Letter Sequence RAI |
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Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance...
- Supplement, Supplement, Supplement, Supplement, Supplement
Results
Other: L-09-056, Downstream Effects for Recirculation Spray System Pumps and Low Head Safety Injection System Pumps, L-13-176, Generic Safety Issue 191 Resolution Plan, ML061380273, ML080220343, ML081230116, ML082740241, ML090750619, ML090900193, ML091050100, ML091240030
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MONTHYEARL-05-034, Response to GL-04-002, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors.2005-03-0404 March 2005
Response to GL-04-002, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors.
Project stage: Request
ML0515302672005-06-0303 June 2005
6/3/05, Beaver Valley, RAI, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-Water Reactors
Project stage: RAI
ML0520801672005-07-22022 July 2005
Response to Request for Additional Information on Generic Letter 2004-02
Project stage: Response to 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
L-05-151, August 24, 2005 Extended Power Uprate Meeting Presentation Material2005-09-0101 September 2005
August 24, 2005 Extended Power Uprate Meeting Presentation Material
Project stage: Request
L-05-140, Response to a Request for Additional Information (RAI Dtd August 2, 2005) in Support of License Amendment Request Nos. 302 and 173, Extended Power Uprate2005-09-0606 September 2005
Response to a Request for Additional Information (RAI Dtd August 2, 2005) in Support of License Amendment Request Nos. 302 and 173, Extended Power Uprate
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
ML0609604422006-04-0303 April 2006
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: Request
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
ML0731005762007-11-0808 November 2007
Notice of Meeting to Discuss the Safety Review Process and Environmental Scoping Process for Beaver Valley Power Station, Units 1 and 2, License Renewal Application Review
Project stage: Meeting
ML0802203432008-01-14014 January 2008
Letter from George Dudash III, Comment Regarding the Beaver Valley Power Station Unit 1 and 2 License Renewal
Project stage: Other
ML0805102462008-02-14014 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-08-054, 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
ML0806605972008-02-29029 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
ML0807301162008-03-21021 March 2008
Summary of Conference Call Between Us Nuclear Regulatory Commission and Firstenergy Nuclear Operating Company, Concerning the Impact of Table 8.0-1 Error on the Beaver Valley Severe Accident Mitigation Alternatives Request for Additional in
Project stage: Request
ML0807403922008-03-26026 March 2008
Summary of Telephone Conference Between NRC and Firstenergy Nuclear Operating Company, Concerning Clarification of Severe Accident Mitigation Alternatives Request for Additional Information Pertaining to Beaver Valley Units 1 & 2
Project stage: RAI
ML0812304992008-06-0303 June 2008
Teleconf Held 4/30/08 Between NRC and Firstenergy Concerning the RAI Pertaining to the Refurbishment Activities at Beaver, Units 1 and 2, LRA
Project stage: Request
ML0824800452008-08-28028 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
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
ML0826001472008-09-30030 September 2008
NUREG-1437 Supp 36, Dfc, Generic Environmental Impact Statement for License Renewal of Nuclear Plants: Regarding Beaver Valley Power Station, Units 1 & 2 (Draft for Comment)
Project stage: Draft Other
ML0830800942008-10-29029 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-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
ML0907506192009-03-11011 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
ML0912501802009-04-30030 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
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 Reactors2009-06-30030 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 Staffs 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
2008-03-21
[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
Clarify that axial break of 11.25 inches is limiting break. With that change, draft response appears satisfactory.
4 throuqh 19 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 Meeting Notice 4
Meeting
- urnrnar, 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