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
REGU~
UNITED STATES
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NUCLEAR REGULATORY COMMISSION g
WASHINGTON, D.C. 20555*0001 ii:
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April 2, 2012
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LICENSEE:
FirstEnergy Nuclear Operating Company FACILITY:
Davis-Besse Nuclear Power Station
SUBJECT:
SUMMARY
OF TELEPHONE CONFERENCE CALL HELD ON FEBRUARY 9,2012, BETWEEN 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 February 9, 2012, to discuss and clarify the staff's concerns related to the Davis-Besse license renewal application. provides a listing of the participants and Enclosure 2 contains a description of the staff concerns discussed with the applicant. A brief description on the status of the Items is also included.
The appiicant had an opportunity to comment on this summary.
ue cuad~~~Manager rojects 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
SUMMARY
OF TELEPHONE CONFERENCE CALL DAVIS-BESSE LICENSE RENEWAL APPLICATION LIST OF PARTICIPANTS February 9, 2012 PARTICIPANTS AFFILIATIONS Samuel Cuadrado de Jesus U.S. Nuclear Regulatory Commission (NRC)
Allen Hiser NRC Christopher Sydnor NRC Cliff Custer FirstEnergy Nuclear Operating Company (FENOC)
Larry Hinkle FENOC Allen McAllister FENOC Dennis Blakely FENOC John Hartigan FENOC Mark Rinckel FENOC ENCLOSURE 1
SUMMARY
OF TELEPHONE CONFERENCE CALL DAVIS-BESSE LICENSE RENEWAL APPLICATION February 9,2012 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 February 9,2012, to discuss and clarify the following concerns related to the Davis-Besse license renewal application (LRA).
LRA Section 4.2.1 Neutron Fluence Discussion:
The staff noted that in LRA Section 4.2.1 neutron fluence is dis positioned as "not a TLAA." The staff stated that it's position is that neutron fluence is a time-limited aging analysis (TLAA).
The applicant stated that it will change the LRA to disposition the neutron fluence evaluation as a TLAA using 10 CFR 54.21 (c)(1)(ii).
Action: The applicant will update the LRA to disposition neutron fluence as a TLAA.
LRA Section 4.2.2 Upper Shelf Energy (USE)
Discussion:
The staffs position is that the Upper Shelf Energy (USE) evaluation for the Linde 80 welds should be based on a more conservative value than the average of 70 ft-Ib (mean value with a standard deviation of 5.6, minimum value of 64 ft-Ib and maximum value of 81 ft-Ib) unirradiated USE.
The applicant agreed to reevaluate the Linde 80 welds using an unirradiated USE value less than 70 ft-Ib or provide a basis to use an unirradiated value of 70 ft-Ib. The applicant will revise LRA Section A.2.2.2 accordingly. In addition the applicant agreed to revise LRA Section A.2.2.2 for consistency with the previously provided response to the staffs request for additional information (RAI) 4.2.2-2.
Action: The applicant will reevaluate the Linde 80 welds and revise LRA Section A.2.2.2 accordingly.
ENCLOSURE 2
- 2 Section 4.2.4 Pressure-Temperature Limits Discussion:
The staff stated that it needed clarification on how the fluence values were obtained at 1/4T and 3/4T for the reactor vessel (RV) nozzles and associated welds.
The applicant provided an explanation of the fluence evaluation methodology for the subject location and that this methodology included adding the attenuation from both the inside and outside surfaces.
After some discussion, the staff indicated that it will need to review this issue further to understand the methodology on the use of inner and outer surfaces fluence to project the 52 effective full power years (EFPY) adjusted reference temperature (ART) value for this location.
Section 4.2.6 Intergranular Separation (Underclad Cracking)
Discussion:
The staff asked the applicant if it has plans to update the updated safety analysis report Supplement (LRA Section A) in order to reflect their recent RV head replacement.
The applicant stated that it will change the LRA (Sections A.2.2.6, 4.2.6 and 8.2.29) to acknowledge that the RV head was replaced in the fall of 2011.
Action: The applicant will revise the LRA.
Section 4.3.2.2.2 Reactor Vessel Internals (RVI) Low-Cycle Fatigue Discussion:
The staff wanted to know if an aging effect of cracking due to fatigue was identified and managed in the LRA for the RVI Alloy A-286 original bolts.
The applicant responded that for the replacement RVI Alloy X-750 HTH bolts, aging management review (AMR) rows are provided in the LRA (Table 3.1.2-2) for cumulative fatigue damagelTLAA. However, for the RVI Alloy X-750 HTH replacement bolts and for the RVI Alloy A-286 original bolts, AMR rows are not provided for the aging effect of cracking due to fatigue.
The applicant noted that this approach is consistent with the industry guidance in MRP-227-A and the associated safety evaluation where, for the subject bolts, cracking due to fatigue is not shown as an aging effect requiring management.
-3 The staff indicated that it will review this issue and may need further discussion with the applicant at a later time.
There was no further discussion, and the call was concluded.
SUBJECT:
Summary of Telephone Conference Call conducted on February 9, 2012 DISTRIBUTION:
HARD COPY:
DLRRF E-MAIL:
PUBLIC [or NON-PUBLIC, if applicable]
RidsNrrDlr Resource RidsNrrDlrRpb1 Resource RidsNrrDlrRpb2 Resource RidsNrrDlrRarb Resource RidsNrrDlrRapb Resource RidsNrrDlrRasb Resource RidsNrrDlrRerb Resource RidsNrrDlrRpob Resource PCooper BHarris SCuadrado EMilier MMahoney DMclntyre, OPA TRiley,OCA BHarris, OGC
LICENSEE:
FirstEnergy Nuclear Operating Company FACILITY:
Davis-Besse Nuclear Power Station
SUBJECT:
SUMMARY
OF TELEPHONE CONFERENCE CALL HELD ON FEBRUARY 9,2012 BETWEEN 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 February 9, 2012, to discuss and clarify the staff's concerns related to the Davis-Besse license renewal application. provides a listing of the participants and Enclosure 2 contains a description of the staff concerns discussed with the applicant. A brief description on the status of the items is also included.
The applicant had an opportunity to comment on this summary.
IRAJ Samuel Cuadrado de Jeas, Project 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 DISTRIBUTION: See next page ADAMS Accession No. ML12059a078 OFFICE LA:RPB1:DLR PM:RPB1 :DLR BC:RPB1 :DLR NAME YEdmonds SCuadrado de Jeas DMorey DATE 02 /29/12 03/07/12 04/2/12 OFFICIAL RECORD COpy