Letter Sequence RAI |
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MONTHYEARML0515302672005-06-0303 June 2005
6/3/05, Beaver Valley, RAI, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-Water Reactors
Project stage: RAI
L-05-123, Response to Request for Additional Information on Generic Letter 2004-022005-07-22022 July 2005
Response to Request for Additional Information on Generic Letter 2004-02
Project stage: Response to RAI
ML0603803422006-02-0909 February 2006
Request for Additional Information Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design-Basis Accidents at Pressurized-Water Reactors TAC Nos. MC4665 and MC4666
Project stage: RAI
ML0613802732006-05-18018 May 2006
Request for Scheduler Extension from Generic Letter (GL) 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors (TAC No. MC46666)
Project stage: Other
L-08-054, Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors - Request for Extension of Completion Date for Corrective Actions2008-02-14014 February 2008
Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors - Request for Extension of Completion Date for Corrective Actions
Project stage: Request
L-08-035, Supplemental Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized - Water Reactors2008-02-29029 February 2008
Supplemental Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized - Water Reactors
Project stage: Supplement
ML0812301162008-02-29029 February 2008
Extension Request Approval Letter Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors,...
Project stage: Other
L-08-257, Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors, Request for Extension of Completion Date for Corrective Actions2008-08-28028 August 2008
Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors, Request for Extension of Completion Date for Corrective Actions
Project stage: Request
ML0827402412008-09-30030 September 2008
Extension Request Approval Letter Generic Letter 2004--02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors.
Project stage: Other
L-08-321, Supplemental Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors2008-10-29029 October 2008
Supplemental Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors
Project stage: Supplement
L-09-056, Downstream Effects for Recirculation Spray System Pumps and Low Head Safety Injection System Pumps2009-03-11011 March 2009
Downstream Effects for Recirculation Spray System Pumps and Low Head Safety Injection System Pumps
Project stage: Other
ML0909001932009-03-31031 March 2009
Extension Request Approval Letter Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors,
Project stage: Other
ML0910501002009-04-21021 April 2009
Correction Letter Extension Request Approval to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors
Project stage: Other
L-09-131, Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors - Request for Extension of Completion Date for Additional Corrective Actions2009-04-30030 April 2009
Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors - Request for Extension of Completion Date for Additional Corrective Actions
Project stage: Request
ML0912400302009-05-0505 May 2009
Extension Request Approval Letter Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors.
Project stage: Other
L-09-152, Supplemental Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors.2009-06-30030 June 2009
Supplemental Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors.
Project stage: Supplement
ML1002903182010-02-18018 February 2010
RAI, Supplemental 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
ML1008407562010-03-31031 March 2010
Notice of Teleconference Meeting with Firstenergy Nuclear Operating Company Regarding Mutual Understanding of NRR Staff'S Request for Additional Information and to Discuss Generic Letter 2004-02
Project stage: RAI
ML1013206652010-05-18018 May 2010
Summary of Category 1 Teleconference with Firstenergy Nuclear Operating Company to Discuss NRC Request for Additional Information Regarding Generic Letter 2004-02
Project stage: RAI
L-13-176, Generic Safety Issue 191 Resolution Plan2013-05-16016 May 2013
Generic Safety Issue 191 Resolution Plan
Project stage: Other
2009-03-11
[Table View] |
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Category:Meeting Summary
MONTHYEARML23179A0012023-06-28028 June 2023
6/7/2023 - Annual Assessment Meeting for Pa/Md/Ny/Nj Nuclear Power Plants - Meeting Summary
ML23135A7872023-05-19019 May 2023
Summary of Conference Calls Regarding the Spring 2023 Steam Generator Tube Inspections
ML23026A3552023-01-31031 January 2023
Summary of Public Meeting with Energy Harbor Nuclear Corp. Regarding Beaver Valley Power Station License Amendment Request to Consolidate Fuel Decay Time TS Into New Limiting Condition for Operation
ML22187A1462022-07-0606 July 2022
Joint Annual Assessment Meeting for Pa/Md/Nj/Ny Nuclear Power Plants - Meeting Summary
ML22105A3932022-04-20020 April 2022
Summ. of March 17, 2022, Public Meeting with Ehnc Regarding Planned License Amendment Request to Consolidate Fuel Decay Time Requirements in a New Limiting Condition for Operation for Beaver Valley Power Station, Units 1 and 2
ML22053A2982022-02-25025 February 2022
Summary of the February 15, 2022, Meeting with Energy Harbor Nuclear Corp. Regarding the License Amendment Request Related to Revising TS 5.6.3 Core Operating Limits Report (COLR)
ML21308A0712021-11-0909 November 2021
Summary of Teleconference with Energy Harbor Nuclear Corp. Regarding Fall 2021 Steam Generator Inspections at Beaver Valley Power Station, Unit 2
ML20197A2722020-07-15015 July 2020
2020 Beaver Valley, Calvert Cliffs, Limerick Peach Bottom, Susquehanna Annual Assessment Webinar Summary
ML20148M3852020-06-0101 June 2020
Summary of May 26, 2020, Public Meeting with Energy Harbor Nuclear Corp. Potential License Amendment Request Related to Steam Generator Tube Sleeve Inspections and Maintenance
ML20122A0032020-05-19019 May 2020
Summary of April 22, 2020, Teleconference with Energy Harbor Nuclear Corp. Regarding Spring 2020 Steam Generator Inspections at Beaver Valley Power Station, Unit 2
ML20111A0142020-04-27027 April 2020
Summary of March 31, 2020, Public Meeting with Energy Harbor Nuclear Corp. to Discuss COVID-19 Potential Submittals of Regulatory Actions
ML19280A0382019-10-22022 October 2019
Ti 2515-191 Summary of Findings
ML16125A5072019-10-22022 October 2019
Ti 191 Issue Matrix
ML19191A1882019-07-0909 July 2019
Joint Annual Assessment Meeting (Webinar) for Pennsylvania Power Plants - Meeting Summary
ML18325A0232018-11-28028 November 2018
Summary of Teleconference with Firstenergy Nuclear Operating Company Regarding Fall 2018 Steam Generator Inspections at Beaver Valley Power Station, Unit 2
ML18099A0812018-04-0606 April 2018
Bv Annual Assessment Meeting Summary and Attendance List 2018
ML17347A8082017-12-20020 December 2017
December 5, 2017, Summary of Public Meeting with Firstenergy Nuclear Operating Company to Discuss a Proposed License Amendment Request Extending Sleeve Life on the Steam Generator at Beaver Valley Power Station, Unit 2
ML17158B1662017-06-0909 June 2017
Summary of Meeting with Firstenergy Nuclear Operating Company Regarding the Spring 2017 Steam Generator Inspections at Beaver Valley Power Station, Unit 2
ML17082A1842017-03-28028 March 2017
March 20, 2017, Summary of Annual Assessment Meeting with Beaver Valley, Units 1 and 2
ML16250A5012016-10-0303 October 2016
Summary of August 30, 2016, Meeting with Firstenergy Nuclear Operating Company Regarding Planned Submittal of Emergency Action Level Scheme Change
ML16105A0082016-04-25025 April 2016
March 30, 2016, Summary of Meeting with Firstenergy Nuclear Operating Company on Its Draft Probabilistic Risk Assessment RAI Related to Its License Amendment Request to Adopt NFPA Standard 805
ML16091A0702016-03-31031 March 2016
2016 Beaver Valley Annual Assessment Meeting Summary 2016
ML15320A3912015-11-24024 November 2015
Summary of Conference Call Regarding the Fall 2015 Steam Generator Inspections
ML15225A4812015-08-14014 August 2015
July 23, 2015, Summary of Meeting with Representatives of the U.S. Army Corps, U.S. Nuclear Regulatory Commission and First Energy Nuclear Operating Co. to Discuss Flooding Analysis Associated with Beaver Valley Power Station
ML15135A2982015-05-21021 May 2015
Summary of April 28, 2015, Meeting Between Representatives of the U.S. Army Corps of Engineers, Nuclear Regulatory Commission, and First Energy Nuclear Operating Co. to Discuss Flooding Analysis Associated with Beaver Valley Power Station,
ML15104A6652015-04-14014 April 2015
April 9, 2015 Summary of Annual Assessment Meeting with Beaver Valley Power Station, Units 1 and 2
ML14325A7782014-12-16016 December 2014
October 6, 2014, Summary of Pre-Application Meeting with Firstenergy Nuclear Operating Company to Discuss Proposed Combination of Site Emergency Plans
ML14184B1962014-08-14014 August 2014
Summary of June 18, 2014, Closed Meeting Between Representatives of the U.S. Army Corps of Engineers, Nuclear Regulatory Commission, and Firstenergy Nuclear Operating Co. to Discuss Flooding Analysis Associated with Beaver Valley Power Stat
ML14160B1032014-07-10010 July 2014
June 6, 2014 Summary of Meeting with FENOC Flooding Hazard Reevaluation Extension Request for Beaver Valley Power Station, Units 1 and 2 and Flooding Hazard Reevaluation Report for Davis-Besse Nuclear Power Station, Unit 1
ML14142A0872014-06-0909 June 2014
Summary of Conference Call Regarding the Spring 2014 Steam Generator Inspections
ML14099A1732014-04-0909 April 2014
Annual Assessment Meeting Summary, ROP14
ML13295A2182013-10-22022 October 2013
Summary of Public Meeting with Beaver Valley,
ML13114A2072013-04-22022 April 2013
Summary of Annual Assessment Meeting at Beaver Valley
ML13057A6782013-03-11011 March 2013
2/20/2013 - Summary of Meeting with Firstenergy Nuclear Operating Company to Discuss Proposed Request for Additional Information Response Regarding Beaver Valley Power Station End-of-Life Moderator Temperature Coefficient Testing
ML12321A3012012-11-29029 November 2012
Summary of November 15, 2012, Meeting with Firstenergy Nuclear Operating Company to Discuss Upcoming License Amendment Request Relating to the Implementation of the Alternate Pressurized Thermal Shock Rule
ML12310A0662012-11-13013 November 2012
Summary of Conference Call with Firstenergy Nuclear Operating Company to Discuss 2012 Steam Generator Tube Inspections
ML12293A0402012-11-0101 November 2012
October 18, 2012 - Summary of Meeting with Firstenergy Nuclear Operating Company to Discuss Request for Additional Information Regarding Fenoc'S Extension Request for Upcoming Beaver Valley Power Station National Fire Protection Association
ML12277A4082012-10-0303 October 2012
September 26, 2012, Summary of Public Meeting to Discuss FENOC Fleet Performance
ML12223A4672012-08-22022 August 2012
August 1, 2012 - Summary of Meeting with FENOC to Discuss Upcoming National Fire Protection Association Standard 805 License Amendment Request Status
ML12195A1132012-07-16016 July 2012
Summary of Public Meeting with FENOC Regarding Licensing Practices and Processes
ML12104A1052012-04-13013 April 2012
Meeting Summary of Annual Assessment Meeting on March 22, 2012
ML1115805152011-06-15015 June 2011
(BVPS-2) - Summary of Conference Call Regarding the Spring 2011 Steam Generator Tube Inspection Results
ML1112504622011-05-0505 May 2011
Summary of Annual Assessment Open House Public Meeting, Beaver Valley
ML1035606612010-12-29029 December 2010
Summary of Beaver Valley Power Station, Unit 2 Public Conference Call Regarding Spent Fuel Pool Rerack LAR Draft RAI Responses Discussion
ML1027903512010-10-18018 October 2010
Summary of Meeting with Firstenergy Nuclear Operating Company, on the Request for Additional Resposnses Regarding the Spent Fuel Rerack for Beaver Valley Power Station, Unit No. 2
ML1014105172010-05-21021 May 2010
Summary of the May 2010 Annual Assessment Open-House Public Meeting
ML1013206652010-05-18018 May 2010
Summary of Category 1 Teleconference with Firstenergy Nuclear Operating Company to Discuss NRC Request for Additional Information Regarding Generic Letter 2004-02
ML1009502432010-04-0505 April 2010
Meeting Summary of 3-31-10 Public Meeting with FENOC
ML0931407282009-11-18018 November 2009
Steam Generator Tube Inspections
ML0909203872009-04-0202 April 2009
Summary of Annual Assessment Open-House Meeting Regarding the Safety Performance of the Beaver Valley Units 1 and 2
2023-06-28
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 May 18,2010 LICENSEE: FirstEnergy Nuclear Operating Company FACILITY: Beaver Valley Power Station, Unit Nos. 1 and 2
SUBJECT:
SUMMARY
OF APRIL 21,2010, CATEGORY 1 TELECONFERENCE WITH FIRSTENERGY NUCLEAR OPERATING COMPANY ON GENERIC LETTER 2004-02 (TAC NOS. MC4665 AND MC4666)
On April 21, 2010, a Category 1 public teleconference was held between the Nuclear Regulatory Commission (NRC) and representatives of FirstEnergy Nuclear Operating Company (the licensee). The purpose of the teleconference was to discuss the NRC staff's request for additional information (RAI) dated February 18, 2010 (ADAMS Accession No. ML100290318),
regarding Generic Letter 2004-02, "Potential Impact of Debris Blockage on Emergency Recirculation during Design Basis Accidents at Pressurized-Water Reactors," and agree on the licensee's draft RAI responses for Beaver Valley Power Station, Unit Nos. 1 and 2 (BVPS-1 and 2). Enclosed is a list of attendees.
The licensee provided draft RAI responses for the NRC staff to review. The NRC staff provided the licensee and its contractor detailed feedback on each response. The following table summarizes the discussion of each proposed response:
RAI Question NRC Staff Requested Action "Chemical Effects" 1. For BVPS-2, state that credit sought is temperature-based and that under all cases, full WCAP precipitate load is assumed present at 140 degrees Fahrenheit.
- 2. For BVPS-2, provide a reference in the final response to support the assertion on sodium aluminum silicate and briefly describe why Vogtle data is relevant to BVPS-2.
- 3. Delete the following sentence on page 96 of 109, in section "BVPS-1 ANL Correlation," "Using the ANL correlation approach to delaying the onset of chemical effects ensures it is unlikely that a full debris bed will be established within minutes following pump start." Instead, discuss physical phenomena that make precipitation unlikely. Argument should be based on elevated temperature. Add same reference and discussion regarding why Vogtle data applies to BVPS-2.
- 4. With changes agreed to as documented herein, the NRC staff finds this draft response regarding chemical effects and Appendix II appears satisfactory.
-2 RAI Question NRC Staff Requested Action 1 I" 1 and 2 None draft response appears satisfactory r 4 throuqh 19 Clarify that axial break of 11.25 inches is limiting break. With that change, draft response appears satisfactory.
None - draft response appears satisfactory
- 20. (a and c) None draft response appears satisfactory
- 20. b Add clarification on how any components assumed leak-tight were validated to be leak-tight.
- 21. (a, b, c, d, and f) None draft response appears satisfactory
- 21. e Add discussion of why miscellaneous debris would not affect result.
22 through 25 None draft response appears satisfactory The licensee agreed to revise and submit the draft responses to RAI questions 20.b and 21.e by April 30, 2010.
Please direct any inquiries to me at 301-415-1016, or Nadiyah.Morgan@nrc.gov.
Sincerely, r Nadiyah S. Morgan, Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-334 and 50-412
Enclosure:
List of Attendees cc w/encl: Distribution via Listserv
LIST OF PARTICIPANTS CATEGORY 1 PUBLIC TELECONFERENCE ON APRIL 21,2010 BETWEEN THE NUCLEAR REGULATORY COMMISSION (NRC)
AND FIRSTENERGY NUCLEAR OPERATING COMPANY (FENOC)
BEAVER VALLEY POWER STATION, UNIT NOS. 1 AND 2 DOCKET NOS. 50-334 AND 50-412 Name Organization Tom Lentz FENOC Mark Manoleras FENOC Carmen Mancuso FENOC Mike Testa FENOC Phil Lashley FENOC Ken McMullen FENOC Ann Ryan FENOC Kirk Troxler FENOC Vic Linnenbom FENOC Ken Frederick FENOC Jim Starr FENOC Tom Burns FENOC Steve Dristas FENOC Jay Crawford FENOC Dennis Blakely FENOC Megan Stahowiak Alion Science & Technology, Inc.
Todd Anselmi Alion Science & Technology, Inc.
Ralph Price Alion Science & Technology, Inc.
Greg Guliani Alion Science & Technology, Inc.
Max Ross Sargent & Lundy Michael Scott NRC Paul Klein NRC Stephen Smith NRC Matt Yoder NRC Nadiyah Morgan NRC Enclosure
PKG ML . ML100840756 Meeting Notice .
Meeting S urnrnar, ML101320665 OFFICE DORULPLI-1/PM DORULPLI-1/LA DORUSSIB/BC DORULPLI-1/BC DORULPLI-1/PM NAME NMorgan SLittie MScott NSalgado NMorgan DATE 5/13/10 5/13/10 5/17/10 5/18/10 5/18/10