Letter Sequence RAI |
|---|
TAC:ME4640, Steam Generator Tube Integrity (Approved, Closed) |
Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance, Acceptance
- Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement
Results
- Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval, Approval
Other: L-11-114, Drawing No. M-042B, Rev. 35, Sampling System Sh. 2 Local Grab Samples, L-11-131, Drawing No. LR-OS041A2, Revision 1, Operational Schematic Emergency Diesel Generator Systems, L-11-334, Reply to Request Additional Information for the Review of the License Renewal Application Amendment No. 21, L-12-337, Review of the Safety Evaluation Report with Open Items Related to the License Renewal, L-12-341, Firstenergy Nuclear Operating Cos Initial Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051), L-12-444, Submittal of Contractor Equivalent Margins Assessments for Reactor Vessel Welds (Nonproprietary Versions), L-12-456, Notification of Closure of Commitments Related to the Review of the License Renewal Application, L-13-257, Notification of Completion of a License Renewal Commitment Related to the Review of License Renewal Application TAC No. ME4640) and License Renewal Application Amendment No. 45), L-13-330, License Renewal Application Amendment No. 46 - Annual Update, L-13-341, Review of the Safety Evaluation Report Related to the License Renewal of Davis-Besse Nuclear Power Station, L-14-085, License Renewal Application (TAC No. ME4640) Amendment No. 48, L-14-206, License Renewal Application Amendment No. 50 - Annual Update, L-15-120, Notification of Completion of License Renewal Commitments Related to the Review of the Davis-Besse Nuclear Power Station, Unit No. 1, License Renewal Application and License Renewal Application Amendment No. 55, L-15-139, License Renewal Reactor Vessel Internals Inspection Plan, L-15-214, License Renewal Application Amendment No. 59 - Annual Update, L-15-309, License Renewal Application Amendment No. 60, L-15-310, C-CSS-099.20-069, Rev 0, Shield Building Laminar Cracking Limits, ML111050091, ML11110A089, ML11110A091, ML11110A092, ML11110A093, ML11110A094, ML11110A095, ML11110A105, ML11110A106, ML11110A107, ML11122A014, ML11126A017, ML11126A018, ML11126A019, ML11126A020, ML11126A021, ML11126A022, ML11126A023, ML11126A024, ML11126A025, ML11126A026, ML11126A032, ML11126A033, ML11126A034, ML11126A035, ML11126A036, ML11126A037, ML11126A038, ML11126A039, ML11126A040, ML11126A041, ML11126A042, ML11126A043... further results
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MONTHYEARML11126A0842003-01-22022 January 2003 Drawing No. LR-M039A, Revision 3, Piping & Instrument Diagram Miscellaneous Liquid Radioactive Waste. Job Code 12501 Project stage: Other ML11126A0762003-01-22022 January 2003 Drawing No. LR-M047, Revision 1, Piping & Instrument Diagram Radwaste Drumming Station Project stage: Other ML11126A0552003-08-12012 August 2003 Drawing No. LR-M030B, Revision 1, Reactor Coolant System Instrumentation Project stage: Other ML11126A0862005-08-23023 August 2005 Drawing No. LR-M040D, Revision 2, Piping & Instrument Diagram Reactor Coolant Pump & Motor. Job Code 12501 Project stage: Other ML11126A0882008-01-12012 January 2008 Drawing No. LR-M041B, Revision 1, Piping & Instrument Diagram Primary Service Water System. Job Code 12501 Project stage: Other ML11126A0902008-01-15015 January 2008 Drawing No. LR-OS41A1, Revision 1, Operational Schematic Emergency Diesel Generator Systems Project stage: Other L-11-131, Drawing No. LR-OS041A2, Revision 1, Operational Schematic Emergency Diesel Generator Systems2008-01-15015 January 2008 Drawing No. LR-OS041A2, Revision 1, Operational Schematic Emergency Diesel Generator Systems Project stage: Other ML11126A0682008-05-0505 May 2008 Drawing No. LR-M-037E, Revision 28, Piping & Instrument Diagram Clean Liquid Radioactive Waste System Project stage: Other ML11126A0652008-08-0606 August 2008 Drawing No. LR-M036B, Revision 1, Piping & Instrument Diagram Component Cooling Water System Project stage: Other ML11126A0592008-10-0909 October 2008 Drawing No. LR-M033A, Revision 1, Piping & Instrument Diagram High Pressure Injection Project stage: Other ML11126A0632008-10-10010 October 2008 Drawing No. LR-M033B, Revision 1, Piping & Instrument Diagram Decay Heat Train 1 Project stage: Other ML11126A0702008-10-10010 October 2008 Drawing No. LR-M033C, Revision 1, Piping & Instrument Diagram Decay Heat Train 2 Project stage: Other ML11126A0742008-11-0606 November 2008 Drawing No. LR-M043, Revision 1, Piping & Instrument Diagram Auxiliary Building Chilled Water System Project stage: Other ML11126A0832008-12-18018 December 2008 Drawing No. LR-M038C, Revision 2, Piping & Instrument Diagram Gaseous Radioactive Waste System. Job Code 12501 Project stage: Other ML11126A0712009-04-0707 April 2009 Drawing No. LR-M034, Revision 1, Piping & Instrument Diagram Emerg. Core Cooling System Ctmt. Spray & Core Flooding Systems Project stage: Other ML11126A0892009-04-0707 April 2009 Drawing No. LR-OS002, Revision 1, Operational Schematic Makeup and Purification System Project stage: Other ML1104500462011-02-17017 February 2011 Request for Additional Information for the Review of the Davis-Besse Nuclear Power Station - Fire Protection Project stage: RAI L-11-037, Independent Spent Fuel Storage Installation - Changes, Tests, and Experiments2011-02-17017 February 2011 Independent Spent Fuel Storage Installation - Changes, Tests, and Experiments Project stage: Request ML11126A0792011-02-25025 February 2011 Drawing No. LR-M900A, Revision 0, Instrument Air System Piping Schematic Project stage: Other ML1104205972011-02-28028 February 2011 Request for Additional Information for the Review of the Davis-Besse Nuclear Power Station - Section 2.4 Project stage: RAI ML1106801722011-03-17017 March 2011 Request for Additional Information on the Reactor Vessel Surveillance Aging Management Program, Time-Limited Aging Analyses for Neutron Embrittlement of the Rv and Internals, and Other TLAAs for the Review of the Davis-Besse Nuclear Power s Project stage: RAI L-11-078, Reply to Request for Additional Information for the Review of License Renewal Application (TAC ME4640) Amendment No. 12011-03-18018 March 2011 Reply to Request for Additional Information for the Review of License Renewal Application (TAC ME4640) Amendment No. 1 Project stage: Response to RAI ML1107007322011-03-18018 March 2011 Request for Additional Information for the Review of the Davis-Besse Nuclear Power Station-Section 2.2 & 2.3 Project stage: RAI ML11068A0002011-03-21021 March 2011 Request for Additional Information for the Review of the Davis-Besse Nuclear Power Station - Section 4.7 (TAC Number ME4640) Project stage: RAI L-11-079, Reply to Request for Additional Information for the Review of the License Renewal Application2011-03-23023 March 2011 Reply to Request for Additional Information for the Review of the License Renewal Application Project stage: Response to RAI L-11-089, Reply to Request for Additional Information for the Review License Renewal Application2011-03-23023 March 2011 Reply to Request for Additional Information for the Review License Renewal Application Project stage: Response to RAI ML1108206242011-03-30030 March 2011 Request for Additional Information for the Review of the Davis-Besse Nuclear Power Station-Section 2.1 (Tac No. ME4640) Project stage: RAI ML1109002952011-03-31031 March 2011 Safety Evaluation Report Related to the License Renewal of Salem Nuclear Generating Station Project stage: Approval ML1108204902011-04-0505 April 2011 Request for Additional Information for the Review of the Davis-Besse Nuclear Power Station - Batch 1 Project stage: RAI ML11110A0882011-04-15015 April 2011 Reply to Request for Additional Information for the Review of the License Renewal Application, Sections 2.2 & 2.3, License Renewal Application Amendment No. 3, and Revised License Renewal Project stage: Response to RAI L-11-107, Reply to Request for Additional Information on Reactor Vessel Surveillance Aging Management Program & Time-Limited Aging Analyses for Neutron Embrittlement for Review of License Renewal Application & License Renewal Application.2011-04-15015 April 2011 Reply to Request for Additional Information on Reactor Vessel Surveillance Aging Management Program & Time-Limited Aging Analyses for Neutron Embrittlement for Review of License Renewal Application & License Renewal Application. Project stage: Response to RAI L-11-114, Drawing No. M-042B, Rev. 35, Sampling System Sh. 2 Local Grab Samples2011-04-15015 April 2011 Drawing No. M-042B, Rev. 35, Sampling System Sh. 2 Local Grab Samples Project stage: Other ML11110A0892011-04-15015 April 2011 Drawing No. M-0060, Rev. 52, Auxiliary Feedwater System Project stage: Other ML11110A0912011-04-15015 April 2011 Drawing No. M-011, Rev. 61, Domestic Water System Project stage: Other ML11110A0922011-04-15015 April 2011 Drawing No. M-037C, Rev. 30, Clean Liquid Radioactive Waste System Project stage: Other ML11110A0932011-04-15015 April 2011 Drawing No. M-037D, Rev. 21, Clean Liquid Radioactive Waste System Project stage: Other ML11110A0942011-04-15015 April 2011 Drawing No. M-039A, Rev. 33, Miscellaneous Liquid Radioactive Waste Project stage: Other ML11110A0952011-04-15015 April 2011 Drawing No. M-039B, Rev. 18, Miscellaneous Liquid Radioactive Waste Project stage: Other ML11110A1052011-04-15015 April 2011 Drawing No. M-040A, Rev. 76, Reactor Coolant System Details Project stage: Other ML11110A1062011-04-15015 April 2011 Drawing No. M-042C, Rev. 33, Sampling System Sh. 3 Project stage: Other ML11110A1072011-04-15015 April 2011 Drawing No. M-045, Rev. 56, Chemical Addition Systems Project stage: Other ML1110500912011-04-19019 April 2011 Scoping and Screening Audit Report Regarding the Davis-Besse Nuclear Power Station License Renewal Application Project stage: Other ML1109807182011-04-20020 April 2011 Request for Additional Information for the Review of the Davis-Bessie Nuclear Power Station - Batch 2 Project stage: RAI L-11-115, Reply to Request for Additional Information for the Review of the License Renewal Application and License Renewal Application Amendment No. 42011-04-20020 April 2011 Reply to Request for Additional Information for the Review of the License Renewal Application and License Renewal Application Amendment No. 4 Project stage: Response to RAI ML11126A0342011-04-29029 April 2011 Drawing No. LR-M017B, Revision 1, Piping & Instrument Diagram, Diesel Generators Air Start Project stage: Other ML11126A0172011-04-29029 April 2011 Drawing No. LR-M006E, Revision 1, Piping & Instrument Diagram Condensate System Project stage: Other ML11126A0182011-04-29029 April 2011 Drawing No. LR-M007A, Revision 1, Piping & Instrument Diagram Steam Generator Secondary System Project stage: Other ML11126A0192011-04-29029 April 2011 Drawing No. LR-M003A, Revision 1, Piping & Instrument Diagram Main Steam and Reheat System. Sheet 1 Project stage: Other ML11126A0202011-04-29029 April 2011 Drawing No. LR-M003B, Revision 1, Piping & Instrument Diagram Main Steam and Reheat System. Sheet 2 Project stage: Other ML11126A0212011-04-29029 April 2011 Drawing No. LR-M003C, Revision 2, Piping & Instrument Diagram Main Steam and Reheat System. Sheet 3 Project stage: Other 2011-02-17
[Table View] |
Text
\\.~,..R IlEGu, UNITED STATES
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NUCLEAR REGULATORY COMMISSION J::
WASHINGTON, D.C. 20555-0001 0
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ff July 9, 2013
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LICENSEE:
FirstEnergy Nuclear Operating Company FACILITY:
Davis-Besse Nuclear Power Station
SUBJECT:
SUMMARY
OF TELEPHONE CONFERENCE CALL HELD ON MAY 9,2013, BElWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND FIRSTENERGY NUCLEAR OPERATING COMPANY, CONCERNING REQUESTS FOR ADDITIONAL INFORMATION PERTAINING TO THE DAVIS-BESSE NUCLEAR POWER STATION, LICENSE RENEWAL APPLICATION (TAC. NO. ME4640)
The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of FirstEnergy Nuclear Operating Company (FENOC or the applicant) held a telephone conference call on May 9, 2013, to discuss and clarify the staff's requests for additional information (RAls) concerning the Davis-Besse Nuclear Power Station license renewal application. provides a listing of the participants and Enclosure 2 contains a summary of the staff discussion with FENOC. A brief description on the status of the items is also included.
FENOC had an opportunity to comment on this summary.
Sincerely,
~
tJ/jJ~
ue Cuadrado de Jesl.Js, p"t Manager Projects Branch 1 Division of License Renewal Office of Nuclear Reactor Regulation Docket No. 50-346
Enclosures:
- 1. List of Participants
- 2. List of Requests for Additional Information cc w/encls: Listserv
'ML13149A288 OFFICE LA: DLRIRPB 1 PM:RPB1 :DLR BC:RPB1 :DLR NAME YEdmonds SCuadrado de Jesus YDiaz DATE 6/20/13 7/18/13 7/9113
SUMMARY
OF TELEPHONE CONFERENCE CALL DAVIS-BESSE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION LIST OF PARTICIPANTS May 9,2013 PARTICIPANTS AFFILIATIONS IIAI C'!11::Irlr::lrlo de Jesus U.S. Nuclear ReQulatorv Commission (NRC)
I NRC Brvce Lehman NRC Cliff Custer FirstEnerQV Nuclear OoeratinQ Company (FENOC)
Steven Dort FENOC E. David Baker FENOC Thomas Henrv FENOC DOUQ Noble FENOC Jeff Bobetich FENOC Ned Campbell FENOC ENCLOSURE 1
SUMMARY
OF TELEPHONE CONFERENCE CALL DAVIS-BESSE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION May 9,2013 The U.S. Nuclear Regulatory Commission (NRC or the staff) and representatives of FirstEnergy Nuclear Operating Company (FENOC or the applicant) held a telephone conference call on May 9, 2013, to discuss and clarify the following requests for additional information (RAls) concerning the Davis-Besse license renewal application (LRA).
Response to RAI 8.2.22-6 dated August 26,2011 Discussion: The purpose of the call was to discuss FENOC's response to NRC request for additional information (RAI) B.2.22-6 provided by letter dated August 26, 2011, regarding the location of a proposed core bore in the concrete floor of the containment vessel described in License Renewal Commitment No. 39, and FENOC's intent to relocate that core bore, as follows:
In the response to RAI B.2.22-6, FENOC stated the following:
FENOC plans to locate the core bore below the reactor vessel where the Incore Tunnel opens through the primary shield wall into the area below the reactor vessel. That location is about 18 feet from the containment vessel centerline.
The lowest point of the containment vessel is about 30 inches lower than the elevation of the containment bottom head at the core bore location. The Incore Tunnel location was chosen because of the boron deposits that have been found in the Incore Tunnel.
FENOC stated that, during the research and planning process to perform the originally proposed core bore (location 1) in the next plant outage (Spring 2014), several concerns were identified that resulted in a change in the core bore location (location 2). FENOC described the differences between the two core bore locations as follows:
- Location 2 is in the access hallway to the containment normal sump and provides better radiation shielding, which would significantly reduce the dose received by workers.
Additional dose savings would be achieved during project execution since access to location 2 is much easier than the high dose rate path to location 1. The potential dose savings supports as low as is reasonably achievable (ALARA) dose reduction principles.
- Location 2 is closer to the centerline of the containment vessel than location 1. Location 2 is along the containment vessel east-west centerline and approximately 8 feet east of the vessel north-south centerline, and would allow examination of the deeper portion of the containment vessel (about 12 inches vertical height above bottom dead center) compared to Location 1 (about 30 inches vertical height above bottom dead center).
This new location addresses a concern about examining the containment vessel at the deepest portion where borated water may pond. This concern was raised by the ENCLOSURE 2
- 2 advisory Committee for Reactor Safeguards (ACRS) License Renewal Subcommittee during the meeting with FENOC held on September 19, 2012.
The staff stated that FENOC should provide its basis to relocate the core bore in a supplemental response to RAI B.2.22-6.
FENOC stated that it would submit a supplemental response to RAI B.2.22-6 to describe and justify the proposed new core bore location, and revise license renewal Commitment No. 39 to include the containment vessel examination height above bottom dead center based on the new location.
There was no further discussion, and the call was concluded.
Action: FENOC will provide a supplemental response to RAI 8.2.22-6
SUBJECT:
SUMMARY
OF TELEPHONE CONFERENCE CALL CONDUCTED ON MAY 9,2013.
DISTRIBUTION:
HARDCOPY:
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PUBLIC RidsNrrDlr Resource RidsNrrDlrRpb1 Resource RidsNrrDlrRpb2 Resource RidsNrrDlrRarb Resource RidsNrrDlrRapb Resource RidsNrrDlrRasb Resource RidsNrrDlrRerb Resource RidsNrrDlrRpob Resource SCuadrado EKeegan EMilier MMahoney DMclntyre,OPA TRiley,OCA BHarris, OGC