Letter Sequence Response to 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:Letter
MONTHYEARML24249A1602024-09-0505 September 2024 Information Request to Support Upcoming Material Control and Accounting Inspection at Davis-Besse Nuclear Power Station L-24-188, Submittal of Quality Assurance Program Manual, Revision 302024-08-27027 August 2024 Submittal of Quality Assurance Program Manual, Revision 30 ML24239A3972024-08-23023 August 2024 Rssc Wire & Cable LLC Dba Marmon - Part 21 Final Notification - 57243-EN 57243 IR 05000346/20240052024-08-22022 August 2024 Updated Inspection Plan for Davis-Besse Nuclear Power Station (Report 05000346/2024005) IR 05000346/20240022024-08-0101 August 2024 Integrated Inspection Report 05000346/2024002 IR 05000346/20244012024-07-30030 July 2024 Security Baseline Inspection Report 05000346/2024401 ML24208A0962024-07-25025 July 2024 57243-EN 57243 - Rssc Wire & Cable LLC, Dba Marmon - Part 21 Notification L-24-032, Cycle 23 and Refueling Outage 23 Inservice Inspection Summary Report2024-07-15015 July 2024 Cycle 23 and Refueling Outage 23 Inservice Inspection Summary Report L-24-063, License Amendment Request to Remove the Table of Contents from the Technical Specifications2024-07-0808 July 2024 License Amendment Request to Remove the Table of Contents from the Technical Specifications L-24-024, Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2024-06-19019 June 2024 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models L-23-214, Submittal of Relief Request for Impractical American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI Examination Requirements2024-06-0505 June 2024 Submittal of Relief Request for Impractical American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI Examination Requirements L-24-019, Unit No.1 - Report of Facility Changes, Tests, and Experiments2024-05-22022 May 2024 Unit No.1 - Report of Facility Changes, Tests, and Experiments ML24142A3532024-05-21021 May 2024 Station—Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection L-24-111, Response to Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-05-15015 May 2024 Response to Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations L-24-072, Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report - 20232024-05-15015 May 2024 Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report - 2023 L-24-031, Unit No.1 - Steam Generator Tube Circumferential Crack Report - Spring 2024 Refueling Outage2024-05-14014 May 2024 Unit No.1 - Steam Generator Tube Circumferential Crack Report - Spring 2024 Refueling Outage IR 05000346/20240012024-05-0303 May 2024 Integrated Inspection Report 05000346/2024001 L-24-069, Occupational Radiation Exposure Report for Year 20232024-04-30030 April 2024 Occupational Radiation Exposure Report for Year 2023 L-24-018, Submittal of Core Operating Limits Report, Cycle 24, Revision 02024-04-16016 April 2024 Submittal of Core Operating Limits Report, Cycle 24, Revision 0 ML24089A2582024-04-0101 April 2024 Request for Information for the NRC Quuadrennial Comprehensive Engineering Team Inspection: Inspection Report 05000346/2024010 L-24-013, Annual Notification of Property Insurance Coverage2024-03-26026 March 2024 Annual Notification of Property Insurance Coverage ML24036A3472024-03-0707 March 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0076 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML24057A0752024-03-0101 March 2024 the Associated Independent Spent Fuel Storage Installations IR 05000346/20230062024-02-28028 February 2024 Re-Issue Annual Assessment Letter for Davis-Besse Nuclear Power Station (Report 05000346/2023006) ML24057A3362024-02-28028 February 2024 Annual Assessment Letter for Davis-Besse Nuclear Power Station (Report 05000346/2023006) CP-202300502, Notice of Planned Closing of Transaction and Provision of Documents to Satisfy Order Conditions2024-02-23023 February 2024 Notice of Planned Closing of Transaction and Provision of Documents to Satisfy Order Conditions L-24-050, Retrospective Premium Guarantee2024-02-22022 February 2024 Retrospective Premium Guarantee IR 05000346/20243012024-02-0202 February 2024 NRC Initial License Examination Report 05000346/2024301 IR 05000346/20230042024-01-31031 January 2024 Integrated Inspection Report 05000346/2023004 ML23313A1352024-01-17017 January 2024 Authorization and Safety Evaluation for Alternative Request RP 5 for the Fifth 10 Year Interval Inservice Testing Program ML23353A1192023-12-19019 December 2023 Operator Licensing Examination Approval Davis Besse Nuclear Power Station, January 2024 L-23-260, Corrections to the 2022 Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report for the Davis-Besse Nuclear Power Station2023-12-0707 December 2023 Corrections to the 2022 Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report for the Davis-Besse Nuclear Power Station L-23-243, Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-12-0606 December 2023 Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23338A3172023-12-0606 December 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000346/2024001 IR 05000346/20234032023-11-0202 November 2023 Security Baseline Inspection Report 05000346/2023403 ML23293A0612023-11-0101 November 2023 Letter to the Honorable Marcy Kaptur, from Chair Hanson Responds to Letter Regarding Follow Up on Concerns Raised by Union Representatives During the June Visit to the Davis-Besse Nuclear Power Plant ML24045A0322023-10-26026 October 2023 L-23-221 Proposed Exam Submittal Cover Letter L-23-215, Changes to Emergency Plan2023-10-19019 October 2023 Changes to Emergency Plan ML23237B4222023-09-28028 September 2023 Energy Harbor Nuclear Corp. - Vistra Operations Company LLC - Letter Regarding Order Approving Transfer of Licenses and Draft Conforming License Amendments ML23269A1242023-09-27027 September 2023 Request for Withholding Information from Public Disclosure IR 05000346/20234012023-09-13013 September 2023 Security Baseline Inspection Report 05000346/2023401 (Public) L-23-205, Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-09-12012 September 2023 Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments L-23-172, Quality Assurance Program Manual2023-08-31031 August 2023 Quality Assurance Program Manual IR 05000346/20230112023-08-30030 August 2023 Biennial Problem Identification and Resolution Inspection Report 05000346/2023011 ML23129A1722023-08-25025 August 2023 Request for Withholding Information from Public Disclosure for Beaver Valley Power Station, Units 1 and 2; Davis Besse Nuclear Power Station, Unit 1; and Perry Nuclear Power Plant, Unit 1 IR 05000346/20230052023-08-24024 August 2023 Updated Inspection Plan for Davis-Besse Nuclear Power Station (Report 05000346/2023005) L-23-188, Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-08-0707 August 2023 Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments IR 05000346/20230502023-08-0303 August 2023 Special Inspection Report 05000346/2023050 L-23-175, Submittal of Fifth Ten Year Inservice Testing Program2023-08-0101 August 2023 Submittal of Fifth Ten Year Inservice Testing Program IR 05000346/20230902023-08-0101 August 2023 EA-23-002 Davis-Besse Nuclear Power Station - NRC Inspection Report No. 05000346/2023090 (Public) 2024-09-05
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FENOC0E-% 5501 North State Route 2FirstEnergy Nuclear Operating Company Oak Harbor, Ohio 43449Barry S. Allen 419-321-7676Vice President -Nuclear Fax. 419-321-7582May 25, 2012L-12-185 10 CFR 54ATTN: Document Control DeskU. S. Nuclear Regulatory CommissionWashington, DC 20555-0001SUBJECT:Davis-Besse Nuclear Power Station, Unit No. 1Docket No. 50-346, License Number NPF-3Supplemental Reply to Request for Additional Information for the Review of theDavis-Besse Nuclear Power Station, Unit No. 1, License Renewal Application(TAC No. ME4640) and License Renewal Application Amendment No. 26By letter dated August 27, 2010 (Agencywide Documents Access and ManagementSystem (ADAMS) Accession No. ML102450565), FirstEnergy Nuclear OperatingCompany (FENOC) submitted an application pursuant to Title 10 of the Code of FederalRegulations, Part 54 for renewal of Operating License NPF-3 for the Davis-BesseNuclear Power Station, Unit No. 1 (DBNPS). By letter dated August 11, 2011(ML1 1216A236), the Nuclear Regulatory Commission (NRC) issued request foradditional information (RAI) 4.3.2.3.2-1 -(Supplement), to complete its review of theLicense Renewal Application (LRA). By letter dated October 7, 2011 (ML1 1285A064),FENOC responded to the RAI by providing a commitment to perform a fatigue evaluationof selected Class 1 valves and submit an amendment to the LRA.The actions described in the commitment have been completed. The Attachmentprovides a supplemental response to NRC RAI 4.3.2.3.2-1 -(Supplement), including adescription of the Class 1 valve fatigue evaluations performed and results obtained. TheNRC request is shown in bold text followed by the FENOC response.The Enclosure provides Amendment No. 26 to the DBNPS LRA.
Davis-Besse Nuclear Power Station, Unit No. 1L-1 2-185Page 2There are no regulatory commitments contained in this letter. If there are any questionsor if additional information is required, please contact Mr. Clifford I. Custer, FleetLicense Renewal Project Manager, at 724-682-7139.I declare under penalty of perjury that the foregoing is true and correct. Executed onMay_2, 2012.Sincerely,Barry S enAttachment:Supplemental Reply to Request for Additional Information for the Review of theDavis-Besse Nuclear Power Station, Unit No. 1 (DBNPS), License RenewalApplication, Section 4.3.2Enclosure:Amendment No. 26 to the DBNPS License Renewal Applicationcc: NRC DLR Project ManagerNRC Region III Administratorcc: w/o Attachment or EnclosureNRC DLR DirectorNRR DORL Project ManagerNRC Resident InspectorUtility Radiological Safety Board
Attachment
L-12-185Supplemental Reply to Request for Additional Information for the Review of theDavis-Besse Nuclear Power Station, Unit No. 1 (DBNPS), License Renewal Application,Section 4.3.2Page 1 of 3Section 4.3.2Question RAI 4.3.2.3.2-1 -(Supplement)Background:By letter dated June 22, 2011, the applicant responded to RAI 4.1-1 regardingcumulative usage factor (CUF) or It fatigue analyses for Class 1 valves. In itsresponse to RAI 4.1-1, Request 1, Part A, the applicant identified 12 large boreClass 1 valves (i.e., valves with nominal pipe sizes in excess of 4-inches) thatshould have received CUF or It fatigue analyses in accordance with the designcodes (i.e., 1971 or more recent Editions of the ASME Code Section III, or the1968 Edition of the Draft ASME Pump and Valve Code for Nuclear Power Plants).The applicant provided Commitment No. 46 to complete the following, prior toApril 22, 2015:FENOC commits to perform a fatigue evaluation in accordance withthe requirements of the ASME Code of record for the Davis-BesseClass 1 valves that are greater than 4 inches nominal pipe size. Theapplicable valve identification numbers are CF28, CF29, CF30, CF31,DH76, DH77, DH11, DH12, DHIA, DHIB, DH21, and DH23.LRA Section 4.3.2.3.2, as amended by letter dated June 22, 2011, states that thefatigue analyses for these 12 referenced large bore Class I valves are as TLAAsand are dispositioned in accordance with Title 10 of the Code of FederalRegulations 54.21(c)(1)(iii), that the effects of fatigue on Class 1 valves greaterthan 4 inches diameter nominal pipe size will be managed for the period ofextended operation by the Fatigue Monitoring Program. LRA Section 4.3.2.3.2also states that the issue with the missing CUF or It calculations for the12 referenced large bore Class 1 valves has been entered into the applicant'sCorrective Actions Program.Issue:The information provided by the applicant in letter of June 22, 2011, did notprovide information regarding whether the applicant had any ASME Code,Section III NB-3222.4(d) fatigue waiver assessments (or equivalent waiverassessments permitted by the 1968 Draft ASME Pump and Valve Code) for the12 large bore Class 1 valves referenced in Commitment No. 46. Therefore, the
Attachment
L-12-185Page 2 of 3staff requests additional information regarding whether fatigue calculations arerequired for these valves.The staff is concerned that without the CUF or It analyses or an appropriatefatigue waiver or exemption for these 12 large bore Class 1 valves, the staff wouldnot be able to evaluate whether the aging effects will be appropriately managedby the commitment.Request:Provide justification for not having the analyses for staff review as part of theLRA, or provide your appropriate fatigue waiver or fatigue exemption bases fornot having such analyses.RESPONSE RAI 4.3.2.3.2-1 -(Supplement)In response to RAI 4.3.2.3.2-1 -(Supplement) submitted by letter dated October 7, 2011(ML1 1285A064), FENOC provided the following commitment:FENOC will perform a fatigue evaluation in accordance with therequirements of the ASME Code of record for the Davis-Besse Class 1valves that are greater than 4 inches diameter nominal pipe size. Theapplicable valve identification numbers are CF28, CF29, CF30, CF31, DH76,DH77, DH11, DH12, DH1A, DH1B, DH21 and DH23. LRA Sections 4.3.2.3.2and A.2.3.2.13, both titled "Class 1 Valves Fatigue," will be revised to includethe results of the fatigue evaluations, and these changes will be submitted asan amendment to the Davis Besse LRA no later than May 31, 2012.The actions described in the commitment have been completed. This supplementalresponse to RAI 4.3.2.3.2-1 -(Supplement) addresses the fatigue evaluation results ofthe Davis-Besse Class 1 valves that are greater than 4 inches diameter nominal pipesize (valve identification numbers CF28, CF29, CF30, CF31, DH76, DH77, DH1 1,DH12, DHIA, DH1B, DH21 and DH23) and the associated changes to License RenewalApplication (LRA) Sections 4.3.2.3.2 and A.2.3.2.13.Fatigue analyses were prepared for the subject Class 1 valves in accordance withparagraph NB-3550 of ASME Code Section III, 1974 Edition with Addenda through theSummer of 1976, and were reconciled to the valve construction code year. Thecumulative usage factors (CUFs) calculated for the subject Class 1 valves are based onnuclear steam supply system design transients and, as shown in the table below, areless than 1.0. The number of occurrences of design transients is tracked by the FatigueMonitoring Program to ensure that action is taken before the design cycles are reached.Therefore, the effects of fatigue on Class 1 valves greater than 4 inches diameter
Attachment
L-12-185Page 3 of 3nominal pipe size (NPS) will be managed for the period of extended operation by theFatigue Monitoring Program in accordance with 10 CFR 54.21(c)(1)(iii).Size Construction MaximumValve ID (dia. NPS) Code Year CUF& TypeCF28CF29 14 inch 1971 Core Flood -w/Addenda thru core flood tank discharge line 0.02839CF30 Winter 1972 stop check isolation valveCF31DHI 1 12 inch 1968 Reactor Coolant System to Decay Heat- 0.14594gate Draft Pump & containment isolation valveDH12 gValveDH21 8 inch 1971 Reactor Coolant System to Decay Heat -w/Addenda thru containment isolation valve bypass line 0.02732DH23 gate Winter 1972 isolation valveDH76 10 inch 1971 Low Pressure Injection tow/Addenda thru Reactor Coolant System -0.14099DH77 Winter 1972 stop check isolation valveDH1A 10 inch 1968 Low Pressure Injection -gate Draft Pump & outside containment isolation valve 0.18261DH1Bgt ValveLRA Sections 4.3.2.3.2 and A.2.3.2.13 are revised to include the results of the fatigueevaluations.See the Enclosure to this letter for the revision to the DBNPS LRA.
Enclosure
Davis-Besse Nuclear Power Station, Unit No. 1 (DBNPS)Letter L-12-185Amendment No. 26 to theDBNPS License Renewal ApplicationPage 1 of 5License Renewal ApplicationSections AffectedSection 4.3.2.3.2Section A.2.3.2.13The Enclosure identifies the change to the License Renewal Application (LRA) byAffected LRA Section, LRA Page No., and Affected Paragraph and Sentence. Thecount for the affected paragraph, sentence, bullet, etc. starts at the beginning of theaffected Section or at the top of the affected page, as appropriate. Below each sectionthe reason for the change is identified, and the sentence affected is printed in italics withdeleted text hined-ou and added text underlined.
Enclosure
L-12-185Page 2 of 5Affected LRA Section LRA Page No. Affected Paragraph and Sentence4.3.2.3.2 Pages 4.3-16 Entire Sectionand 4.3-17In response to RAI 4.3.2.3.2-1 -(Supplement), LRA Section 4.3.2.3.2, "Class 1Valves Fatigue," previously revised by FENOC letter dated October 7, 2011(ML1I1285A064), is replaced in its entirety, to read as follows:4.3.2.3.2 Class 1 Valves FatigueThe ASME Code requires a fatigue evaluation for Class 1 valves greater than 4inches diameter nominal pipe size or for valves less than or equal to 4 inches innominal pipe size if specified by the owner's design specification. TheDavis-Besse purchasing specifications did not require a fatigue analysis forClass 1 valves less than or equal to 4 inches in nominal pipe size. Therefore,only valves greater than 4 inches diameter nominal pipe size require a fatigueanalysis. Piping and instrumentation diagrams (P&IDs) were reviewed to identifyClass 1 valves of greater than 4 inches diameter nominal pipe size. There were12 valves of greater than 4 inches diameter nominal pipe size that were identifiedas a result of this effort.Fatigue analyses were prepared for the subject Class 1 valves in accordancewith paragraph NB-3550 of ASME Code Section III, 1974 Edition with Addendathrough the Summer of 1976 and were reconciled to the valve constructioncode year.Since ASME Code fatigue analyses evaluate an explicit number and type ofthermal and pressure transients that are postulated to envelope the number ofoccurrences possible during the design life of the plant, these fatigue analysesare time-limited aging analyses (TLAAs) and therefore, are required to beevaluated in accordance with 10 CFR 54.21(c)(1).The cumulative usage factors calculated for the subject Class 1 valves are basedon nuclear steam supply system design transients and, as shown in the tablebelow, are less than 1.0. The number of occurrences of design transients istracked by the Fatigue Monitoring Program to ensure that action is taken beforethe design cycles are reached. Therefore, the effects of fatigue on Class 1 valvesgreater than 4 inches diameter nominal pipe size (NPS) will be managed for theperiod of extended operation by the Fatigue Monitoring Program.
Enclosure
L-12-185Page 3 of 5Size Construction MaximumValve ID (dia. NPS) Code Year Description CUF& TypeCF28CF29 14 inch 1971 Core Flood -w/Addenda thru core flood tank discharge line 0.02839CF30 Winter 1972 stop check isolation valveCF31Draft1968 Reactor Coolant System to Decay Heat -DH12 gate Valv containment isolation valve 0.14594DH12 ValveDH21 8 inch 1971 Reactor Coolant System to Decay Heat -w/Addenda thru containment isolation valve bypass line 0.02732DH23 gate Winter 1972 isolation valveDH76 10 inch 1971 Low Pressure Injection tow/Addenda thru Reactor Coolant System -0.14099DH77 Winter 1972 stop check isolation valveDDrf1A 10 inch 1968 Low Pressure Injection -gae Draft Pump & outside containment isolation valve 0.18261DH-11B at ValveDisposition: 10 CFR 54.21(c)(1)(iii)The effects of fatigue on Class I valvesgreater than 4 inches diameter nominalpipe size will be managed for the periodof extended operation by the FatigueMonitoring Program.
Enclosure
L-1 2-185Page 4 of 5Affected LRA Section LRA Paqe No. Affected Paragraph and SentenceA.2.3.2.13 Page A-41 Entire SectionIn response to RAI 4.3.2.3.2-1 -(Supplement), LRA Section A.2.3.2.13, "Class 1Valves Fatigue," previously revised by FENOC letter dated October 7, 2011(ML1I1285A064), is replaced in its entirety, to read as follows:A.2.3.2.13 Class 1 Valves FatigueThe ASME Code requires a fatigue evaluation for Class 1 valves greater than 4inches diameter nominal pipe size or for valves less than or equal to 4 inches innominal pipe size if specified by the owner's design specification. TheDavis-Besse purchasing specifications did not require a fatigue analysis forClass 1 valves less than or equal to 4 inches in nominal pipe size. Therefore,only valves greater than 4 inches diameter nominal pipe size require a fatigueanalysis. Piping and instrumentation diagrams (P&IDs) were reviewed to identifyClass 1 valves of greater than 4 inches diameter nominal pipe size. There were12 valves of greater than 4 inches diameter nominal pipe size that were identifiedas a result of this effort.Fatigue analyses were prepared for the subject Class 1 valves in accordancewith paragraph NB-3550 of ASME Code Section III, 1974 Edition with Addendathrough the Summer of 1976 and were reconciled to the valve constructioncode year.Since ASME Code fatigue analyses evaluate an explicit number and type ofthermal and pressure transients that are postulated to envelope the number ofoccurrences possible during the design life of the plant, these fatigue analysesare time-limited aging analyses (TLAAs) and therefore, are required to beevaluated in accordance with 10 CFR 54.21(c)(1).The cumulative usage factors calculated for the subject Class 1 valves are basedon nuclear steam supply system design transients and, as shown in the tablebelow, are less than 1.0. The number of occurrences of design transients istracked by the Fatigue Monitoring Program to ensure that action is taken beforethe design cycles are reached. Therefore, the effects of fatigue on Class 1 valvesgreater than 4 inches diameter nominal pipe size (NPS) will be managed for theperiod of extended operation by the Fatigue Monitoring Program in accordancewith 10 CFR 54.21 (c)(1)(iii).
Enclosure
L-12-185Page 5 of 5size Construction MaximumValve ID (dia. NPS) Code Year Description CUF& TypeCF28CF29 14 inch 1971 Core Flood -w/Addenda thru core flood tank discharge line 0.02839CF30 Winter 1972 stop check isolation valveCF31Draft1968 Reactor Coolant System to Decay Heat -DH1g Draft Pump & containment isolation valve 0.14594DH12 gaeValveDH21 8 inch 1971 Reactor Coolant System to Decay Heat -w/Addenda thru containment isolation valve bypass line 0.02732DH23 gate Winter 1972 isolation valveDH76 10 inch 1971 Low Pressure Injection tow/Addenda thru Reactor Coolant System -0.14099DH77 Winter 1972 stop check isolation valveDH1A 10 inch 1968 Low Pressure Injection -Dae Draft Pump & outside containment isolation valve 0.18261DH-11B at Valve III