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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FENOCTMFE OC% 5501 North State Route 2FirstEnergy Nuclear Operating Company Oak Harbor, Ohio 43449Raymond A. Lieb 419-321-7676Vice President, Nuclear Fax:419-321-7582February 28, 2013L-1 3-098 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-3Revised Reply to Request for Additional Information for the Review of the Davis-BesseNuclear Power Station, Unit No. 1, License Renewal Application (TAC No. ME4640)By 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 ofFederal Regulations, Part 54 for renewal of Operating License NPF-3 for theDavis-Besse Nuclear Power Station, Unit No. 1 (Davis-Besse). By letter L-13-037dated February 12, 2013, FENOC replied to Nuclear Regulatory Commission (NRC)requests for additional information (RAIs) related to NRC review of the Davis-BesseLicense Renewal Application (LRA). During a telephone conference with the NRCProject Manager for Davis-Besse License Renewal held on February 19, 2013, theNRC stated that it appeared there was a typographical error in the FENOC response toRAI B.2.43-2a regarding the value for university testing crack size.FENOC performed a review of the response to RAI B.2.43-2a and confirmed that theuniversity testing crack size of 0.20 inches provided in the response was atypographical error. The correct value for the crack size should have been 0.020 inches.FENOC performed a review of the entire response and identified one additional changein the response. Specifically, in the fourth paragraph of the response, the statement that"[t]wo adjacent splices at 6 inches on center spacing were used" should read "[t]woadjacent splices at clear spacing of approximately 6 inches were used", since thespacing between the splices was not "on center" spacing. These conditions wereentered into the FENOC Corrective Action Program.The Attachment provides the revised FENOC reply to NRC request for additionalinformation B.2.43-2a. The NRC request is shown in bold text followed by the FENOCresponse.1W1(45 Davis-Besse Nuclear Power Station, Unit No. 1L-13-098Page 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 und r penalty of perjury that the foregoing is true and correct. Executed onFebruary ;,k, 2013.Sincerely,RayýoA L ie bAttachment:Revised Reply to Request for Additional Information for the Review of theDavis-Besse Nuclear Power Station, Unit No. 1 (Davis-Besse), License RenewalApplication (LRA), Section B.2.43cc: NRC DLR Project ManagerNRC Region III Administratorcc: w/o AttachmentNRC DLR DirectorNRR DORL Project ManagerNRC Resident InspectorUtility Radiological Safety Board AttachmentL-1 3-098Revised Reply to Request for Additional Information for the Review of theDavis-Besse Nuclear Power Station, Unit No. 1 (Davis-Besse),License Renewal Application (LRA),Section B.2.43Page 1 of 3Question RAI B.2.43-2aBackground:By letter dated November 20, 2012, the applicant responded to a request foradditional information (RAI) regarding the proposed monitoring methods for theshield building (SB) cracking. The RAI response indicates that the proposedinspection sample size of 20 core bores will cover the three areas of cracking(flute shoulders, upper 20 ft of the building, and the steam line penetrations) andis adequate to identify any changes in the laminar cracking, without furtherimpulse response testing during the period of extended operation.Issue:As part of evaluating the applicant's plan for monitoring the SB cracking withcore bores, the staff needs to understand the technical basis for the size of thesample. For example, is the sample based purely on statistics or is it based onthe long term effect of the concrete cracks on the ability of the reinforcement tocarry design loads and the safety significance of the cracking. In an earlier RAIresponse, dated April 5, 2012, it was indicated that the structural impact of thecracking would be determined via testing. A summary description of the testresults and discussion of how the test results demonstrate that the sample size issufficient has not been provided.Request:Provide a discussion of the technical basis for the adequacy of the sample size. Ifthe sample size was based on laboratory testing, provide a summary of thetesting. Include an explanation of the testing completed as well as the results,and how this information relates to the structural capacity of the SB and supportsthe adequacy of the sample size.Telephone Conference Call Summary:The NRC Staff initiated a telephone conference call with FENOC on January 16,2013, to discuss and clarify NRC follow-up RAIs B.2.43-2a and B.2.43-3a regardingthe Davis-Besse Shield Building Monitoring Program. Following discussions, NRCStaff stated that, instead of addressing RAI B.2.43-2a as written, FENOC shouldrespond to the RAI by providing summaries of the laboratory (i.e., university)testing performed and the results of the testing. The summary should address the AttachmentL-1 3-098Page 2 of 3Shield Building reinforcing bar-concrete bond strength, the assumptions made inthe structural operability calculations regarding bond strength, and how thetesting performed supports those assumptions. A copy of laboratory reports isnot needed by the NRC Staff.RESPONSE RAI B.2.43-2aTesting was performed at the University of Kansas and at Purdue University to assessthe concrete-rebar bond strength of concrete with a laminar crack. Given theconservative nature of the test conditions used in these studies, it is concluded that thereinforcement in the Shield Building experiences little, if any reduction in strength andcapacity due to the laminar cracking condition.During the evaluation of the Shield Building laminar cracking in 2011, FENOC performedcalculations to document that the Shield Building remains capable of performing itssafety functions despite the presence of laminar cracking. FENOC assumed in theevaluation calculations that there was no reinforcement capacity in cracked zones wherethe reinforcing bar included splices. The rationale for the assumption was that unsplicedrebar spanning cracked zones retained capacity, while reinforcement capacity with rebarsplices could not be quantified, and therefore was considered ineffective in the analysis.It was recognized at the time that follow-up laboratory testing was required to confirmassumptions regarding reinforcement capacity of spliced rebar.FENOC sponsored independent testing programs at Purdue University and theUniversity of Kansas to determine the effects of laminar cracking in the plane of andparallel with reinforcing bar splices (a condition similar to the Shield Building laminarcracking). The laboratory testing confirmed that the robust design and construction of theShield Building allow the building to retain significant margin against design loads evenwith laminar cracking.Both universities conducted testing programs to evaluate the effects of the laminarcracking using large scale rectangular section beams with size #11 tensionreinforcement splices. The #11 reinforcement was chosen since it matches the size usedin the construction of the Shield Building. Two adjacent splices at clear spacing ofapproximately 6 inches were used in all beams to simulate rebar interaction. The testspecimen set-up at both universities was conservative since the Shield Buildingreinforcement splices are staggered, and not side-by-side, as constructed at bothlaboratory test facilities. Both testing programs used materials that were representativeof the Shield Building materials with similar strengths. Concrete strengths of the sampleswere representative and conservative relative to the strength of the materials in theShield Building. Select beams in both the Purdue and Kansas studies were subject toreload cycles. These beams were loaded to develop the crack (at calculated yield),unloaded, and the beams were reloaded to failure. The crack sizes developed exceededthe crack widths identified in the Shield Building.
AttachmentL-1 3-098Page 3 of 3Purdue University tested six samples with 120-inch splices and six samples with 79-inchsplices. These splice lengths correspond to the splice lengths used in the ShieldBuilding. Purdue used beam geometry in order to produce a preferential (laminar) crackat the location of reinforcement when loaded.During testing, cracks developed and opened to widths exceeding 0.10 inches whenapproaching the maximum load. These crack widths well exceeded the Shield Buildingcracks identified and essentially covered the entire test span prior to failure.Each of the beams tested demonstrated two fundamental properties:1. Each beam developed yielding stress in the reinforcement after thedevelopment of laminar cracks, and2. The load deflection curves for each beam exhibited classic ductile behavior withincreasing deflection beyond the yield point.These tests demonstrate that the reinforcement, and therefore the building as a system,retains its strength despite cracking, given the reinforcement was capable of developingyield stress. By exhibiting ductile behavior, the tests confirm that despite the laminarcracking condition, the building system can be expected to demonstrate the classicallyrequired deflection and surface cracking indications prior to failure.The University of Kansas also used a large-scale rectangular beam section with #11rebar splices as noted above; however, the main study beams were cast with a cold jointin the plane of the reinforcement for a length greater than the entire splice length. TheUniversity of Kansas tested 6 beams: 3 with 79-inch splices, and 3 with 120-inch splices.These splice lengths correspond to the splice lengths used in the Shield Building.For the beams with the reload cycles, crack widths were at or greater than a width of0.020 inches prior to unloading. This exceeds the crack widths identified in the ShieldBuilding by a factor of approximately 2. These specimens developed capacities near andabove yield despite the conservative testing conditions.Given the conservative nature of the conditions used in the tests, it is the conclusion ofthe professors who conducted and evaluated the tests that the reinforcement in theShield Building experiences little, if any, reduction in strength and capacity due to thelaminar cracking condition. The studies also document that the structure retains itsserviceability and ductile behavior. The university test findings provide additionalconfidence in structural adequacy above that already documented in the functionalitycalculations, and confirmed that the robust design and construction of the ShieldBuilding allow the building to retain significant margin against design loads even withlaminar cracking.