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MONTHYEARML0603800332006-02-0909 February 2006 RAI, Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design-Basis Accidents at Pressurized-Water Reactors Project stage: RAI ML0617304622006-06-22022 June 2006 Request for Extension for Completing Corrective Actions for Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Request NL-06-1483, Response to NRC RAI on SNC Request for Extension for Completing Corrective Actions for GL 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors2006-07-28028 July 2006 Response to NRC RAI on SNC Request for Extension for Completing Corrective Actions for GL 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Request ML0625002692006-09-0707 September 2006 Approval of Generic Letter 2004-02 Extension Request Project stage: Other ML0734400422007-12-0707 December 2007 Generic Letter 2004-02 Response Extension Request - Chemical Effects Project stage: Request ML0734400442007-12-0707 December 2007 Generic Letter 2004-02 Response Extension Request Project stage: Request ML0735201452007-12-19019 December 2007 Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors, Extension Request Approval Project stage: Other ML0806406012008-02-28028 February 2008 Supplemental Response to NRC Generic Letter 2004-02 Project stage: Request ML0814301542008-05-21021 May 2008 Request for Implementation Extension for License Amendment Request to Revise Technical Specification (TS) 3.3.2, ESFAS Instrumentation, and TS 3.5.4, Refueling Water Storage Tank (Rwst) Project stage: Request ML0816406172008-05-21021 May 2008 Supplemental Response to NRC Generic Letter 2004-02 Project stage: Request ML0814306162008-05-22022 May 2008 Generic Letter 2004-02 Response Extension Request Project stage: Request ML0814903662008-05-29029 May 2008 Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors, Extension Request Approval (Tac Nos. MC4727 and MC4728) Project stage: Other ML0821705132008-07-31031 July 2008 Supplemental Response to NRC Generic Letter 2004-02 Project stage: Request ML0821704872008-07-31031 July 2008 Generic Letter 2004-02 Response Extension Request Project stage: Request ML0821703062008-07-31031 July 2008 Generic Letter 2004-02 Response Extension Request Project stage: Request ML0822605042008-08-18018 August 2008 Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors, Extension Request Approval Project stage: Other NL-08-1228, Supplemental Response to NRC Generic Letter 2004-022008-08-22022 August 2008 Supplemental Response to NRC Generic Letter 2004-02 Project stage: Supplement ML0823808902008-08-22022 August 2008 Supplemental Response to NRC Generic Letter 2004-02 Project stage: Supplement ML0825602332008-09-17017 September 2008 Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Other ML0831001422008-12-0202 December 2008 Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors, Request for Additional Information (TAC Nos. MC4727 Project stage: RAI ML0920804202009-07-28028 July 2009 Notice of Conference Call with Southern Nuclear Operatingcompany, Inc Project stage: Other ML0923706302009-08-31031 August 2009 Summary of Category 1 Public Meeting Via a Conference Call with Southern Nurclear Opertaing Company, Inc (Snc), to Discuss the Request for Additional Information Pertaining to Generic Letter 2004-02 Project stage: RAI ML0927100542009-09-28028 September 2009 Notice of Forthcoming Conference Call with Southern Nuclear Operating Company, Inc., to Discuss the Licensees Planned Overall Path Forward Re the Response NRCs RAI Pertaining to Generic Letter 2004-02 Project stage: RAI ML0927400232009-10-0101 October 2009 Corrected Notice Conference Call with Southern Nuclear Operating Company, Inc., to Discuss the Licensees Planned Overall Path Forward Project stage: Other ML0931701452009-12-0101 December 2009 Summary of Public Conference Call with Southern Nuclear Operating Co, to Discuss the Request for Additional Information (RAI) Pertaining to Generic Letter 2004-02 (Tac Nos. MC4727 and MC4728) Project stage: RAI ML15126A2562015-05-0606 May 2015 GSI-191 Program Chemical Effects Testing Strainer Headloss Testing NRC Public Meeting - November 6, 2014 Project stage: Request ML15126A3032015-05-0808 May 2015 Summary of Meeting with SNC on GSI-191 Program for the VEGP Project stage: Meeting 2008-05-29
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Text
LICENSEE:
Southern Nuclear Operating Company (SNC)
FACILITY:
Vogtle Electric Generating Plant, Units 1 and 2 (VEGP)
SUBJECT:
SUMMARY
OF NOVEMBER 6, 2014, MEETING WITH SNC ON GSl-191 PROGRAM FOR THE VEGP (TAC NOS. MC4727 AND MC4728)
On November 6, 2014, a Category 1 public meeting was held between the U.S. Nuclear Regulatory Commission (NRC) and SNC representatives at NRC Headquarters, One White Flint North, 11555 Rockville Pike, Rockville, Maryland. The licensee's objectives in the meeting were to provide an overview of their plans for future large scale chemical effects and strainer head loss testing, and receive any comments, concerns or feedback from NRC staff. The meeting notice and agenda, dated October 23, 2014, is available in the Agencywide Documents Access and Management System (ADAMS) at Accession No. ML14296A292. A list of attendees is provided as Enclosure 1. The licensee provided slides for its presentation (ADAMS Accession No. ML15126A256).
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The VEGP includes two Westinghouse four-loop pressurized water reactors with characteristics relevant to this issue as follows: 99 percent NUKON insulation; 6 cubic feet of lnteram fire barrier material; GE Stacked Disk Strainers (4 per unit) for ECCS and Containment Spray (CS) to provide 765 square feet of strainer for each of the two ECCS trains, two separate CS strainers (each with 590 square feet); and trisodium phosphate as a buffer. The licensee stated that the strainer head loss and in-vessel issues remain open for VEGP; that previous chemical effects testing provided very promising results, but were not accepted by NRC and that the licensee has elected to follow Option 2B (risk-informed resolution) of SECY-12-0093, as being piloted by the South Texas Plant.
The licensee provided an overview of its chemical effects testing plans, summarized its previous testing, and described the University of New Mexico testing facility.
The licensee also summarized its risk-informed head loss test strategy, including activities to be performed by Enercon Services, Inc. and the Alden -Research Laboratory. The licensee summarized its head loss testing strategy as follows:
A comprehensive test program is necessary to quantify head loss for thousands of break scenarios.
The rule based approach is a more practical option than a full correlation or test for every break scenario.
o Simplifications of fiber type, particulate surrogate, and water chemistry are necessary to develop a practical test matrix.
Small-scale testing may be utilized to gather a majority of the data. The rule based approach is a more praCtical option than a full correlation or test for every break scenario.
Simplifications of fiber type, particulate surrogate, and water chemistry are necessary to develop a practical test matrix.
Small-scale testing may be utilized to gather a majority of the data.
The NRC staff found the information provided by SNC to be a useful description of the licensee's plans for this program. No regulatory decisions or commitments were made during the meeting.
Members of the public did not participate. Public Meeting Feedback forms were not received.
Docket Nos. 50-424 and 50-425
Enclosure:
List of Attendees cc w/encl: Distribution via Listserv
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f ~~b M~rtin, Senior Project Manager (J. ~lant Licensing Branch LPL2-1
- Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
LIST OF ATTENDEES November 6, 2014 MEETING WITH SNC Licensee Phil Grissom Southern Nuclear Operating Company (SNC)
Ken McElroy SNC Ryan Joyce SNC Owen Scott SNC Franchelli Febo SNC Jim Littleton SNC Kip Walker Enercon Services Blake Stair Enercon Services Tim Sande Enercon Services Edwark Glandforcj University of New Mexico (UNM)
Amir Ali UNM Kerry Howe UNM Steven Unikewicz Alion Science and Technology Janet Leavitt Alion Science and Technology NRC Staff Victor Cusumano DSS/SSIB Stephen Smith DSS/SSIB Ashley Guzetta DSS/SSIB John Stanq DSS/SSIB Gloria Kulesa DE/ESGB Paul Klein DE/ESGB Matt Yoder DE/ESGB Bob Martin DORULPL2-1 Members of the Public Maurice Dingler Wolf Creek NOC Ron Holloway Wolf Creek NOC Eric Federline MPR Associates Enclosure
Meetinq Notice ML14296A292
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Bob Martin, Senior Project Manager Plant Licensing Branch LPL2-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation VCusumano GKulesa SSmith, SSIB PKlein MY oder RPascarelli Meetinq Summary ML15126A303 OFFICE NRR/DORL/LPL2-1/PM N RR/DORL/LPL2-1 /LA NRR/DORL/LPL2-1 /BC NRR/DORL/LPL2-1 /PM NAME BMartin SFigueroa RPascarelli BMartin DATE 05/07/15 05/07/15 05/08/15 05/08/15