EPU outage or startup to the previous license thermal power of 3458 MWt after the outage, while providing the NRC with a 60-day time period for review of the revised BFN Unit 1 RSD analysis.
The timing for submittal of the revised analysis is a requirement of a license condition included in the Renewed Facility Operating License. As such, a change to the timing for submittal of the revised analysis is a change to the operating license for the unit.
4.0 REGULATORY EVALUATION
4.1 APPLICABLE REGULATORY REQUIREMENTS/CRITERIA The proposed change has been evaluated to determine whether applicable regulations and requirements continue to be met. TVA has determined that the proposed change does not require any exemptions or relief from regulatory requirements other than the operating license.
The following applicable regulations and regulatory requirements were reviewed in making this determination:
- 10 CFR 50.90, Application for amendment of license, construction permit, or early site permit Enclosure 3 of 5
Evaluation of Proposed Change
- 10 CFR 50.92, Issuance of amendment 4.2 PRECEDENT License Amendment No. 305 to Renewed Facility Operating License No. DPR-56 for the Peach Bottom Atomic Power Station Unit 3, approved by the NRC on August 11, 2015 (ML15189A185), involved a reduction I relaxation of a required submittal schedule for the revised replacement steam dryer analysis from at least 90 days prior to the start of the Peach Bottom Unit 3 EPU outage to at least 30 days prior to the start of the Peach Bottom Unit 3 EPU outage...
4.3 NO SIGNIFICANT HAZARDS CONSIDERATION Tennessee Valley Authority (TVA) has evaluated whether or not a significant hazards consideration is involved with the proposed amendment by focusing on the three standards set forth in 10 CFR 50.92, "Issuance of amendment," as discussed below:
- 1. Does the proposed amendment involve a significant increase in the probability or consequences of an accident previously evaluated?
Response: No.
The proposed license amendment reduces the length of time, from 90 days prior to the outage to 60 days prior to exceeding 3458 MWt after the outage, by which a revised analysis of the Browns Ferry Nuclear Plant (BFN) Unit 1 replacement steam dryer (RSD), performed using an NRC-approved methodology benchmarked on the BFN Unit 3 RSD, must be submitted to the NRC for information. There is no required review or approval of the revised analysis needed to satisfy the license condition. The proposed change is an administrative change to the period before the outage and does not impact any system, structure or component in such a way as to affect the probability or consequences of an accident previously evaluated. The proposed amendment is purely administrative and has no technical or safety aspects. Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
- 2. Does the proposed amendment create the possibility of a new or different kind of accident from any accident previously evaluated?
Response: No.
The proposed license amendment reduces the length of time, from 90 days prior to the outage to 60 days prior to exceeding 3458 MWt after the outage, by which a revised analysis of the BFN Unit 1 RSD must be submitted to the NRC for information. The proposed amendment is purely administrative and has no technical or safety aspects. Therefore, the proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated.
Enclosure 4 of 5
Evaluation of Proposed Change
- 3. Does the proposed amendment involve a significant reduction in a margin of safety?
Response: No.
The proposed license amendment reduces the length of time, from 90 days prior to the outage to 60 days prior to exceeding 3458 MWt after the outage, by which a revised analysis of the BFN Unit 1 RSD must be submitted to the NRC for information. The proposed amendment is purely administrative and has no technical or safety aspects. Therefore, the proposed change does not involve a significant reduction in a margin of safety.
Based on the above, TVA concludes that the proposed amendment does not involve a significant hazards consideration under the standards set forth in 10 CFR 50.92(c) and, accordingly, a finding of no significant hazards consideration is justified.
4.4 CONCLUSION
S In conclusion, based on the considerations discussed above, (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
5.0 ENVIRONMENTAL CONSIDERATION
A review has determined that the proposed amendment does not change any technical requirement with respect to the installation or use of a facility component located within the restricted area, as defined in 10 CFR 20, and does not change any inspection or surveillance requirement. The proposed amendment does not involve (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amounts of any effluent that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure. Accordingly, the proposed amendment meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(10). Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the proposed amendment.
6.0 REFERENCE
- 1. Letter from NRC to TVA, Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Issuance of Amendments Regarding Extended Power Uprate (CAC Nos. MF6741, MF6742, and MF6743), dated August 14, 2017 (ML17032A120).
Enclosure 5 of 5
ATTACHMENT 1 Proposed Renewed Facility Operating License Change (Markup)
exceeding 3458 MWt after
-6a-active MSL strain gauges is less than two strain gauges (180 degrees apart) at any of the eight MSL locations, TVA will stop power ascension and repair/replace the damaged strain gauges and only then resume 60 power ascension.
- 3. At least 90 days prior to the start of the BFN Unit 1 EPU outage, TVA shall revise the BFN Unit 1 replacement steam dryer (RSD) analysis utilizing the BFN Unit 3 on-dryer strain gauge based end-to-end bias and uncertainties (B&Us) at EPU conditions, and submit the information including the updated limit curves and a list of dominant frequencies for BFN Unit 1, to the NRC as a report in accordance with 10 CFR 50.4.
- a. If the on-dryer instrumentation was not available when BFN Unit 3 reached a power level of 3458 MWt and the BFN-specific bias and uncertainty data and transfer function could not be developed, the predicted dryer loads during the BFN Unit 1 power ascension will be calculated with the Plant Based Load Evaluation Method 2 transfer function used in the steam dryer design analyses for EPU. The acceptance limits will be based on BFN Unit 3 steam dryer confirmatory stress analysis results using the MSL strain gauge data collected at EPU conditions. The acceptance limits will ensure the steam dryer stress margins remain above the minimum alternating stress ratio (MASR) determined in the BFN Unit 3 steam dryer EPU confirmatory analyses.
- 4. TVA shall evaluate the BFN Unit 1 limit curves prepared in item (a)3 above based on new MSL strain gauge data collected following the BFN Unit 1 EPU outage at or near 3458 MWt. If the limit curves change, the new post-EPU outage limit curves shall be provided to the NRC Project Manager. TVA shall not increase power above 3458 MWt for at least 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> after the NRC Project Manager confirms receipt of the reports unless, prior to expiration of the 96 hour0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> period, the NRC Project Manager advises that the NRC staff has no objections to the continuation of power ascension.
- 5. TVA shall monitor the MSL strain gauges during power ascension above 3458 MWt for increasing pressure fluctuations in the steam lines. Upon the initial increase of power above 3458 MWt until reaching 3952 MWt, TVA shall collect data from the MSL strain gauges at nominal 2.5 percent of 3458 MWt (approximately 86 MWt) increments and evaluate steam dryer performance based on this data.
- 6. During power ascension at each nominal 2.5 percent power level above 3458 MWt (approximately 86 MWt), TVA shall compare the MSL data to the approved limit curves based on end-to-end B&Us from the BFN Unit 3 benchmarking at EPU conditions and determine the MASR.
BFN-UNIT 1 Renewed License No. DPR-33 Amendment No. 299
ATTACHMENT 2 Retyped Proposed Renewed Facility Operating License Change
-6a-active MSL strain gauges is less than two strain gauges (180 degrees apart) at any of the eight MSL locations, TVA will stop power ascension and repair/replace the damaged strain gauges and only then resume power ascension.
- 3. At least 60 days prior to exceeding 3458 MWt after the BFN Unit 1 EPU outage, TVA shall revise the BFN Unit 1 replacement steam dryer (RSD) analysis utilizing the BFN Unit 3 on-dryer strain gauge based end-to-end bias and uncertainties (B&Us) at EPU conditions, and submit the information including the updated limit curves and a list of dominant frequencies for BFN Unit 1, to the NRC as a report in accordance with 10 CFR 50.4.
- a. If the on-dryer instrumentation was not available when BFN Unit 3 reached a power level of 3458 MWt and the BFN-specific bias and uncertainty data and transfer function could not be developed, the predicted dryer loads during the BFN Unit 1 power ascension will be calculated with the Plant Based Load Evaluation Method 2 transfer function used in the steam dryer design analyses for EPU. The acceptance limits will be based on BFN Unit 3 steam dryer confirmatory stress analysis results using the MSL strain gauge data collected at EPU conditions. The acceptance limits will ensure the steam dryer stress margins remain above the minimum alternating stress ratio (MASR) determined in the BFN Unit 3 steam dryer EPU confirmatory analyses.
- 4. TVA shall evaluate the BFN Unit 1 limit curves prepared in item (a)3 above based on new MSL strain gauge data collected following the BFN Unit 1 EPU outage at or near 3458 MWt. If the limit curves change, the new post-EPU outage limit curves shall be provided to the NRC Project Manager. TV A shall not increase power above 3458 MWt for at least 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> after the NRC Project Manager confirms receipt of the reports unless, prior to expiration of the 96 hour0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> period, the NRC Project Manager advises that the NRC staff has no objections to the continuation of power ascension.
- 5. TVA shall monitor the MSL strain gauges during power ascension above 3458 MWt for increasing pressure fluctuations in the steam lines. Upon the initial increase of power above 3458 MWt until reaching 3952 MWt, TVA shall collect data from the MSL strain gauges at nominal 2.5 percent of 3458 MWt (approximately 86 MWt) increments and evaluate steam dryer performance based on this data.
- 6. During power ascension at each nominal 2.5 percent power level above 3458 MWt (approximately 86 MWt), TVA shall compare the MSL data to the approved limit curves based on end-to-end B&Us from the BFN Unit 3 benchmarking at EPU conditions and determine the MASR.
BFN-UNIT 1 Renewed License No. DPR-33 Amendment No.