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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 ML23325A2432023-11-13013 November 2023 Regulatory Conference Summary ML23325A2442023-11-13013 November 2023 Enclosure 1 - Attendance List ML23325A2452023-11-13013 November 2023 Enclosure 2 - Dominion Slides ML23331A7892023-11-0909 November 2023 Nov. 2023 Enviro Scoping Meetings Related to the V.C. Summer Subsequent License Renewal Application Meeting Summary ML23304A0682023-11-0606 November 2023 Summary of October 24, 2023, Public Mtg W/Tennessee Valley Authority Regarding Proposed License Amendment Request for Watts Bar Nuclear Plant, Units 1 and 2, and Sequoyah Nuclear Plant, Units 1 and 2 to Revise Function 5, Turbine Trip and F ML23265A1512023-09-28028 September 2023 Summary of September 12, 2023, Partially Closed Meeting with Tennessee Valley Authority to Discuss Proposed License Amendment Request ML23270A0702023-09-26026 September 2023 SLRA Pre-Application Meeting Summary 09-13-2023 ML23198A3102023-07-20020 July 2023 July 10, 2023, Summary of Public Meeting with Tennessee Valley Authority Regarding Proposed License Amendment Request for Watts Bar Nuclear Plant, Units 1 and 2 ML23171A9172023-06-20020 June 2023 Summary of Meeting Concerning the V.C. Summer Nuclear Station, to Discuss Annual Assessment for Period Jan 1, 2022 Through December 31, 2022 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 ML23068A1532023-03-16016 March 2023 Summary of February 22, 2023, Meeting with Tennessee Valley Authority Regarding Proposed License Amendment Request to Increase Allowable Number of Tritium Producing Burnable Absorber Rods at Watts Bar Nuclear Plant, Units 1 and 2 ML23055A4562023-03-0909 March 2023 Summary of February 15, 2023, Public Meeting with Tennessee Valley Authority Regarding Proposed Expedited License Amendment Request for Watts Bar Nuclear Plant, Units 1 and 2 ML22329A1382022-12-0505 December 2022 Summary of Meeting with Tennessee Valley Authority Related to Planned Alternative Request WBN-2-ISI-01 for Watts Bar Nuclear Plant, Unit 2 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 ML22312A3522022-12-0101 December 2022 Revised - Summary of Regulatory Audit for Alternative Request RV-02 ML22298A1612022-11-17017 November 2022 Summary of Public Meeting on SAMA with TVA ML22270A2042022-09-30030 September 2022 Summary of Meeting Regarding a Potential Request to Modify the Reactor Vessel Surveillance Capsule Withdrawal Schedule for VC Summer 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 ML22207B8302022-07-28028 July 2022 Summary of July 20, 2022, Observation Public Meeting with the Tennessee Valley Authority to Discuss Planned Alternative Request RP-12 to ASME OM Code Testing for the 1B-B Centrifugal Charging Pump at Sequoyah Nuclear Plant, Unit 1 ML22168A1642022-06-27027 June 2022 Summary of June 9, 2022, Meeting with TVA Regarding a Proposed License Amendment Request Related to Low Temperature Overpressure System and Cold Overpressure Mitigation System for Sequoyah and Watts Bar Nuclear Plants ML22151A3332022-05-31031 May 2022 Public Meeting Summary 2021 Annual Assessment Meeting Regarding the V.C. Summer Nuclear Station, Docket No. 50-395, Meeting Number 20220449 ML22109A0042022-04-20020 April 2022 Summary of Meeting with Tennessee Valley Authority Regarding a Proposed Alternative Request Related to Testing of the Motor-Driven Auxiliary Feedwater Pumps at Sequoyah and Watts Bar Nuclear Plants ML22104A2252022-04-20020 April 2022 Summary of Meeting with Tennessee Valley Authority Regarding a Proposed Exemption Request for Watts Bar Nuclear Plant, Unit 2 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 ML22048B7852022-03-0202 March 2022 Summary of February 16, 2022, Public Preapplication Meeting with Tennessee Valley Authority Regarding a Future Submittal of a Request for an Alternative to Requirements for Addressing Pressure Isolation Valve Leakage ML22042B3262022-02-14014 February 2022 Summary of February 8, 2022, Meeting with Tennessee Valley Authority Regarding a Proposed License Amendment Request to Revise the Allowable Value for Trip of Turbine-Driven Main Feedwater Pump at Watts Bar Nuclear Plant, Unit 1 ML22025A3112022-02-0909 February 2022 Summary of January 19, 2022, Meeting with Tennessee Valley Authority Regarding a Proposed Schedule for Development of a License Amendment Request for Increased Tritium Production ML21349A3642022-01-0404 January 2022 Summary of December 14, 2021, Teleconference with Tennessee Valley Authority Regarding a Proposed Change to the Capsule Withdrawal Schedule for Watts Bar Nuclear Plant, Unit 2 ML21313A3482021-11-18018 November 2021 Summary of Public Preapplication Meeting with Tennessee Valley Authority Regarding a Future Submittal of a License Amendment Request Regarding Seismic and Fire Probabilistic Risk Assessment (PRA) Modifications to 10 CFR 50.69 ML21279A0902021-11-0303 November 2021 Summary of Conference Calls Regarding the Fall 2021, Mid-Cycle Steam Generator Tube Inspections 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 ML21265A5142021-10-12012 October 2021 Summary of September 15, 2021, Public Preapplication Meeting with Tennessee Valley Authority Regarding a Future Submittal of a License Amendment Request Regarding Elimination of the High Negative Flux Rate Trip ML21253A0872021-09-15015 September 2021 Summary of August 19, 2021, Partially Closed Meeting with Tennessee Valley Authority to Discuss Mid-Cycle Outage Contingencies for Watts Bar Nuclear Plant, Unit 2 ML21245A4252021-09-15015 September 2021 Summary of August 19, 2021, Teleconference with Tennessee Valley Authority Regarding Planned License Amendment Request Related to the Watts Bar Nuclear Plant, Units 1 and 2 ML21251A1122021-09-14014 September 2021 Summary of September 7, 2021, Teleconference with Tennessee Valley Authority to Discuss a Planned License Amendment ML21218A1472021-08-11011 August 2021 August 5, 2021 N-769 Relief Pre-Submittal Meeting Summary 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 ML21152A1252021-06-0202 June 2021 Summary of Verbal Authorization of Alternative Request RP-10 for the 1B-B Motor Driven Auxiliary Feedwater Pump 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 ML21131A1612021-05-11011 May 2021 Public Meeting Summary - 2020 Annual Assessment Meeting Regarding Virgil C. Summer Nuclear Station, Docket No. 50-395; North Anna Power Station, Docket Nos. 50-338 and 50-339; and Surry Power Station, Docket Nos. 50-280 and 50-281, Meeting ML21120A2192021-05-0404 May 2021 April 28,2021, Summary of Meeting with Tennessee Valley Authority Related to a Planned License Amendment Request for Watts Bar Nuclear Plant, Units 1 and 2, to Remove from Technical Specifications Redundant Units of Measurement for Control ML21112A3262021-04-30030 April 2021 Summary of April 21, 2021, Teleconference with Tennessee Valley Authority to Discuss a Planned License Amendment Request for Sequoyah Nuclear Plant, Units 1 and 2 2024-01-18
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ENCLOSURE 2The following questions/comments were provided via comment cards during the January 9through 10, 2006, Nuclear Regulatory Commission (NRC) public workshop:Jennifer Weber, TVA - Transmission* Very Important *"Offsite Power" : clearly distinguish throughout when actual real-time physical loss is intendedvs. tech spec "disqualification" (i.e., cannot assure adequacy for a subsequent DBE) vs.
"external power," which seems to be the intent of the section on emergency restoration (i.e., will run plant loads, but not necessarily be TS/DBE-qualified for start-up purposes).NRC Response:Questions 3 and 4 in the Generic Letter address the issue of adequacy of offsite power andmeeting the N-1 contingency for satisfying the Technical Specification requirements. Question7 in the Generic Letter addresses procedures required for making local power sources (offsite or onsite) to resupply the nuclear power plant following a loss-of-offsite power (LOOP) or an station blackout (SBO). The information requested in questions 3, 4, and 7 of the GenericLetter are needed to assess whether the nuclear power plant is meeting its regulatory requirements to which it was licensed. Jennifer Weber, TVA - Transmission"Stressed grid" & "degraded grid" : these terms are too broad, vague, and subjective and should be eliminated from the GL unless more specifically defined. Consider term such as "periods of increased risk to offsite power adequacy."NRC Response:The revised Generic Letter contains a section on "Definitions," which provides clarification on"Stressed grid," and "degraded grid," so that these terms are clearly defined and clarified.Jennifer Weber, TVA - TransmissionEliminate use of term "reliability," which NERC relates to the ability of the Transmissionoperator to maintain positive control of the grid. Even if controlled load shed or generation trips are required. Instead, use "offsite power adequacy," since nuclear O.P. is a special form of grid customer demand.NRC Response:The terms "adequate offsite power," and "grid reliability," are defined and clarified under thesection, "Definitions," in the revised Generic Letter. We believe there is no need to eliminate the term "reliability."
Jennifer Weber, TVA - TransmissionEliminate use of term "stability," which is a narrow technical term relating to the damping ofpost-disturbance oscillations as the system transitions to a new steady-state condition. Instead,refer to "offsite power adequacy or risk."NRC Response:Refer to the "Definitions" section in the revised Generic Letter that clarifies this term.Jennifer Weber, TVA - Transmission"Reactor trip" and similar terms: change to "worst-case Design Basis Event (DBE), such asa LOCA shutdown or full-load rejection, including the associated changes in plant loads."NRC Response:The reactor trip (or unit trip) may occur independent of design bases event (DBE), thereforethese terms are not the same. The term 'reactor trip' is used in Regulatory Guide 1.155 and other NRC documents such as the Standard Review Plan (NUREG-800). Therefore, it is notprudent to accept the above proposed change.Jennifer Weber, TVA - TransmissionNote that a unit trip "contingency" that is modeled for Bulk System Reliability and NERCcompliance purposes is not the same as a DBE shutdown that must be considered for offsite power adequacy/qualification purposed (i.e., with associated changes to load magnitude and source alignment).
- Define "contingency" clearly for the intended purpose.NRC Response:See the "Definitions" section in the revised Generic Letter where N -1 contingency is defined.Jennifer Weber, TVA - Transmission Q2 Please clearly define "RTCA" in light of Mr. Paul Gill's comment that it is int ended to bea generic term that encompasses a variety of possible tools. What are the specificcharacteristics of the tool/ process that the NRC is interested in?
(e.g., use of near-real-time models vs. bounding models).NRC Response:See the "Definitions" section in the revised Generic Letter where Real Time ContingencyAnalysis (RTCA) is defined for clarification.
Jennifer Weber, TVA - Transmission*Very Important*
Q2To meet the stated intention of determining how Licensees continue to ensure that theiroffsite power analysis remain adequate given dramatically changing grid conditions, rather than implying the requirement to use a particular tool, rephrase each subquestion to focus on the underlying safety requirement rather than how an RTCA in particular would handle it. NRC Response:See the revised Generic Letter for added clarification of each question.Jennifer Weber, TVA - TransmissionQ2 (a) Rephrase to something like "Given the greater variability in system flow patterns from historical norms, how are actual grid conditions evaluated to ensure that offsite power remains adequate."NRC Response:See the revised Generic Letter for added clarification of each question.Jennifer Weber, TVA - TransmissionQ2 (h) "...not available to the NPP's TSO"Change to "... not used by the NPP's TSO for offsite power adequacy determination,""...for the TSO to obtain one?"Change to "... for the TSO to use a RTCA for official offsite power adequacy determinations."NRC Response:See the revised Generic Letter for added clarification of each of these questions.Jennifer Weber, TVA - TransmissionQ2 (j) Please clarify how (a) - (i) constitute "provisions of GDC 17," compliance with which is called into question if a RTCA is not used.NRC Response:Given that the grid is being operated in manner that may not be within the constraints of theoriginal analysis, the question then arises how are nuclear power plants meeting their licensing basis? Further, if the grid operations and flows change on daily basis or hourly basis, how do you verify that it is being operated within the bound of the original analysis? One way to assure this is by operating the grid within the confines of a bounding analysis. The second option is to assess via a real time analysis such as RTCA (or some other tool) that the grid will not degrade the offsite power system as set forth in the nuclear power plant license (i.e., General DesignCriterion (GDC) 17 and other GDCs that rely on offsite power). The staff believes that an analysis is needed to assess grid conditions to ensure adequate offsite power given that the grid is not being operated in the manner that was used in the licensing bases of the nuclearpower plant. Jennifer Weber, TVA - TransmissionQ3 (a) Note that O.P. operability is not required to withstand a grid failure, such as a line trip. "stability" studies that consider line and load trips, etc. are very different from offsite power degraded voltage studies.NRC Response:The nuclear power plant was licensed to withstand the loss of the largest supply (nuclear ornon-nuclear), the most critical transmission line, or largest load to ensure that the offsite power will have the c apability and capacity (GDC 17) to supply the design basis event loads. Therequirements of GDC 17 were embodied in the Technical Specifications that established theoperating requirements and the associated Limiting Conditions for Operations. Jennifer Weber, TVA - TransmissionQ4 "... remain operable following a trip of your NPP" Redundant, or could imply double-contingency. "Operability" is determined by evaluating a postulated NPP DBE shutdown. NRC Response:The licensing basis of the nuclear power plant is that the offsite power remains operable(capability and capacity) following a trip of the reactor. Therefore, licensees have to ensure thatthis capability is not compromised for a DBE or other events as specified in the license of thenuclear power plant.Jennifer Weber, TVA - TransmissionQ5 (c) "Stress on grid" too broad, vague, undefinedQ5 (c)and (d) "Seasonal variations" consider instead referring to "definable periods of increased risk to offsite power adequacy"Q5 (i) "Such a condition" Spell out the condition being referred toQ5 (l) "Worsening degraded grid, reliability, conditions" "offsite power and adequacy conditions"NRC Response:See the revised Generic Letter where all of the above terms have been defined and clarified.
Dan Goldston, SCANA, SCE>here seems to be an implicit assumption that using and passing an RTCA will provideassurance that a Degraded or Undervoltage actuation will not occur. Our RTCA is steady stateto steady state - it does not predict minimum voltage or it's duration during a transient. I suspect this is true for most of them. This is in spirit of very conservative bus voltage violation limits for the RTCA - well above degraded voltage or undervoltage setpoints.NRC Response:We agree that an RTCA type tool should be used to predict minimum voltage and it's durationduring a transient for the conditions that the plant was licensed to in order assure that adequateoffsite power will be available upon the trip of the nuclear power plant. ADAMS/ACCESSION NO.: ML060170552