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EPID:L-2022-LRM-0077, October 13, 2022 Public Meeting on 5th Interval Alternative Planned Requests - Licensee Slides (Open) |
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MONTHYEARML22285A1902022-10-13013 October 2022 October 13, 2022 Public Meeting on 5th Interval Alternative Planned Requests - Licensee Slides Project stage: Request ML22319A1952022-12-0202 December 2022 Summary of October 13, 2022, Meeting with Tennessee Valley Authority to Discuss Planned Alternative Requests for the Fifth 10-Year Inservice Testing Program Interval for Brown'S Ferry Nuclear Plant, Units 1, 2, and 3 Project stage: Meeting 2022-10-13
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Category:Meeting Summary
MONTHYEARML24008A1592024-01-18018 January 2024 Summary of December 13, 2023, Meeting with Tennessee Valley Authority Regarding a Proposed Change to the Tennessee Valley Authority Nuclear Quality Assurance Plan ML23270A0702023-09-26026 September 2023 SLRA Pre-Application Meeting Summary 09-13-2023 ML23157A1272023-06-13013 June 2023 Meeting Summary for Environmental Pre-Submittal Meeting for Subsequent License Renewal Application on May 11, 2023 ML23142A2132023-05-22022 May 2023 Public Meeting Summary - 2022 Annual Assessment Meetings for Browns Ferry, Sequoyah and Watts Bar Nuclear Plants ML22319A1952022-12-0202 December 2022 Summary of October 13, 2022, Meeting with Tennessee Valley Authority to Discuss Planned Alternative Requests for the Fifth 10-Year Inservice Testing Program Interval for Brown'S Ferry Nuclear Plant, Units 1, 2, and 3 ML22298A1612022-11-17017 November 2022 Summary of Public Meeting on SAMA with TVA ML22266A2742022-09-28028 September 2022 Summary of September 22, 2022, Public Meeting with Tennessee Valley Authority to Discuss a Request to Use a Later Edition of the ASME OM Code ML22108A1842022-04-18018 April 2022 TVA 2021 Annual Assessment Public Meeting Summary ML22103A2472022-04-14014 April 2022 Summary of April 12, 2022, Closed Meeting with Tennessee Valley Authority to Discuss Recently Identified Errors Potentially Affecting the Browns Ferry Revised Criticality Analysis License Amendment Request ML22094A1112022-04-0404 April 2022 Public Meeting Summary 2021 Annual Assessment Meeting Catawba Dockets Nos. 50-413 and 50-414; McGuire No. 50-369 and 50-370; Oconee. 50-269, 50-270, and 50-287 ML22083A0762022-03-24024 March 2022 Summary of March 17, 2022, Closed Meeting with Tennessee Valley Authority to Discuss Recently Identified Errors Potentially Affecting the Browns Ferry Atrium 11 License Amendment Request (EPID L-2021-LLA-0132 ML21291A0092021-11-0303 November 2021 Tennessee Valley Authority Fleet - Summary of October 13, 2021, Teleconference with Tennessee Valley Authority to Discuss Planned License Amendment Requests Related to the Emergency Action Level Scheme ML21266A0532021-10-20020 October 2021 Summary of September 22, 2021, Meeting with Tennessee Valley Authority Regarding Planned License Amendment Request to Adopt Technical Specifications Task Force (TSTF)-205 and TSTF-563 ML21273A1922021-10-12012 October 2021 September 27, 2021, Summary of Meeting with Browns Ferry Nuclear Plant, Units 1 & 2 Related to a Planned Alternative Request Per American Society of Mechanical Engineers (Asmee) Code Case N-526, Alternative Requirements for Successive Sect ML21251A1122021-09-14014 September 2021 Summary of September 7, 2021, Teleconference with Tennessee Valley Authority to Discuss a Planned License Amendment ML21165A1482021-06-30030 June 2021 Summary of Closed Meeting with Tennessee Valley Authority to Discuss Planned Requests for Exemption from Certain Requirements of 10 CFR Part 37 ML21155A0212021-06-0808 June 2021 Summary of Teleconference with Tennessee Valley Authority to Discuss a Planned License Amendment ML21137A0022021-05-17017 May 2021 Public Meeting Summary - Browns Ferry, Sequoyah and Watts Bar Nuclear Plants, Docket Nos. 50-259, 50-260, 50-296, 50-327, 50-328, 50-390, and 50-391, Meeting Number 20210392 ML20357A0092021-01-19019 January 2021 Summary of December 17, 2020, Teleconference with Tennessee Valley Authority Regarding Planned License Amendment Request Related to Use of Alternate Probability of Detection at Watts Bar Nuclear Plant, Unit 2 ML20175A8012020-08-11011 August 2020 Summary of June 23, 2020, Public Meeting with Tennessee Valley Authority to Discuss a Planned License Amendment ML20162A1532020-06-25025 June 2020 Summary of June 8, 2020, Partially Closed Meeting with Tennessee Valley Authority to Discuss a Planned License Amendment ML20127H8412020-05-0606 May 2020 Public Meeting Summary - Browns Ferry, Sequoyah and Watts Bar Nuclear Plant, Meeting No. 20200384 ML20094M9012020-04-13013 April 2020 Summary of April 2, 2020 Public Meeting with Tennessee Valley Authority Regarding the Future Submittal of a License Amendment Request Adoption of 10 CFR 50.69 ML19120A2882019-06-0606 June 2019 Summary of March 19, 2019, Closed Meeting with Tennessee Valley Authority a License Amendment Request to Implement Maximum Extended Line Limit Analysis Plus ML19120A3692019-04-30030 April 2019 Public Meeting Summary - Browns Nuclear Plant, Docket No. 50-259, 50-260, and 50-296 ML18242A4882018-09-24024 September 2018 Summary of Pre-Application Conference Call with Tennessee Valley Authority to Discuss Proposed Changes to Modifications Associated with Approved NFPA 805 for Browns Ferry Nuclear Plant, Units 1, 2, and 3 ML18101A1012018-04-13013 April 2018 Summary of March 16, 2018, Meeting with Tennessee Valley Authority Regarding a License Amendment Request to Implement Maximum Extended Load Line Limit Analysis Plus for Browns Ferry Nuclear Plant ML18068A0792018-03-15015 March 2018 Summary of Pre-Application Meeting with Tennessee Valley Authority Regarding a Planned License Amendment Request Associated with Modifications to the Control Bay Chillersystems at Browns Ferry Units 1, 2 and 3 ML18053A5362018-03-0101 March 2018 Summary of February 7, 2018, Pre-Application Conference Call with TVA a Planned License Amendment Request to Change the Emergency Response Organization Staffing ML17278A8972017-10-17017 October 2017 Summary of Meeting with TVA Regarding Hydrology-Related Licensing Actions, Browns Ferry, Units 1, 2, and 3, Sequoyah Nuclear, Units 1 and 2 and Watts Bar Nuclear Plant, Units 1 and 2(EPID L2016-TOP-0011; CAC Nos. MF8391-MF8397 ML17227A5142017-09-0101 September 2017 Summary of August 1, 2017, Pre-Submittal Public Meeting with TVA Regarding a Class 1E Unbalanced Voltage Relay Licensing Amendment Request for Browns Ferry Nuclear Plant, Sequoyah Nuclear Plant, and Watts Bar Nuclear Plant ML17131A2512017-05-11011 May 2017 Summary of Public Meeting Concerning Annual Assessment of Browns Ferry Nuclear Plant, Units 1, 2, and 3 ML17061A6722017-04-0606 April 2017 Summary of February 15, 2017, Meeting with Tennessee Valley Authority on Updates to the Transmission System Regarding Extended Power Uprate for Browns Ferry Nuclear Plant, Units 1, 2, and 3 ML17017A4552017-02-0303 February 2017 Summary of Meeting with Tennessee Valley Authority Regarding Maximum Extended Load Line Limit Plus Pre-Application Meeting for Browns Ferry Nuclear Plant ML16350A2962016-12-14014 December 2016 Enclosure 3- Reactor Oversight Process Task Force FAQ Log- November 16, 2016 ML16280A2912016-10-31031 October 2016 September 23, 2016, Summary of Public Meeting with TVA Regarding Hydrology-Related Licensing Actions, Browns Ferry Nuclear Plant, Units 1, 2, and 3, Sequoyah Nuclear Plant, Units 1 & 2 and Watts Bar Nuclear Plant, Units 1 & 2 (CAC Nos. MF83 ML16279A2332016-10-0505 October 2016 Summary of Closed Pre-Decisional Enforcement Conference with Tennessee Valley Authority Regarding Browns Ferry Nuclear Plant ML16210A4532016-08-16016 August 2016 07/19/2016 Summary of Meeting with Tennessee Valley Authority Regarding Extended Power Uprate License Amendment Request for Browns Ferry Nuclear Plant (CAC Nos. MF6741, MF6742, and MF6743) 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 ML16153A1982016-06-0101 June 2016 2015 EOC Meeting Summary ML16043A2772016-03-14014 March 2016 Summary of Meeting with Tennessee Valley Authority Regarding a License Amendment Request to Modify Browns Ferry Technical Specifications (TS) by Adding New TS 3.3.8.3 (CAC Nos. MF6738, MF6739 and MF6740) ML15321A4942015-11-30030 November 2015 Summary of Public Meeting with Tennessee Valley Authority Regarding the Planned Extended Power Uprate License Amendment Request for Browns Ferry Nuclear Plant ML15295A2602015-11-0404 November 2015 July 14, 2015, Summary of Public Meeting with Tennessee Valley Authority to Discuss Topics Regarding Seismic Risk Evaluations Related to the Seismic Hazard Reevaluation for Browns Ferry Nuclear Plant (TACs MF3764, MF3765 and MF3766) ML15146A2792015-05-21021 May 2015 Bf EOC Meeting Summary 2015 ML14204A2672014-08-15015 August 2014 Summary of July 10, 2014, Meeting Between the Tennessee Valley Authority and the Nuclear Regulatory Commission to Discuss Near-Term Task Force Recommendation 2.1 Flooding Hazard Reevaluation Report and Improved Mitigation System Quarterly U ML14197A6082014-08-0606 August 2014 July 1, 2014, Summary of Category 1 Public Meeting with Tennessee Valley Authority to Discuss Seismic Hazard Reevaluations Associated with Implementation of Japan Lessons-Learned Near-Term Task Force Recommendation 2.1 ML14147A3222014-05-27027 May 2014 Public Meeting Summary 05/21/2014 to Present Annual Assessment ML14090A4582014-03-31031 March 2014 Public Meeting Summary TVA Synergy Safety Culture Survey Results ML14036A3872014-02-0505 February 2014 Summary of Meeting with Public to Discuss the Results of the Follow-up Inspection of the Items Identified in Confirmatory Action Letter (ML13232A105) of August 22, 2013, and the Status of Nrc'S Performance Assessment of Browns Ferry Unit 1 ML13225A2932013-08-12012 August 2013 7/23-24/2013, Summary of Meeting 2013 U.S. Nuclear Regulatory Commission (NRC) Initial Exam Writers' Workshop 2024-01-18
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December 2, 2022 LICENSEE: Tennessee Valley Authority FACILITIES: Browns Ferry Nuclear Plant, Units 1, 2, and 3
SUBJECT:
SUMMARY
OF OCTOBER 13, 2022, MEETING WITH TENNESSEE VALLEY AUTHORITY TO DISCUSS PLANNED ALTERNATIVE REQUESTS FOR THE FIFTH 10-YEAR INSERVICE TESTING PROGRAM INTERVAL (EPID L-2022-LRM-0077)
On October 13, 2022, a virtual observation public meeting was held between the U.S. Nuclear Regulatory Commission (NRC) and representatives of the Tennessee Valley Authority (TVA, the licensee). The purpose of the meeting was to discuss planned alternative requests for the fifth 10-Year Inservice Testing (IST) Program interval for the Browns Ferry Nuclear Plant, Units 1, 2, and 3 (Browns Ferry or BFN). The meeting notice and agenda, dated September 29, 2022, are available in the Agencywide Documents Access and Management System (ADAMS) Accession No. ML22272A570. A list of attendees is provided in the enclosure.
The licensee presented (ML22285A190) and discussed the following:
o Background American Society of Mechanical Engineers (ASME) Code of Record for the fifth 10-Year IST Program interval at BFN is the 2017 Edition of the ASME OM Code. TVA plans to seek NRC approval to use the 2020 Edition of ASME OM Code for the fifth 10-Year IST Program interval.
o The licensee discussed multiple planned requests (shown below), including the affected components, applicable ASME Code requirements, reason for request, and basis for use. The licensee plans to submit the code edition request along with the following alternative requests.
Request BFN-IST-1 Alternative to Title 10 of the Code of Federal Regulations (CFR),
paragraph 10 CFR 50.55a(b)(3)(xi) for implementing ASME OM Code, Subsection ISTC, paragraph ISTC-3700, for supplementing the control rod drive (CRD) system scram discharge vent (SDV) and drain valve position indicating lights with other indications.
Request BFN-IST-2 Alternative to 10 CFR 50.55a(b)(3)(xi) for implementing ASME OM Code, Subsection ISTC, paragraph ISTC-3700, for supplementing manually operated passive residual heat removal (RHR) system valve position indicating lights with other indications.
Request BFN-IST-3 Alternative to 10 CFR 50.55a(b)(3)(xi) for implementing ASME OM Code, Subsection ISTC, paragraph ISTC-3700, for supplementing main steam line (MSL) drain valve position indicating lights with other indications.
Request BFN-IST-4 Alternative to 10 CFR 50.55a(b)(3)(xi), ASME OM Code, Subsection ISTC, and Mandatory Appendices I and IV, for main steam relief valves (MSRVs).
Request BFN-IST-5 Alternative to 10 CFR 50.55a(b)(3)(xi) for implementing ASME OM Code, Subsection ISTC, paragraph ISTC-3700, for supplementing emergency equipment cooling water (EECW) strainer backwash valve position indicating lights with other indications.
o For each planned request, the licensee noted that the request duration would be for the fifth 10-Year IST Program interval.
o The licensee noted that they are not aware of any precedents for the planned alternative requests.
o The licensee plans to submit the requests by November 30, 2022, and will request NRC authorization by August 31, 2023.
The NRC staff provided the following feedback in response to the licensees presentation:
o With respect to planned request BFN-IST-1, the staff recommended that the alternative request specify the supplemental position verification method for the SDV vent and drain valves and the proposed verification interval as an alternative to the requirements in the ASME OM Code, Subsection ISTC, paragraph ISTC-3700, as supplemented by 10 CFR 50.55a(b)(3)(xi), rather than referencing the Technical Specifications (TS) or Surveillance Frequency Control Program (SFCP) in the request. The licensee may reference an applicable ASME OM Code Case that has been accepted in NRC Regulatory Guide 1.192 as incorporated by reference in 10 CFR 50.55a in the alternative request, or may include a justification for the use of an applicable OM Code Case directly in the alternative request prior to the acceptance of the OM Code Case in RG 1.192.
o With respect to planned request BFN-IST-2, the staff recommended that the alternative request specify the supplemental position verification method for the locally manually operated RHR system valves and the proposed verification interval as an alternative to the requirements in the ASME OM Code, Subsection ISTC, paragraph ISTC-3700, as supplemented by 10 CFR 50.55a(b)(3)(xi). The licensee should provide justification that these specified passive valves have no safety function to open, and no procedures that require their opening.
o With respect to planned request BFN-IST-3, the staff recommended that the alternative request specify the supplemental position verification method for the (MSL) drain valves and the proposed verification interval as an alternative to the requirements in the ASME OM Code, Subsection ISTC, paragraph ISTC-3700, as supplemented by 10 CFR 50.55a(b)(3)(xi). The staff recommended that the licensee review the recent report on valve stem-disk connections prepared by the Electric Power Research Institute (EPRI) and reviewed by the NRC in a safety evaluation for information that could help support its justification for an alternative to the ASME OM Code, Subsection ISTC, paragraph ISTC-3700, as supplemented by 10 CFR 50.55a(b)(3)(xi).
o With respect to planned request BFN-IST-4, the staff recommended that the licensee clarify the specific requirements in the ASME OM Code, paragraph ISTC-3700, Appendix I and Appendix IV, as supplemented by 10 CFR 50.55a(b)(3)(xi) for which an alternative is being requested for the MSRVs. For example, the licensee should provide justification that the Appendix I testing meets the intent of the Appendix IV testing that the MSRVs are operationally ready to perform their safety functions if this is an alternative being requested by the licensee. The staff also requested that the licensee clarify the discussion of the credit for remote-manual operation of only 6 of the 13 MSRVs. The staff recommended that for each aspect of the request, the licensee specify the alternative method and interval for the applicable ASME OM Code requirements as incorporated by reference in 10 CFR 50.55a.
o With respect to planned request BFN-IST-5, the staff recommended that the alternative request specify the supplemental position verification method for the EECW strainer backwash valves and the proposed verification interval as an alternative to the requirements in the ASME OM Code, Subsection ISTC, paragraph ISTC-3700, as supplemented by 10 CFR 50.55a(b)(3)(xi). For example, the staff recommended that the licensee discuss verification of both the open and close valve positions as part of the alternative request. The staff also noted that the EPRI report and NRC safety evaluation on valve stem-disk connections might provide useful information for the alternative request.
There were no members of the public in attendance.
Please direct any inquiries to me at 301-415-3867, or Michael.Mahoney@nrc.gov.
Sincerely,
/RA/
Michael Mahoney, Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-259, 50-260, and 50-296
Enclosure:
List of Attendees cc: Listserv
LIST OF ATTENDEES OCTOBER 13, 2022, PUBLIC MEETING WITH TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT, UNITS 1, 2 AND 3 PLANNED ALTERNATIVE REQUESTS FOR THE FIFTH INSERVICE TESTING PROGRAM INTERVAL Name Organization Michael Mahoney U.S. Nuclear Regulatory Commission (NRC)
Thomas Scarbrough NRC Gurjendra Bedi NRC Stewart Bailey NRC Yuken Wong NRC Perry Buckberg NRC Russ Wells Tennessee Valley Authority (TVA)
Beau Eckermann TVA Robert Shaler TVA Mark Gowin TVA Kevin Groom TVA Fred Nilsen TVA Mike Taggins TVA Enclosure
Package: ML22319A219 Meeting Notice: ML22272A570 Meeting Summary: ML22319A195 OFFICE NRR/DORL/LPL2-2/PM NRR/DORL/LPL2-2/LA NRR/DEX/EMIB NAME MMahoney RButler SBailey DATE 11/14/2022 11/17/2022 12/02/2022 OFFICE NRR/DORL/LPL2-2/BC NAME DWrona DATE 12/02/2022