Letter Sequence RAI |
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TAC:ME4640, Steam Generator Tube Integrity (Approved, Closed) |
Results
- 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-12-444, 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., ML102450565, 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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MONTHYEARML11126A0882008-01-12012 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 Systems.2008-01-15015 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 ML1024505652010-08-27027 August 2010 License Renewal Application and Ohio Coastal Management Program Consistency Certification 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 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 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 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 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 ML11110A0932011-04-15015 April 2011 Drawing No. M-037D, Rev. 21, Clean Liquid Radioactive Waste System Project stage: Other ML11110A1072011-04-15015 April 2011 Drawing No. M-045, Rev. 56, Chemical Addition Systems Project stage: Other ML11110A1062011-04-15015 April 2011 Drawing No. M-042C, Rev. 33, Sampling System Sh. 3 Project stage: Other ML11110A1052011-04-15015 April 2011 Drawing No. M-040A, Rev. 76, Reactor Coolant System Details Project stage: Other ML11110A0952011-04-15015 April 2011 Drawing No. M-039B, Rev. 18, Miscellaneous Liquid Radioactive Waste Project stage: Other ML11110A0942011-04-15015 April 2011 Drawing No. M-039A, Rev. 33, Miscellaneous Liquid Radioactive Waste Project stage: Other ML11110A0922011-04-15015 April 2011 Drawing No. M-037C, Rev. 30, Clean Liquid Radioactive Waste System Project stage: Other 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 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 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 ML11110A0912011-04-15015 April 2011 Drawing No. M-011, Rev. 61, Domestic Water System Project stage: Other ML11110A0892011-04-15015 April 2011 Drawing No. M-0060, Rev. 52, Auxiliary Feedwater System 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 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 ML1109807182011-04-20020 April 2011 Request for Additional Information for the Review of the Davis-Bessie Nuclear Power Station - Batch 2 Project stage: RAI ML11126A0362011-04-29029 April 2011 Drawing No. LR-M017D, Revision 1 Piping & Instrument Diagram, Steam Blackout Diesel Generator. Project stage: Other ML11126A0352011-04-29029 April 2011 Drawing No. LR-M017C, Revision 2, Piping & Instrument Diagram, Fuel Oil. Project stage: Other ML11126A0342011-04-29029 April 2011 Drawing No. LR-M017B, Revision 1, Piping & Instrument Diagram, Diesel Generators Air Start. Project stage: Other ML11126A0332011-04-29029 April 2011 Drawing No. LR-M016B, Revision 1, Piping & Instrument Diagram Station Fire Protection System Project stage: Other ML11126A0322011-04-29029 April 2011 Drawing No. LR-M016A, Revision 1, Piping & Instrument Diagram Station Fire Protection System Project stage: Other ML11126A0262011-04-29029 April 2011 Drawing No. LR-M010C, Revision 1, Piping & Instrument Diagram Make-up Water Treatment System Project stage: Other ML11126A0252011-04-29029 April 2011 Drawing No. LR-M010A, Revision 1, Piping & Instrument Diagram Make-Up Water Treatment System Project stage: Other ML11126A0242011-04-29029 April 2011 Drawing No. LR-M009B, Revision 1, Piping & Instrument Diagram Cooling Water 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 ML11126A0452011-04-29029 April 2011 Drawing No. LR-M024H, Revision 1, Piping & Instrument Diagram, No. 2 Main and Auxiliary Turbine Driven Feed Pumps. Project stage: Other 2011-02-25
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Category:Meeting Summary
MONTHYEARML23152A2552023-06-0505 June 2023 Summary of the May 17, 2023, Public Outreach to Discuss the NRC 2022 End-of-Cycle Plant Performance Assessment of Davis-Besse Nuclear Power Station ML22178A2312022-06-28028 June 2022 Summary of the June 22, 2022, Public Outreach to Discuss the NRC 2021 End-Of-Cycle Plant Performance Assessment of Davis Besse Nuclear Power Station ML22088A1972022-03-30030 March 2022 Summary of March 11, 2022, Call Regarding the Spring 2022 Steam Generator Tube Inspections ML22084A1022022-03-27027 March 2022 Reissue Summary of the February 1, 2022, Regulatory Conference Between Energy Harbor, Davis-Besse Nuclear Power Station and the Nuclear Regulatory Commission ML22077A8062022-03-23023 March 2022 Summary of the February 1, 2022, Regulatory Conference Between Energy Harbor, Davis-Besse Nuclear Power Station and the Nuclear Regulatory Commission ML21314A5362021-11-18018 November 2021 Summary of November 8, 2021, Meeting with Energy Harbor Nuclear Corp. Regarding Its Proposed Alternate for Examination of Steam Generator Welds at ML21180A4632021-06-29029 June 2021 Summary of the June 22, 2021, Public Outreach to Discuss the NRC 2020 End-of-Cycle Plant Performance Assessment of Davis-Besse Nuclear Power Station, and Perry Nuclear Power Plant ML20240A2942020-08-27027 August 2020 July 23, 2020 Summary of Public Webinar to Discuss the Nrc 2019 End-Of-Cycle Plant Performance Assessment of the Davis-Besse Nuclear Power Station and the Perry Nuclear Power Plant ML19249C7112019-09-0404 September 2019 Summary of the July 18, 2019 Public Outreach/Open House to Discuss the NRC 2018 End-Of-Cycle Plant Performance Assessment of the Davis-Besse Nuclear Power Station ML18313A1982018-11-14014 November 2018 Summary of Meeting with Firstenergy Nuclear Operating Company Regarding Planned Submittal of Post-Shutdown Emergency Plan for Davis-Besse Nuclear Power Station ML18192A6522018-07-10010 July 2018 Summary of Public Meeting to Discuss the 2017 End-of-Cycle Plant Performance Assessment of Davis-Besse Nuclear Power Station ML17258A1462017-09-20020 September 2017 Summary of September 12, 2017, Meeting with Firstenergy Nuclear Operating Company Regarding Its Licensing Amendment Request to Adopt National Fire Protection Association Standard 805 at Davis-Besse Nuclear Power Station, Unit No. 1 ML17229B1362017-08-16016 August 2017 Summary of July 19, 2017, Open House to Discuss the 2016 End-of-Cycle Plant Performance Assessment of Davis-Besse Nuclear Power Station ML17087A1882017-03-28028 March 2017 Summary of Closed Meeting with Firstenergy Nuclear Operating Company Regarding Changes to the Davis-Besse Nuclear Power Station, Unit No. 1, Security Plan ML16197A0522016-07-14014 July 2016 Summary of June 21, 2016, Public Meeting with Firstenergy Nuclear Operating Company to Discuss the 2015 End-of-Cycle Plant Performance Assessment of Davis-Besse Nuclear Station ML16130A7502016-05-12012 May 2016 Summary of April 12, 2016, Teleconference Regarding Steam Generator Tube Inservice Inspection ML14177A5782016-02-22022 February 2016 November 13, 2013, Summary of Meeting with Firstenergy Nuclear Operating Company to Discuss Delay in Submittal of Fire Risk Reduction Amendment Request ML16006A3512016-01-20020 January 2016 December 17,2015 Summary of Meeting with Firstenergy Nuclear Operating Company on Its License Amendment Request to Revise the Emergency Diesel Generator Surveillance Requirements at Davis-Besse Nuclear Power Station, Unit 1 ML16007A3962016-01-12012 January 2016 Summary of January 5, 2016, Meeting with Firstenergy Nuclear Operating Company on Its Planned License Amendment Request to Revise the Emergency Action Level Scheme at Davis-Besse Nuclear Power Station, Unit No. 1 ML15196A5162015-07-24024 July 2015 Summary of Telephone Conference Call Held on May 06, 2015, and May 19, 2015 Between the U.S. Nuclear Regulatory Commission and Firstenergy Nuclear Operating Company ML15170A2862015-06-18018 June 2015 Summary of the Public Open House Regarding Davis-Besse Nuclear Power Station ML15089A1642015-04-27027 April 2015 Summary of February 25, 2015, Partially Closed Meeting with Industry Stakeholders Regarding the Babcock and Wilcox Loss of Coolant Accident Evaluation Model Analysis ML15056A4562015-04-20020 April 2015 Summary of Teleconference Call Held February 20, 2015, Between U.S. Nuclear Regulatory Commission and First Energy Nuclear Operating Company, Concerning Requests for Additional Information Pertaining to the Davis-Besse Nuclear Power Station 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 ML14224A6142014-08-12012 August 2014 Summary of Public Meeting to Discuss the 2013 Performance of Davis-Besse Nuclear Power Station 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 ML14099A4642014-05-0606 May 2014 Summary of Public Meetings to Discuss Draft Supplement 52 to the Generic Environmental Impact Statement for License Renewal of Nuclear Plants Regarding Davis-Besse Nuclear Generating Station, Unit 1 ML14099A3392014-04-22022 April 2014 March 27, 2014, Summary of Telephone Conference Call Held Between Nuclear Regulatory Commission and First Energy Nuclear Operating Company Concerning Commitment 13 of the Safety Evaluation Report Pertaining to the Davis Besse Unit 1, Licens ML14080A1842014-03-21021 March 2014 Summary of Webinar Meeting to Discuss NRC Inspection Activities Associated with the Davis-Besse Nuclear Power Station Installation of Two New Steam Generators ML13240A0702013-08-29029 August 2013 8 22 2013 DB NRC Telecon Summary License Condition ML13225A2932013-08-12012 August 2013 7/23-24/2013, Summary of Meeting 2013 U.S. Nuclear Regulatory Commission (NRC) Initial Exam Writers' Workshop ML13197A2572013-07-17017 July 2013 5 28 2013 DB Hs Bolts Telecon Summary ML13182A4082013-07-17017 July 2013 Summary of Telephone Conference Call Held on October 16, 2012, Between NRC and FENOC, Concerning RAI Pertaining to the Davis-Besse Nuclear Power Station, LRA (TAC No. ME640) ML13149A2862013-07-12012 July 2013 Summary of Telephone Conference Call Held on May 2, 2013, Between the NRC and FENOC, Concerning RAI Pertaining to the Davis-Besse Nuclear Power Station License Renewal Application ML13182A4432013-07-12012 July 2013 Summary of Telephone Conference Call Held on April 11, 2013, Between the U.S. Nuclear Regulatory Commission and Firstenergy Nuclear Operating Company, Concerning Requests for Additional Information Pertaining to the Davis-Besse Nuclear Powe ML13149A2882013-07-0909 July 2013 May 9, 2013, Summary of Telephone Conference Call Held Between the U.S. Nuclear Regulatory Commission and Firstenergy Nuclear Operating Company, Concerning Requests for Additional Information Pertaining to the Davis-Besse Nuclear Power Stat ML13168A2422013-06-14014 June 2013 6/11/2013 - Summary of Open House to Discuss the 2012 Davis-Besse Nuclear Power Station End-Of-Cycle Performance ML13091A3272013-03-29029 March 2013 Summary of Public Meeting to Discuss the Davis-Besse Replacement Activities ML13051A6602013-03-26026 March 2013 Summary of Telephone Conference Call Held on January 23, 2013, Between the NRC and FENOC, Concerning RAI Pertaining to the Davis-Besse Nuclear Power Station, LRA ML13051A0682013-03-26026 March 2013 January 16, 2013 Summary of Telephone Conference Call Held Between U.S. Nuclear Regulatory Commission and Firstenergy Nuclear Operating Company ML13025A0272013-02-14014 February 2013 October 23, 2012 Summary of Telephone Conference Call Held Between the Nuclear Regulatory and Firstenergy Nuclear Operating Company, Concerning Requests for Additional Information Pertaining to the Davis-Besse Nuclear Power Station, License ML12277A4082012-10-0303 October 2012 September 26, 2012, Summary of Public Meeting to Discuss FENOC Fleet Performance ML12243A2832012-08-30030 August 2012 Summary of Public Meeting to Discuss Nrc'S Review of Fenoc'S Root Cause Analysis of Davis-Besse Shield Building Cracks ML12237A0432012-08-24024 August 2012 August 15, 2012 - Summary of Public Meeting to Discuss the Davis-Besse Nuclear Power Station, Unit 1, End-Of-Cycle Plant Performance Assessment ML12195A1132012-07-16016 July 2012 Summary of Public Meeting with FENOC Regarding Licensing Practices and Processes ML12165A3502012-07-16016 July 2012 Summary of Conference Call for Stream Generator Tube Inservice Inspections for Spring 2012 Refueling Outage ML12052A1792012-05-15015 May 2012 July 19, 2011, Summary of Telephone Conference Call 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 ML12059A0782012-04-0202 April 2012 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 Pow ML12061A2582012-04-0202 April 2012 Summary of Telephone Conference Call Held on July 12,2011, Between the U.S. Nuclear Regulatory Commission and Firstenergy Nuclear Operating Company, Concerning Requests for Additional Information Pertaining to the Davis-Besse Nuclear Power ML12031A1832012-03-0202 March 2012 Summary of Telephone Conference Call Held on July 13, 2011, Between the U.S. Nuclear Regulatory Commission and Firstentergy Nuclear Operating Company, Concerning Request for Additional Information Pertaining to the DA7 13 2011 DB NRC Teleco 2023-06-05
[Table view] Category:Conference/Symposium/Workshop Paper
MONTHYEARML16130A7502016-05-12012 May 2016 Summary of April 12, 2016, Teleconference Regarding Steam Generator Tube Inservice Inspection ML13051A0682013-03-26026 March 2013 January 16, 2013 Summary of Telephone Conference Call Held Between U.S. Nuclear Regulatory Commission and Firstenergy Nuclear Operating Company ML12052A1792012-05-15015 May 2012 July 19, 2011, Summary of Telephone Conference Call 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 ML12018A1462012-02-0909 February 2012 June 16, 2011, Summary of Telephone Conference Call Held Between the NRC and Firstenergy Nuclear Operating Company, Concerning RAI Pertaining to the Davis-Besse, License Renewal Application ML11364A0172012-01-19019 January 2012 Summary of Telephone Conference Call 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, LRA ML0804306122008-03-0505 March 2008 Summary of Conference Telephone Call Regarding Their 2008 Steam Generator Tube Inspections ML0618002632006-09-18018 September 2006 Crack Growth Rates in a PWR Environment of Nickel-Base Alloys from Davis-Besse and V. C. Summer Plants ML0526600162005-08-16016 August 2005 Mantg Conference, 8/16/05 - Plenary - Keynote Speech by Samuel J. Collins, Regional Administrator, Region I, the Changing Roles of the Operators and Trainers 2016-05-12
[Table view] |
Text
~f>.1'\ REGu{ UNITED STATES
"'~vv\,; '1>>0'1>..<. NUCLEAR REGULATORY COMMISSION
~ Cl WASHINGTON, D.C. 20555-0001
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~ i February 9, 2012
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"'", 0' LICENSEE' FirstEnergy Nuclear Operating Company FACILITY: Davis-Besse Nuclear Power Station SUBJECT
SUMMARY
OF TELEPHONE CONFERENCE CALL HELD ON JUNE 16,2011, 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 (FENOe or the applicant) held a telephone conference call on June 16, 2011, to discuss and clarify the staff's concerns related to the Davis-Besse Nuclear Power Station license renewal application.
Enclosure 1 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.
Docket No. 50-346 Enclosures' As stated cc w/encls: Listserv
SUMMARY
OF TELEPHONE CONFERENCE CALL DAVIS-BESSE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION LIST OF PARTICIPANTS June 16, 2011 PARTICIPANTS AFFILIATIONS Samuel Cuadrado de Jesus U.S. Nuclear Regulatory Commission (NRC)
James Medoff NRC Steve Dort FirstEnergy Nuclear Operating Company (FENOC)
Kathy Nesser FENOC John Hartigan FENOC Larry Hinkle FENOC ENCLOSURE 1
SUMMARY
OF TELEPHONE CONFERENCE CALL DAVIS-BESSE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION June 16, 2011 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 June 16, 2011, to discuss and clarify the following concerns related to the Davis-Besse Nuclear Power Station (Davis-Besse) license renewal application (LRA).
Discuss absence of a time-limited againg analysis (TLAA) on their bases for non-Class 1!
non-piping components Discussion:
The staff requested the applicant to explain the absence of a TLAA on their bases for non-Class 1, non-piping components.
The applicant responded by explaining that non-Class 1 components reanalyzed as Class 1 components are addressed under the Class 1 Section of the LRA.
The staff understood the applicant's explanation and stated that no request for additional information (RAI) is necessary.
RAI4.1-2 Discussion:
The staff requested the applicant to discuss extension of the scope of RAI 4.1-2 to both the time-dependent J-integral analysis and the time-dependent fatigue flaw growth analysis in Structural Integrity Associates (SIA) Topical Report No. SIR-99-040, Revision 1, "ASME Code Case N-481 of Davis-Besse Reactor Coolant Pumps" (ADAMS Accession No. ML011200090).
The staff stated that the scope of the RAI, as issued, only talked about the fatigue flaw growth analysis in the report, which forms the basis for applying VT-1 or EVT-1 visual examinations of the outside surfaces of the reactor coolant pump (RCP) casing welds in lieu of the ultrasonic test (UT) examinations that would be required by the ASME Section XI Code of Record. The staff also stated that there is a possibility, that 10 CFR SO.SSa may require the applicant to update to a more recent edition of the ASME Section XI Code that has incorporated the visual examinations requirements for the pump casings. If this is the case, the staff stated that it will need to know whether the applicant's current licensing basis (CLB) is still relying on the SIA report to support using the visual methods cited in the updated ASME Section XI Code of Record.
The applicant responded by stating that the response to RAI 4.1-2 as presently drafted only addresses time-dependent fatigue flaw growth analysis. The applicant stated that the response is included in the letter (L-11-203) that is to be sent to the staff on Friday, June 17, 2011.
Because the response was already drafted and already went through the applicant's submittal process, a supplement to the response will be submitted at a later date (most likely with the letter due June 24, 2011) to address the time-dependent J-integral analysis.
ENCLOSURE 2
-2 In addition, the applicant also stated that the applicable ASME Code for the current (third) 1O-year inspection interval for Davis-Besse is ASME Section XI, 1995 Edition, through the 1996 Addenda and that the interval does not end until September 20, 2012. Therefore, the Davis-Besse CLB still relies on the SIA Topical Report SIR-99-040.
Action: NRC project manager and applicant's license renewal project manager will discuss submittal date via telephone.
Topic updated safety analysis report (USAR) Appendix SA design basis for reactor coolant pump (Rep) flywheel integrity Discussion:
The staff requested the applicant to discuss their USAR Appendix 5A design basis for RCP flywheel integrity. The staff agrees that the reference temperature nil ductility (RTndt ) analysis for the flywheels in that appendix does not need to include a time-dependent neutron fluence-based .6RTndt adjustment in the manner that they are included in the RT ndt analyses for the reactor vessel beltline components (Le., beltline base metals and weld components).
However, USAR Appendix 5A states that the Standard Review Plan (SRP) Section 5.4.1.1 acceptance basis is an 80"F difference basis between the RTndt value and the operating temperature (which according to the USAR Appendix, puts the minimum operating temperature at 120°F). Contrary to this statement, the staff determined that SRP 5.4.1.1 states (recommends) that the difference between the RTndt value and the operating temperature should be at least 100°F, which for full conformance with the SRP basis would dictate a minimum operating temperature of 140°F for the RCP flywheels at Davis-Besse. The USAR Section 5A also states that Section 3.1 of the USAR gives the 120"F operating temperature basis for the flywheels, but the staff could not find any such basis in USAR Section 3.1. The staff further stated that SRP Section 5.4.1.1 on flywheel integrity (which the applicant uses as the USAR Appendix 5A basis) states that the RTndt values for the RCP flywheel plate will be based on actual drop-weight testing results; however, the applicant established the RTndt value for the SA-533 flywheel plates materials using generic application of the RTndt values for their SA-533 plate materials for the reactor vessel (RV) beltline materials (pick 40"F as the highest value. The staff stated that this is a CLB issue.
The applicant responded by stating that its intention was not to completely comply with SRP 5.4.1.1.
The staff suggested that the applicant look into this, not as a license renewal issue, but rather as a CLB issue. The staff stated that no RAI will be issued.
Reactor Vessel Internal fRV!) components Discussion:
The staff stated that the discrepancy between the applicant's Technical Specification (TS) 5.5.4 inspection requirements for its RVI vent valve discs and its plant-specific Pressurized-Water Reactor (PWR) Vessel Internals Program criteria that needs to be discussed. The staff also stated that the adequacy of the aging management reviews (AMRs) for the RVI components will need to be discussed as well.
-3 The applicant stated that it does not believe that a discrepancy exists between the TS 5.5.4 inspection requirements for its RVI vent valve discs and its plant-specific PWR Vessel Internals Program criteria that is based on MRP-227. The applicant also stated that the TS requires the disc inspection each refueling outage versus MRP-227 that requires the inspection each 10 year interval. Therefore, MRP-227 inspection frequency is satisfied. However, this may require further discussion, as the staff lead reviewer, Ganesh Cheruvenki, was not in attendance.
The AMR of the RVI was briefly discussed. The applicant suggested that an LRA supplement could be submitted that would revise the AMR for RVI and that it would be based on MRP-227 along with the guidance provided in NUREG-1801, Revision 2 (GALL Report). The staff stated that the concerns related to the RVI would be discussed internally (to include Ganesh Cheruvenki) and a response provided to the applicant at a later date.
There was no further discussion, and the call was concluded.
Memorandum to FirstEnergy Nuclear Operating Company from S. CuadradoDeJesus dated February 9, 2012
SUBJECT:
SUMMARY
OF TELEPHONE CONFERENCE CALL HELD ON JUNE 16, 2011 BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION AND FIRSTENERGY NUCLEAR OPERATING COMPANY, CONCERNING REQUESTS FOR ADDITIONAL INFORMATION PERTAIf\IING TO THE DAVIS-BESSE NUCLEAR POWER STATION LICENSE RENEWAL APPLICATION (TAC. NO. ME4640)
DISTRIBUTION:
HARD COPY:
DLRRF E-MAIL:
PUBLIC RidsNrrDlr Resource RidsNrrDlrRpb'l Resource RidsNrrDlrRpb2 Resource RidsNrrDlrRarb Resource RidsNrrDlrRapb Resource RidsNrrDlrRasb Resource RidsNrrDlrRerb Resource RidsNrrDlrRpob Resource PCooper BHarris SCuadrado EMilier MMahoney ICouret, OPA TReilly,OCA BHarris, OGC
'.. ML12018A146 *concurred via email OFFICE LA: RPB1 :DLR* PM:RPB1 :DLR BC:RPB1 :DLR NAME YEdmonds/lKing for SCuadrado de Jesus DMorey DATE 2/9/12 2/09/12 2/09/12