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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217P2061999-10-26026 October 1999 Forwards for First Energy Nuclear Operating Co Insp Rept 50-346/99-17 on 990928-1001.Insp Was Exam of Activities Conducted Under License Re Implementation of Physical Security Program.No Violations Identified ML20217N3851999-10-20020 October 1999 Forwards RAI Re Licensee 990521 Request for License Amend to Allow Irradiated Fuel to Be Stored in Cask Pit at Davis-Besse,Unit 1.Response Requested within 60 Days from Receipt of Ltr ML20217N2321999-10-15015 October 1999 Requests NRC Approval to Use Alternative to Requirements of 10CFR50.55a(f)(4)(ii).Licensee Requests Extension to Specified Schedule for Implementing Updates to IST Program ML20217G9201999-10-14014 October 1999 Discusses Utils Request for Approval of Quality Assurance Program Changes PY-CEI-NRR-2438, Informs That DBNPS & Pnpp Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl1999-10-14014 October 1999 Informs That DBNPS & Pnpp Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl ML20217F8371999-10-0808 October 1999 Forwards Insp Rept 50-346/99-10 on 990802-0913.One Violation Occurred Being Treated as NCV ML20217A5641999-09-30030 September 1999 Informs of Completion of mid-cycle PPR of Davis-Besse on 990901.Informs That NRC Plans to Conduct Addl Insps to Address Questions Raised by Issues Re Operator Errors & Failure to Commit to JOG Topical Rept on MOV Verification ML20212L0691999-09-30030 September 1999 Forwards,For Review & Comment,Copy of Preliminary ASP Analysis of Operational Condition Discovered at Unit 1 on 981014,as Reported in LER 346/98-011 ML20216J6701999-09-24024 September 1999 Forwards Post Examination Documentation for Written Operator Initial License Examination Administered at Davis-Besse Nuclear Power Station on 990920.Without Encls ML20212D3501999-09-21021 September 1999 Forward Copy of Final Accident Sequence Precursor Analysis of Operational Event at Plant,Unit 1 on 980624,reported in LER 346/98-006 05000346/LER-1998-001, Forwards Rev 1 for LER 1998-001,which Updates Corrective Actions & Revises Completion Date Re Implementation of Changes to Plant Emergency Operating Procedure.List of Commitments Attached1999-09-0909 September 1999 Forwards Rev 1 for LER 1998-001,which Updates Corrective Actions & Revises Completion Date Re Implementation of Changes to Plant Emergency Operating Procedure.List of Commitments Attached ML20216E5961999-09-0707 September 1999 Forwards Application for Amend to License NPF-3,revising Tech Specs 3/4.3.2.1,safety Features Actuation Sys Instrumentation & Associated Bases 3/4.3.1 & 3/4.3.2,reactor Protection Sys & Safety Sys Instrumentation ML20211P3001999-09-0707 September 1999 Forwards FEMA Transmitting FEMA Evaluation Rept for 990504 Emergency Preparedness Exercise at Davis-Besse Nuclear Power Plant.No Deficiencies Identified.One Area Requiring C/A & Two Planning Issues Identified ML20211K6681999-08-30030 August 1999 Forwards Copies of Certified Personal Qualification Statement - Licensee (NRC Form 398) for Operator Candidates Listed Below.Without Encls ML20211K6611999-08-30030 August 1999 Forwards Copies of Operator License Renewal Applications for Individuals Listed.Operators Have Successfully Completed Appropriate Operator Requalification Training Program at Dbnps.Without Encls ML20211K0951999-08-30030 August 1999 Forwards Request for Addl Info Re Fire & Seismic Analyses of IPEEE for Davis-Besse Nuclear Power Station,Unit 1. Response Requested within 60 Days ML20211H0201999-08-25025 August 1999 Forwards semi-annual FFD Rept for 990101-0630 for DBNPS, Unit 1,IAW 10CFR26.71(d) ML20211D1171999-08-20020 August 1999 Forwards Insp Rept 50-346/99-09 on 990623-0802.Violations Identified & Being Treated as Noncited Violations ML20211G3911999-08-20020 August 1999 Forwards Update to Estimated Info for Licensing Action Requests Through 010930,re Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates PY-CEI-NRR-2411, Informs That Firstenergy Nuclear Operating Co Has Developed Corporate QA Program Manual for Davis-Besse Nuclear Power Station & Perry Nuclear Power Plant,As Discussed on 990318 Between Util & Nrc.Revised USAR Pages,Encl1999-08-19019 August 1999 Informs That Firstenergy Nuclear Operating Co Has Developed Corporate QA Program Manual for Davis-Besse Nuclear Power Station & Perry Nuclear Power Plant,As Discussed on 990318 Between Util & Nrc.Revised USAR Pages,Encl ML20211J9201999-08-13013 August 1999 Urges NRC to Find Funds for Stockpiling Radiation Pills for Residents Living Near Plant ML20211B0161999-08-13013 August 1999 Forwards SE Accepting Evaluation of Second 10-year Interval Inservice Insp Program Request for Relief Numbers RR-A16, RR-A17 & RR-B9 for Plant,Unit 1 ML20210T1061999-08-12012 August 1999 Forwards Preliminary NRC Forms 398 & 396 for Listed Candidates,Per Operator License Exam Scheduled for Week of 990913.Encl Withheld ML20210S6071999-08-11011 August 1999 Provides Final Response to NRC RAI Re GL 98-01, Y2K Readiness of Computer Systems at Npps ML20210P8051999-08-0909 August 1999 Forwards Insp Rept 50-346/99-15 on 990712-16.No Violations Noted.However,Several Deficiencies Were Identified with Implementation of Remp,Which Collectively Indicated Need for Improved Oversight of Program IR 05000346/19980211999-08-0606 August 1999 Refers to NRC Insp Rept 50-346/98-21 Conducted on 980901- 990513 & Forwards Nov.Two Violations Identified Involving Failure to Maintain Design of Valve & Inadequate C/A for Degraded Condition Cited in Encl NOV 05000346/LER-1998-009, Forwards LER 98-009-01,IAW 10CFR50.73(a)(2)(ii)(B). Commitments Made by Util Are Encl1999-08-0606 August 1999 Forwards LER 98-009-01,IAW 10CFR50.73(a)(2)(ii)(B). Commitments Made by Util Are Encl ML20210H6101999-07-30030 July 1999 Informs That Region III Received Rev 21 to Various Portions of Davis-Besse Nuclear Power Station Emergency Plan.Revision Was Submitted Under Provisions of 10CFR50.54(q) in Apr 1999 ML20210H0491999-07-28028 July 1999 Forwards Application for Amend to License NPF-3,revising TS 3/4.7.5.1, Ultimate Heat Sink, to Allow Plant Operation in Modes 1-4 with Water Temp Less than or Equal to 90 F ML20210G5521999-07-28028 July 1999 Provides Addl Response to 980923 OL Licensing Exam Rept 50-346/98-301 Re OL Exam Administered in Aug 1998.Results of Root Cause Investigation & Corrective Actions,Discussed ML20210G3831999-07-27027 July 1999 Forwards Application for Amend to NPF-3,changing TSs 6.4, Training, 6.5.2.8, Audits, 6.10, Record Retention, 6.14, Process Control Program & 6.15, Odcm ML20211P3071999-07-26026 July 1999 Forwards Final Rept for 990504 Biennial Radiological Emergency Preparedness Exercise for David-Besse Power Station.No Deficiencies Identified for Any Jurisdiction During Exercise ML20210G4391999-07-26026 July 1999 Forwards Application for Amend to License NPF-3,revising Tech Specs 3/4.3.2.1, Safety Features Actuation Sys Instrumentation, & Associated Bases 3/4.3.1 & 3/4.3.2, Reactor Protection Sys & Safety Sys Instrumentation ML20210G7151999-07-26026 July 1999 Forwards Application for Amend to License NPF-3,revising TSs 3/4.3.3.1, Radiation Monitoring Instrumentation, 3/4.3.3.2, Instrument - Incore Detectors & 3/4.3.3.9, Instrumentation - Waste Gas Sys Oxygen Monitor ML20210G5151999-07-26026 July 1999 Forwards Application for Amend to License NPF-3,revising Tech Specs for Implementation of 10CFR50,App J,Option B for Type B & C Containment Leakage Rate Testing ML20210G3211999-07-26026 July 1999 Forwards Written OL Exam & Supporting Matl for Exam to Be Administered at DBNPS During Week of 990913.Listed Encls Withheld from Public Disclosure Until After Exam Complete ML20210C4381999-07-20020 July 1999 Forwards Insp Rept 50-346/99-08 on 990513-0622.Unidentified RCS Leak Approached TS Limit of 1 Gallon Per Minute Prior to Recently Completed Maint Outage.Three Violations of NRC Requirements Identified & Being Treated as NCVs ML20209G3681999-07-15015 July 1999 Advises That Info Submitted in & 990519 Affidavit Re Design & Licensing Rept,Davis-Besse,Unit 1 Cask Pit Rack Installation Project,Holtec Intl, HI-981933,marked Proprietary,Will Be Withheld from Public Disclosure ML20207H6401999-07-0909 July 1999 Discusses Closure of TAC MA0540 Re Util Responses to RAI on GL 92-01,rev 1,suppl 1, Rv Structural Integrity. Staff Has Revised Info in Rvid & Releasing It as Rvid Version 2 ML20209D1341999-07-0808 July 1999 Forwards Notice of Withdrawal of Application for Amend to Operating License.Proposed Change Would Have Modified Facility TSs Pertaining to Allowable as-found Pressure Lift Setting Tolerance of Two Pressurizer Code Safety Valves 05000346/LER-1998-012, Forwards LER 98-012-01,which Is Being Submitted to Provide Addl Info Re 981018 Occurrence.Commitment List Attached1999-07-0707 July 1999 Forwards LER 98-012-01,which Is Being Submitted to Provide Addl Info Re 981018 Occurrence.Commitment List Attached ML20209C3981999-07-0101 July 1999 Responds to NRC Re Violations Noted in Insp Rept 50-346/98-21.Corrective Actions:Developed Rev to Boric Acid Control Program & Work Process Guideline on Plant Leakage ML20209B5821999-06-24024 June 1999 Provides Justification for Rev to Completion Date for One of Insp follow-up Items Cited in Insp Rept 50-346/98-03, Designated as Inspector follow-up Item 50-346/97-201-10 ML20196G1251999-06-23023 June 1999 Responds to NRC RAI Re GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants ML20196E5321999-06-17017 June 1999 Forwards Addl Info Re Relief Request RR-A16 to Support NRC Approval of Relief Request ML20195K2751999-06-16016 June 1999 Forwards Safety Evaluation Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves ML20196A6601999-06-16016 June 1999 Forwards Master Decommissioning Trust Agreements Revised After 1990 for Ohio Edison Co,Cleveland Electric Illuminating Co,Toledo Edison Co & Pennsylvania Power Co Re Bvnps,Units 1 & 2,DBNPS,Unit 1 & Perry Unit 1 ML20195F9071999-06-10010 June 1999 Forwards Application for Amend to NPF-3,changing Tech Specs 3/4.6.4.4, Hydrogen Purge Sys, TS 3/4.6.5.1, Shield Bldg Emergency Ventilation Sys & TS 3/4.7.6.1, Crevs ML20195F8851999-06-0707 June 1999 Withdraws 950929 License Amend Application,Proposing Mod to Allowable as-found Pressure Lift Setting Tolerance of Two Pressurizer Code Safety Valves ML20207G0751999-06-0707 June 1999 Forwards Insp Rept 50-346/99-04 on 990323-0513.Violations Occurred & Being Treated as non-cited Violations,Consistent with App C of Enforcement Policy 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217N2321999-10-15015 October 1999 Requests NRC Approval to Use Alternative to Requirements of 10CFR50.55a(f)(4)(ii).Licensee Requests Extension to Specified Schedule for Implementing Updates to IST Program PY-CEI-NRR-2438, Informs That DBNPS & Pnpp Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl1999-10-14014 October 1999 Informs That DBNPS & Pnpp Staffs Have Modified or Withdrawn Several of Positions Proposed within Re Request for Approval of Qap.Revised Positions Encl ML20216J6701999-09-24024 September 1999 Forwards Post Examination Documentation for Written Operator Initial License Examination Administered at Davis-Besse Nuclear Power Station on 990920.Without Encls 05000346/LER-1998-001, Forwards Rev 1 for LER 1998-001,which Updates Corrective Actions & Revises Completion Date Re Implementation of Changes to Plant Emergency Operating Procedure.List of Commitments Attached1999-09-0909 September 1999 Forwards Rev 1 for LER 1998-001,which Updates Corrective Actions & Revises Completion Date Re Implementation of Changes to Plant Emergency Operating Procedure.List of Commitments Attached ML20216E5961999-09-0707 September 1999 Forwards Application for Amend to License NPF-3,revising Tech Specs 3/4.3.2.1,safety Features Actuation Sys Instrumentation & Associated Bases 3/4.3.1 & 3/4.3.2,reactor Protection Sys & Safety Sys Instrumentation ML20211K6611999-08-30030 August 1999 Forwards Copies of Operator License Renewal Applications for Individuals Listed.Operators Have Successfully Completed Appropriate Operator Requalification Training Program at Dbnps.Without Encls ML20211K6681999-08-30030 August 1999 Forwards Copies of Certified Personal Qualification Statement - Licensee (NRC Form 398) for Operator Candidates Listed Below.Without Encls ML20211H0201999-08-25025 August 1999 Forwards semi-annual FFD Rept for 990101-0630 for DBNPS, Unit 1,IAW 10CFR26.71(d) ML20211G3911999-08-20020 August 1999 Forwards Update to Estimated Info for Licensing Action Requests Through 010930,re Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates PY-CEI-NRR-2411, Informs That Firstenergy Nuclear Operating Co Has Developed Corporate QA Program Manual for Davis-Besse Nuclear Power Station & Perry Nuclear Power Plant,As Discussed on 990318 Between Util & Nrc.Revised USAR Pages,Encl1999-08-19019 August 1999 Informs That Firstenergy Nuclear Operating Co Has Developed Corporate QA Program Manual for Davis-Besse Nuclear Power Station & Perry Nuclear Power Plant,As Discussed on 990318 Between Util & Nrc.Revised USAR Pages,Encl ML20211J9201999-08-13013 August 1999 Urges NRC to Find Funds for Stockpiling Radiation Pills for Residents Living Near Plant ML20210T1061999-08-12012 August 1999 Forwards Preliminary NRC Forms 398 & 396 for Listed Candidates,Per Operator License Exam Scheduled for Week of 990913.Encl Withheld ML20210S6071999-08-11011 August 1999 Provides Final Response to NRC RAI Re GL 98-01, Y2K Readiness of Computer Systems at Npps 05000346/LER-1998-009, Forwards LER 98-009-01,IAW 10CFR50.73(a)(2)(ii)(B). Commitments Made by Util Are Encl1999-08-0606 August 1999 Forwards LER 98-009-01,IAW 10CFR50.73(a)(2)(ii)(B). Commitments Made by Util Are Encl ML20210H0491999-07-28028 July 1999 Forwards Application for Amend to License NPF-3,revising TS 3/4.7.5.1, Ultimate Heat Sink, to Allow Plant Operation in Modes 1-4 with Water Temp Less than or Equal to 90 F ML20210G5521999-07-28028 July 1999 Provides Addl Response to 980923 OL Licensing Exam Rept 50-346/98-301 Re OL Exam Administered in Aug 1998.Results of Root Cause Investigation & Corrective Actions,Discussed ML20210G3831999-07-27027 July 1999 Forwards Application for Amend to NPF-3,changing TSs 6.4, Training, 6.5.2.8, Audits, 6.10, Record Retention, 6.14, Process Control Program & 6.15, Odcm ML20210G7151999-07-26026 July 1999 Forwards Application for Amend to License NPF-3,revising TSs 3/4.3.3.1, Radiation Monitoring Instrumentation, 3/4.3.3.2, Instrument - Incore Detectors & 3/4.3.3.9, Instrumentation - Waste Gas Sys Oxygen Monitor ML20210G5151999-07-26026 July 1999 Forwards Application for Amend to License NPF-3,revising Tech Specs for Implementation of 10CFR50,App J,Option B for Type B & C Containment Leakage Rate Testing ML20210G3211999-07-26026 July 1999 Forwards Written OL Exam & Supporting Matl for Exam to Be Administered at DBNPS During Week of 990913.Listed Encls Withheld from Public Disclosure Until After Exam Complete ML20210G4391999-07-26026 July 1999 Forwards Application for Amend to License NPF-3,revising Tech Specs 3/4.3.2.1, Safety Features Actuation Sys Instrumentation, & Associated Bases 3/4.3.1 & 3/4.3.2, Reactor Protection Sys & Safety Sys Instrumentation ML20211P3071999-07-26026 July 1999 Forwards Final Rept for 990504 Biennial Radiological Emergency Preparedness Exercise for David-Besse Power Station.No Deficiencies Identified for Any Jurisdiction During Exercise 05000346/LER-1998-012, Forwards LER 98-012-01,which Is Being Submitted to Provide Addl Info Re 981018 Occurrence.Commitment List Attached1999-07-0707 July 1999 Forwards LER 98-012-01,which Is Being Submitted to Provide Addl Info Re 981018 Occurrence.Commitment List Attached ML20209C3981999-07-0101 July 1999 Responds to NRC Re Violations Noted in Insp Rept 50-346/98-21.Corrective Actions:Developed Rev to Boric Acid Control Program & Work Process Guideline on Plant Leakage ML20209B5821999-06-24024 June 1999 Provides Justification for Rev to Completion Date for One of Insp follow-up Items Cited in Insp Rept 50-346/98-03, Designated as Inspector follow-up Item 50-346/97-201-10 ML20196G1251999-06-23023 June 1999 Responds to NRC RAI Re GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants ML20196E5321999-06-17017 June 1999 Forwards Addl Info Re Relief Request RR-A16 to Support NRC Approval of Relief Request ML20196A6601999-06-16016 June 1999 Forwards Master Decommissioning Trust Agreements Revised After 1990 for Ohio Edison Co,Cleveland Electric Illuminating Co,Toledo Edison Co & Pennsylvania Power Co Re Bvnps,Units 1 & 2,DBNPS,Unit 1 & Perry Unit 1 ML20195F9071999-06-10010 June 1999 Forwards Application for Amend to NPF-3,changing Tech Specs 3/4.6.4.4, Hydrogen Purge Sys, TS 3/4.6.5.1, Shield Bldg Emergency Ventilation Sys & TS 3/4.7.6.1, Crevs ML20195F8851999-06-0707 June 1999 Withdraws 950929 License Amend Application,Proposing Mod to Allowable as-found Pressure Lift Setting Tolerance of Two Pressurizer Code Safety Valves ML20207F4231999-06-0202 June 1999 Forwards Rev 1 to DBNPS Emergency Preparedness Evaluated Exercise Manual 990504, IAW 10CFR50.4.NRC Evaluated Exercise Has Been Rescheduled for 991208,since NRC Did Not Evaluate 990504 Exercise ML20207E2521999-05-28028 May 1999 Forwards Rev 18,App A,Change 1 to Davis-Besse Nuclear Power Station,Unit 1,industrial Security Plan IAW Provisions of 10CFR50.54(p).Encl Withheld,Per 10CFR73.21 ML20207E9561999-05-28028 May 1999 Forwards Update to NRC AL 98-03,re Estimated Info for Licensing Activities Through Sept 30,2000 ML20207E7801999-05-21021 May 1999 Forwards Application for Amend to License NPF-3,allowing Use of Expanded Spent Fuel Storage Capacity.Proprietary & non- Proprietary Version of Rev 2 to HI-981933 Re Cask Pit Rack Installation Project,Encl.Proprietary Info Withheld ML20206N0231999-05-0606 May 1999 Forwards License Renewal Applications for Davis-Besse Nuclear Power Station,Unit 1 for ML Klein,Cn Steenbergen & CS Strumsky.Without Encls ML20206D2421999-04-28028 April 1999 Forwards Combined Annual Radiological Environ Operating Rept & Radiological Effluent Release Rept for 1998. Rev 11, Change 1 to ODCM & 1998 Radiological Environ Monitoring Program Sample Analysis Results Also Encl PY-CEI-NRR-2382, Forwards 1998 Annual Rept for Firstenergy Corp, for Perry Nuclear Power Plant & Davis-Besse Nuclear Power Station.Form 10-K Annual Rept to Us Securities & Exchange Commission for FY98 Also Encl1999-04-21021 April 1999 Forwards 1998 Annual Rept for Firstenergy Corp, for Perry Nuclear Power Plant & Davis-Besse Nuclear Power Station.Form 10-K Annual Rept to Us Securities & Exchange Commission for FY98 Also Encl ML20206B8831999-04-17017 April 1999 Forwards 1634 Repts Re Results of Monitoring Provided to Individuals at Davis-Besse Nuclear Power Station During 1998,per 10CFR20.2206.Without Repts ML20205K3871999-04-0707 April 1999 Forwards Copy of Application of Ceic,Oec,Ppc & Teco to FERC, Proposing to Transfer Jurisdictional Transmission Facilities of Firstenergy Operating Companies to American Transmission Sys,Inc.With One Oversize Drawing ML20205K5641999-04-0707 April 1999 Forwards Response to NRC 980415 RAI Re GL 96-06, Assurance of Equipment Operability & Ci During Design-Basis Accident Conditions. Rept FAI/98-126, Waterhammer Phenomena in Containment Air Cooler Swss, Encl ML20205J1171999-03-29029 March 1999 Forwards Rev 1 to BAW-2325, Response to RAI Re RPV Integrity, Per GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity. Rev Includes Corrected Values in Calculations PY-CEI-NRR-2377, Submits Decommissioning Repts for Bvps,Units 1 & 2,Davis- Besse Nuclear Power Station,Unit 1 & Perry Nuclear Power Plant,Unit 1,per 10CFR50.75(f)(1)1999-03-29029 March 1999 Submits Decommissioning Repts for Bvps,Units 1 & 2,Davis- Besse Nuclear Power Station,Unit 1 & Perry Nuclear Power Plant,Unit 1,per 10CFR50.75(f)(1) ML20205F5961999-03-27027 March 1999 Forwards Comments on Preliminary Accident Sequence Percursor (ASP) Analysis of 980624 Operational Event at Dbnps,Unit 1, as Transmitted by NRC Ltr ML20205D4791999-03-26026 March 1999 Forwards Rept Submitting Results of SG Tube ISI Conducted in Apr 1998.Rept Includes Description of Number & Extent of Tubes Inspected,Location & Percent wall-thickness Penetration for Each Indication of Imperfection ML20205L2031999-03-26026 March 1999 Submits Correction to Dose History of Tj Chambers.Dose Records During 1980-1997 Were Incorrectly Recorded Using Wrong Social Security Number.Nrc Form 5 Not Encl ML20205C7371999-03-25025 March 1999 Certifies That Dbnps,Unit 1,plant-referenced Simulator Continues to Meet Requirements of 10CFR55.45(b) for Simulator Facility Consisting Solely of plant-referenced Simulator.Acceptance Test Program & Test Schedule,Encl ML20205E3551999-03-19019 March 1999 Requests That Proposed Changes to TS 6.8.4.d.2 & TS 6.8.4.d.7 Be Withdrawn from LAR Previously Submitted to NRC ML20204J6361999-03-17017 March 1999 Forwards Firstenergy Corp Annual Rept for 1998 & 1999 Internal Cash Flow Projection as Evidence of Util Guarantee of Retrospective Premiums Which May Be Served Against Facilities PY-CEI-NRR-2375, Forwards List That Details Util Insurers,Policy Numbers & Coverage Limits for Two Power Plants,Per Requirements of 10CFR50.54(w)(3) Re Reporting of Property Insurance Coverage1999-03-15015 March 1999 Forwards List That Details Util Insurers,Policy Numbers & Coverage Limits for Two Power Plants,Per Requirements of 10CFR50.54(w)(3) Re Reporting of Property Insurance Coverage ML20204E6821999-03-12012 March 1999 Requests That Listed Changes Be Made to NRC Document Svc List for Davis-Besse Nuclear Power Station,Unit 1 1999-09-09
[Table view] Category:UTILITY TO NRC
MONTHYEARML20065D0491990-09-14014 September 1990 Forwards Operator & Senior Operator Licensing Exam Ref Matl for Exam Scheduled for Wk of 901112,per 900607 Request ML20065D4951990-09-14014 September 1990 Forwards Updated Exam Schedule for Facility,In Response to Generic Ltr 90-07, Operator Licensing Natl Exam Schedule ML20059K4681990-09-14014 September 1990 Provides Supplemental Info Re Emergency Response Data Sys (Erds).Data Transmitted by Util ERDS Will Have Quality Tag of 4 & Point Identification for ERDS Renamed ML20059G2341990-09-10010 September 1990 Provides Response to Request for Addl Info Re Interpretation of Tech Spec 3/4.7.10, Fire Barriers. Interpretation Is Implemented & Unnecessary Compensatory Measures Removed.List of Fire Barriers Inspected on One Side Only Encl ML20059G4961990-09-0606 September 1990 Submits Voluntary Rept of Svc Water HX Testing During Sixth Refueling Outage.Expected Flow Rates Not Achieved.Periodic Tests Developed to Check Efficiency of Containment Air Coolers ML20064A6271990-09-0606 September 1990 Requests That Requirement Date for Installation & Testing of Alternate Ac Power Source & Compliance w/10CFR50.63 Be Deferred Until Completion of Eighth Refueling Outage ML20028G8611990-08-28028 August 1990 Forwards Davis Besse Nuclear Power Station Semiannual Rept: Effluent & Waste Disposal,Jan-June 1990. ML20059D4121990-08-28028 August 1990 Forwards Second 10-Yr Interval Pump & Valve Inservice Testing Program ML20059D5521990-08-24024 August 1990 Forwards Semiannual Fitness for Duty Rept for Jan-June 1990 ML20059B5291990-08-23023 August 1990 Forwards Updated Fracture Mechanics Analysis of Hpi/Makeup Nozzle,Per 900510 Meeting W/Nrc.Util Believes That Addl Analysis to Assess Structural Integrity of Nozzle Using More Conservative Fracture Model Supports Previous Analysis ML20058Q3911990-08-16016 August 1990 Requests NRC Concurrence on Encl Interpretation & Technical Justification of Tech Spec 3/4.7.10, Fire Barriers ML20058P7801990-08-10010 August 1990 Advises of Intentions to Revise Testing Requirements for Fire Protection Portable Detection Sys at Plant & Functional Testing of auto-dialer & Telephone Line Subsys from Daily to Weekly Testing ML20063P9981990-08-0909 August 1990 Submits Supplemental Response to Insp Rept 50-346/89-21. Util Rescinds Denial & Accepts Alleged Violation ML20056A5341990-08-0303 August 1990 Confirms Electronic Transfer of Payment of Invoice I0942 Covering Annual Fee for FY90,per 10CFR171 ML20058M7791990-08-0303 August 1990 Forwards Rev 10 to Industrial Security Plan & Rev 6 to Security Training & Qualification Plan.Revs Withheld ML20058L1821990-08-0101 August 1990 Forwards Davis-Besse Dcrdr Human Engineering Discrepancy Repts 1988 Summary Addendum 1,Vol 1, Per NRC Audit Team Request ML20056A8341990-07-23023 July 1990 Forwards Revised Monthly Operating Rept for June 1990 for Davis-Besse Nuclear Power Station Unit 1 ML20055H4601990-07-20020 July 1990 Discusses Resolution of Draft SER Open Item on Voluntary Loss of Offsite Power.Util Preparing License Amend Request Per Generic Ltrs 86-10 & 88-12 to Relocate Fire Protection Tech Specs & Update Fire Protection License Condition ML20055F9681990-07-17017 July 1990 Forwards Application for Amend to License NPF-3,adding Centerior Svc Company as Licensee in Facility Ol.Change Allows for Improved Mgt Oversight,Control & Uniformity of Nuclear Operations ML20055F8561990-07-17017 July 1990 Discusses Util Planned Activities Re Instrumented Insp Technique Testing Performed at Facility in View of to Hafa Intl.Relief Requests Being Prepared by Util for Sys on Conventional Hydrostatic Testing ML20044B3001990-07-12012 July 1990 Provides Written Confirmation of Util Electronic Transfer of Funds to NRC on 900711 in Payment of Invoice Number I1050 ML20044B1841990-07-10010 July 1990 Requests Approval of Temporary non-code Repair & Augmented Insp of Svc Water Piping,Per 900626 Telcon ML20055D9701990-06-29029 June 1990 Provides Written Confirmation of Util Electronic Transfer of Funds for Payment of Invoice 0111 Covering Insp Fees for 890326-0617 ML20043H5291990-06-14014 June 1990 Forwards Plans Re Reorganization & Combining of Engineering Assurance & Svc Program Sections ML20055C7521990-06-14014 June 1990 Responds to NRC Bulletin 89-002, Potential Stress Corrosion Cracking of Internal Preloaded Bolting in Swing Check Valves & Justification for Alternate Insp Schedule for One Valve. No Anchor Darling Swing Check Valves Installed at Plant ML20055F2261990-06-14014 June 1990 Forwards 1990 Evaluated Emergency Exercise Objectives for Exercise Scheduled for 900919 ML20043G5661990-06-14014 June 1990 Forwards Rev 9 to Industrial Security Plan.Rev Withheld (Ref 10CFR73.21) ML20043G7811990-06-12012 June 1990 Forwards Info Re Implementation of NUREG-0737,Item II.F.2, Inadequate Core Cooling Instrumentation, Per NRC 900214 Safety Evaluation.Item II.B.1 Issue Re Reactor Vessel Head Vent Also Considered to Be Closed ML20043F6091990-06-11011 June 1990 Forwards Util Comments on NRC Insp Rept 50-346/90-12, Per 900601 Enforcement Conference Re Core Support Assembly Movement & Refueling Canal Draindown.Refueling Canal Draindown Procedure Provides Specific Draining Instructions ML20043E1301990-06-0101 June 1990 Withdraws 870831 & 890613 Applications to Amend License NPF-3.Changes Requested Addressed by Issuance of Amend 147 or Can Now Be Made as Change to Updated SAR Under 10CFR50.59 ML20043D5601990-05-31031 May 1990 Forwards Application for Amend to License NPF-3,revising Tech Spec 3/4.6.4.1, Combustible Gas Control - Hydrogen Analyzers. Request Consistent W/Nrc Guidance,Generic Ltr 83-37,dtd 831101,NUREG-0737 Tech Specs & Item II.F.1.6 ML20043D5691990-05-31031 May 1990 Forwards Application for Amend to License NPF-3,requesting Extension of Expiration Date of Section 2.H to Allow Plant Operation to Continue Approx 6 Yrs Beyond Current Expiration Date ML20043D1451990-05-31031 May 1990 Forwards Rev 11 to Updated SAR for Unit 1.Rev Updates Table 6.2-23 Re Containment Vessel Isolation Valve Arrangements ML20043D1621990-05-29029 May 1990 Documents Util Understanding of NRC Interpretation of Plant Tech Spec 3.7.9.1,Action b.2 Re Fire Suppression Water Sys, Per 891206 Telcon.Nrc Considered Electric Fire Pump Operable Provided Operator Stationed to Open Closed Discharge Valve ML20043C2331990-05-25025 May 1990 Forwards Summary of 900510 Meeting W/B&W & NRC in Rockville, MD Re Hpi/Makeup Nozzle & Thermal Sleeve Program.List of Attendees & Meeting Handout Encl ML20043B1701990-05-18018 May 1990 Forwards Revised Exemption Request from 10CFR50,Section III.G.2,App R for Fire Areas a & B,Adding Description of Specific Limited Combustibles That Exist Between Redundant Safe Shutdown Components in Fire Area a ML20043A5441990-05-16016 May 1990 Discusses Status of Safety & Performance Improvement Program Portion of B&W Owners Group EOP Review Project ML20043A2311990-05-11011 May 1990 Responds to Violation Noted in Insp Rept 50-346/90-08. Corrective Actions:Results of Analysis of Radiological Environ Samples & Radiation Measurements Included in 1989 Annual Radiological Environ Operating Rept ML20043A4901990-05-10010 May 1990 Forwards Summary of Differences Between Rev 5 to Compliance Assessment Rept & Rev 1 to Fire Area Optimization,Fire Hazards Safe Shutdown Evaluation, Vols 1-3.Rept Demonstrates Compliance W/Kaowool Wrap Removal ML20042F9801990-05-0404 May 1990 Provides Written Confirmation of Util Electronic Transfer of Payment of Invoice Number 10716 to Cover Third Quarterly Installment of Annual Fee for FY90 ML20042F5781990-05-0303 May 1990 Provides Status of Hpi/Makeup Nozzle & Thermal Sleeve Program.Nrc Approval Requested for Operation of Cycle 7 & Beyond Based on Program Results.Visual Insp of Thermal Sleeve Identified No Thermal Fatique Indications ML20042F0951990-04-30030 April 1990 Responds to Violations Noted in Insp Rept 50-346/90-02. Corrective Actions:Maint Technician Involved in Tagging Violation Counseled on Importance of Procedure Adherence W/ Regard to Personnel Safety ML20042F0841990-04-27027 April 1990 Responds to Violations Noted in Insp Rept 50-346/89-201 for Interfacing Sys LOCA Audit on 891030-1130.Corrective Actions:Plant Startup Procedure Will Be Revised Prior to Restart from Sixth Refueling Outage ML20042E7311990-04-27027 April 1990 Forwards Application for Amend to License NPF-3,deleting 800305 Order Requiring Implementation of Specific Training Requirements Which Have Since Been Superseded by INPO Accredited Training Program ML20042F1961990-04-27027 April 1990 Informs of Adoption of Reorganization Plan Re Plants on 900424.Reorganization Will Make No Changes in Technical or Financial Qualifications for Plants.Application for Amends to Licenses Adding Company as Licensee Will Be Submitted ML20043F7261990-04-20020 April 1990 Requests Exemption from 10CFR55.59(a)(2) to Permit one-time Extension of 6 Months for Reactor Operators & Senior Reactor Operators to Take NRC 1990 Requalification Exam. Operators Will Continue to Attend Training Courses ML20042E7091990-04-17017 April 1990 Forwards Annual Environ Operating Rept 1989 & Table 1 Providing Listing of Specific Requirements,Per Tech Spec 6.9.1.10 ML20012F5091990-04-0303 April 1990 Forwards Completed NRC Regulatory Impact Survey Questionnaire Sheets,Per Generic Ltr 90-01 ML20012F6001990-04-0202 April 1990 Submits Supplemental Response to Station Blackout Issues,Per NUMARC 900104 Request.Util Revises Schedule for Compliance W/Station Blackout Rule (10CFR50.63) to within 2 Yrs of SER Issuance Date ML20012E0181990-03-22022 March 1990 Forwards Application for Amend to License NPF-3,changing License Condition 2.C(4) Re Fire Protection Mods to Fire Extinguishers,Fire Doors,Fire Barriers,Fire Proofing,Fire Detection/Suppression & Emergency Lighting 1990-09-06
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%me EDISON Docket No. 50-346 Roano P Cnotu License No. NPF-3 0,*i?"**
1419)259 S221 Serial No. 826 June 16, 1982 Mr. John F. Stolz, Director Nuclear Reactor Regulation Operating Reactors Branch No. 4 Division of Operating Reactors United States Nuclear Regulatory Commission Washington, D.C. 20555
Dear Mr. Stolz:
Your letter dated March 8, 1982 (Log No. 918) requested additional information concerning Masonry Wall Design; IE Bulletin 80-11, as it relates to Davis-Besse Nuclear Power Station Unit No. 1. Toledo Edison made a partial response in a May 3, 1982, submittal (Serial No. 814).
Additional information and clarifications were provided in a meeting at Becthel, Gaithersburg on May 27, 1982, between NRC staff reviewers, Bechtel and Toledo Edison personnel.
The attachment to this letter provides the same information provided in our May 3,1982, submittal with additional information and clarifications added as indicated by change bars in the right margin. Part of the additional information was discussed in the May 27, 1982, meeting and is being provided in a formal manner at this time. This submittal completes our response to your March 8, 1982, request for additional information, except for Question 15. The information requested in Question 15 will be provided in early July 1982.
Very truly yours, l W RPC:LDY: lab g)/
1 attachment cc: DB-1 NRC Resident Inspector 8206220357 820616 gDRADOCK 05000346 PDR THE TOLEDO EDISON COMPANY EDISON PLAZA 300 MADISON AVENUE TOLEDO. OH!O 43652
Dock:t No. 50-346 ,
Licensq No. NPF-3 ,
Serial No. 826 June 16, 1982
,,) RESPONSE TO NRC QUESTIONS MASONRY WALL DESIGN REVISION 1
- 1. Question -
Table 1 (2) refers only to the edge conditions as indicated in the masonry wall d rawi ng s . Provide the boundary conditions assumed for the analysis.
Response
For CtU walls supported at the top and bottom edges, vertical strips have been analyzed assuming the top and bottom edges are pinned. This is conservative because the calculated natural f requency of the CMU wall, using this assumption, will be lower than the calculated natural frequency based on fixed or partially fixed connections. The various floor response spectra employed a constant response equal to the peak response on the low frequency side of the peak. This results in determining f rom the respective floor response curve, the uppe r bound seismic acceleration to be applied perpendicular to the plane of the CMU wall. In addition to uppe r bound seismic loads being applied to the CMU wall, the calculated moments used in stress calculations will be greater for the assumption of pinned edges versus the assumption of fixed or partially fixed edges, resulting in conservative stress calculations.
For CMU walls with short horizontal spans, supported on both vertical edges, horizontal strips have been analyzed assuming the vertical edges are pinned. This is conservative based on the above statements.
For CMU walls f ree at the top, the bottom connections are assumed fixed, with the stresses in the masonry and the connections analyzed accordingly.
- 2. Question Indicate how the ef fects of higher modes were considered in cases where the analysis was based on the " block wall" program, which includes only three modes.
Res ponse The computer code " BLOCK WALLS" was verified by comparison with a solution considering nine modes. The comparison showed the computer code " BLOCK WALLS" produced a seismic moment due to flexure that was conservative by 1.1 percent versus the 9 mode solution.
- 3. Ques tion Indicate whether any of the walls was analyzed as a plate, with special ref erence to walls having cut-outs.
Response ,
Some CMU walls were analyzed using the computer code BSAP. Large openings, such as doors, were naturally included as part of the finite elenent mesh. In general openings larger that the selected mesh size were included in the model, openings .
I
l
. i%
smaller were not, with the added consideration that the smaller opening sizes do not af fect the structural integrity of the wall.
! The mesh size selected was influenced by consideration of the height and length of the wall, location and namber of applied loads, size and, therefore, subsequent I cost of execution of the computer program created, and the spacing of both verti-l cal and horizontal reinforcing.
For a summary of wall geometry and openings, see Table 1. Rectangular openings shown on the drawings at the time the walls were constructed are shown per the blockout schedules to have trim bars around the openings.
- 4. Question Explain why the Table V (2) factors for operating basis earthquake (OBE) and wind load are 1.0, while the plant FSAR specifies a factor of 1.25 for these loads.
Response
Analysis of CMU walls used working stress criteria for which "SEB Interim Criteria for Safety-Related Masonry Wall Evaluation", July 1981, specifies a factor of 1.0 for both operating basis earthquake and wind. The factor of 1.25 in the FSAR is based on ultimate strength criteria.
- 5. Question
! Indicate how equipment weight was considered in the analysis of the masonry walls.
Standard Review Plan (SRP), Section 3.7.2 (7), suggests that the equipment weight should be multiplied by a factor of 1.5 times the peak floor acceleration.
Res po nse The equipment weight multiplied by a factor of 1.5 times the peak floor accelera-j tion is an equivalent static load method of analysis which may be used in lieu
- of a dynamic method. All CMU walls which were analyzed used a dynamic method j
including actual dead weight of the wall plus the dead weight of the equipment.
- 6. Ques tion With reference to Section 7.1, Appendix E (2), use the envelope of the floor spectra or provide justification for using the average spectral acceleration.
Response
The evaluations herein demonstrate that the use of the average floor accelera-tion response spectra to calculate the response of the wall panel is appropriate. ;
For the purposes of this evaluation, the seismic response of a simply-supported, uniform beam simulating a strip of the wall panel with unit width is considered, .
I as shown in Figure 1:
i '
_3_
i Use of Average Spectra The quation. of motion of an undamped, simply-supported bea$ can be written in terms of the total displacement with respect to some fixed' reference axis as:
m + EI =0 (1) it' bx j where m and EI are the mass density and flexural rigidity of the beam. Denote the seismic excitations at the ends of the beam as aU and U b . Then the total displacement u(x,t) can be expressed in terms of the twa seismic motions and' the relative displacement to the seismic motions as: ' '
i u(x,t) = (x/L) Ub + (1 x/L) Ua + r(x,t) (2) where L is the length of the beam. The relation expressed by the' above equation y is shown in Figure 2. The relative displacement r(x,t) must satisfy the following simply supported conditions:
r(o,t) = r (L,t) = 0 (3)
YT a -
T -
(4)
Y)d(X80 %X g X : L-Upon substitution of Equation 2 into Equation 1, the bquation of motion in terms of relative displacement r(x,t) can be expressed as:
m
[p + EI h y - = .. ..
m(1 - x/L)U (5) m(x/L) Ub N hX The eigen-f unction solutions for the homogeneous equation associated with Equation 5 that satisfy the boundary conditions specified by Equations 3 and 4 are:
! sin n T x , n = 1, 2, 3, ... ,
i L I
I
.> i' ,
and the corresponding frequencies of vibration are:
1 E'$.
. W^< 1 h . }(1, 4- - n = 1, 2, 3, ... (6)
/mL !
So, the solution of Equation 5 can be expressed as:
4
' bh b) '
Sid ha( (7)
Substitute Equation 7 into Equation 5, and mutiply the latter by sin h'h W[L and then integrate it with respect to x.over the full length of the beam; the equation of motion can be transformed into modal equations of motion as:
1W +cM w,t(/u.,+u %
g s
n = 1, 3, 5, ...
(8a) and Y hT n = 2, 4, 6, ...
where [n = participation factor
= 4 ny (9)
If damping in the form of modal damping ratio is included, Equations 8a and 8b become :
i .. .
A + 2 % &,0.s + e'@w
/ h 4. h g n = 1, 3, 5, ...
\ 1 (10a) and g Y W w i O n = 2, 4, 6 ... (10b) i
..n ..
= y" f Va.- Ob s '2.
t
'5-Where h is the damping ratio of the nth mode.
Equation 10a. means that the odd-number modes which are symmetrical abcut the mid-span of the beam will be excited by the average of the two seismic excitations; while equation 10b means that the even number modes which are antisymmetrical about the mid-span of the beam will be excited by half of the dif ference between the two seismic excitations.
Expressing the maximur rodal displacement response in Eq'ntion 10a and 10b in terms of absolute acceleration response spectra gives: ,
I N , r g,, (p w , Q g (,g c3 g*iIw.ty. 4 !+i ,
gg gg j
~
E 4 m L' _
%.C. k Owl + % Osw M
#trar 1
- (11) n = 1, 2, 3, ...
This illustrates that the use of the average of two floor acceleration response spe ct ra to calculate the modal response of a wall panel is appropriate.
- 7. Question With reference to Table II (2), indicate possible variations in the value E for masonry, and determine the actual value of E such that the spectral curve provides a conservative estimate for acceleration.
Res ponse A single value of E was used in the analysis of the CMU walls. Specifically, E was taken equal to 1000 f'n per the !!niform Building Code, 1970 Edition, Volume 1, Table No. 24-H, page 170 (also refer to ACI 531-79, Table 10.1). The various floor response spectra employed a constant response equal to the peak response on the low f requency side of the peak. The value of E described above coupled with the modified frequency response spectrum results in conservative stress calculations.
- 8. Ques tio n With reference to page 8 of Reference 2, provide sample calculations to illustrate that single wythe analysis of multiple wythe walls is conservative.
Response
All wythes in a multiple wythe CMU wall were assumed to respond as single wythe walls because of the dif ficulty in verifying the adequacy of the collar joint I between the wythes. This was assumed to be conservative when using the re-
t evaluation criteria and the objective of this response is to validate the degree of conse rvatism.
Two double wythe CMU walls (walls 1177 and 2107) were selected to compare the results obtained when computing the response as single wythe versus the response as double wythe using the re-evaluation criteria. In using the re-evaluation criteria, the two walls were assumed to have pinned supports at the top and bottom for the analysis of vertical spans. As a consequence, no forces are induced in the wall due to out-of plane drif t. Wall 1177 is 32 inches long, 87 inches high and consis ts of two wythes of eight inch wide units with 8" grout in between. Wall 2107 is 48 inches long, 217 inches high and consists of two wythes of 12" wide units with 12" grout in be tween.
Results The results of the analyses performed f or the two walls are given in Tables 2 and 3.
Table 2 conpares the frequencies of each wall acting either as a single or double wythe wall. Table 3 compares the maximum seismic moment and the tensile steel stress ratio for each wall acting either as a single or double wythe wall.
Discussion of Results From the results presented in Table 2, it is clear that the single wythe assumption 1 is conservative with respect to frequency shif t. The fundamental or first mode f requency of double wythe wall 1177 is approximately five times that of the single wythe assumption. The fundamental or first mode frequency of double wythe wall 2107 is approximately eight times that of the single wythe assumption.
Fron the results presented in Table 3 it is clear that the single wythe assump-tion is conservative with respect to seismic moments and tensile steel stress ratios also. The seismic moments on single wythe walls are considerably greater than those for double wythe walls. Correspondingly, the tensile steel stress ratios for double wythe walls are nuch lower than for single wythe walls.
- 2. olusions Two 5 alls were selected to demonstrate that the use of the single wythe assumption for rtitiple wythe walls results in a conservative evaluation with respect to frequency shif t and out of plane load considerations. The results indicate that the frequencies of the double wythe walls are greater than those of the single wythe walls. Therefore, f rom f requency shif t considerations the use of the single wythe assumption is conservative. The results also indicate the seismic moments and the tensile steel stress ratios are much smaller for the double wythe walls compared to the single wythe walls.
The single wythe assumption applied to multiple wythe CMU walls is therefore conservative for the CMU wall re-evaluation criteria.
- 9. Ques tio n .
l It is the NRC's position that the energy balance technique and the arching theory I should not be used in the absence of conclusive evidence of their validity as applied to masonry structures. With reference to Table 1 (2), explain the following points:
f L -7
- a. Provide sample calculations to show the procedure used to determine the ductility ratio of walls and explain the effect of wall boundary conditions on this. ratio.
- b. Explain why the ductility ratios for several walls are less than unity even _though the working stresses have been exceeded.
- c. Explain how a ductile mode of failure of the masonry walls can be guaranteed since it depends on several factors, such as the amount and distribution of reinforcements and the anchorage provided.
- d. Explain how wall deflections are estimated for specific ductility ratios.
Res ponse
- a. The ductility of walls is calculated by the following equations:
2 AA. = 1/2 u.1+Ma)!
nr .
My = Fy Ier nd where: JA,= ductility ratio Ma = applied moment, including seismic Fy = yield stress of reinf orcing bar Icr = cracked moment of inertia n = modular ratio d = distance from neutral axis to reinforcing bar Example : Assume a 12" thick, totally grouted wall My = 40 k/in x 275 in /ft.
20 x 6.99 in.
= 78.68 in-k/ft.
Ma = 109.69 in-k/f t. (Output from " BLOCK WALLS")
A). = 1/2 1 + 109.692 78.68
~
= 1.47 For ef fects of assumed wall boundary conditions on calculated moments and the resulting ef fect on the ductility ratio, see the response to Question #1.
- b. A ductility ratio less than unity represents a stress in the reinforcing har between the allowable and yield.
- c. Reference,9 indicates that CMU walls with poured-in place concrete columns and bond beams act as flexible structures, even when the design and construction is poor. This observation was based on actual structures located within 20 miles of the epicenter of an earthquake with a magnitude of 7.5 on the Richter scale.
Reference 10 indicates considerable ductility where the reinforcement ratio is 0.15% or greater. All CMU walls analyzed for Davis-Besse Unit I have reinforce-ment ratios which exceed this value. Reference 11 indicates that a reinforced ,
CMU wall is a ductile structure provided a flexural type of failure will occur with tensile yielding of the reinf orcing steel. All CMU walls which were analyzed met this criteria for loads applied perpendicular to the plane of the wall.
- d. Wall deflections are calculated by the following equation:
doax. = d x h xg x 2 fs where: f( = deflection, f rom " BLOCK WALLS" f s = stress of reinforcing bar, from " BLOCK WALLS" 2 = factor of safety
- 10. Question With reference to Table IV (2), specify the allowable stresses for shear (shear l walls and flexural members where reinforcenent takes the shear), tension parallel to the bed joint, and tension normal to the bed joint.
Res po nse No CMU walls were provided to resist building shear or moments due to a seismic event. Therefore, no CMU walls have been evaluated as shear walls. In no case was it necessary to resist shear forces with reinforcenent, because the masonry shear stress for each evaluated CMU wall was less than 0.02 f'm. All CMU walls which were evaluated contain steel tension reinforcement to resist tension forces normal or parallel to the bed joint. Therefore, the assumed allowable masonry tensile stresses normal or parallel to the bed joint was zero for the evaluation perf ormed in response to IE Bulletin 80-11.
The top edge detail for CMU walls f astened to the floor above contains a minimum of one inch thick expansion joint material. Therefore, the in plane building 1 shear will be minimal and the in plane shear experienced by any CMU wall will be due to the weight of the wall plus attachments accelerated due to a seismic event.
- 11. Question '
With reference to Table IV (2), justify the maximum value of 1260 si specified for allowable stress in axial compression.
q . .
l '.
Respons e The maximum allowable axial compressive stress of 1200 psi is given in the Uniform Building Code, 1970 Edition, Volume 1, Section 2418, page 158, and corresponds to a f' , of 6000 psi. The values of f'm established f or Davis-Besse Unit 1 are 1500 psi for reinforced, completely grouted hollow or solid units and 1350 psi for reinforced, partially grouted hollow or ungrouted hollow units. The maximum allowable masonry compressive stresses for Davis-Besse Unit 1 are 300 psi and 270 psi, res pectively.
- 12. Ques tion With reference to the proposed allowables for factored loads in Table IV (2),
justify the increase factors of 3.17 for bearing,1.5 for masonry shear, 1.67 for reinforcement shear, and 1.33 for bond. The SEB criteria (4) propose 2.5 for bearing, 1.3 for masonry shear, and 1.5 for reinforcement shear.
Res ponse The working stress allowables of Table IV are from the Uniform Building Code, 1970 Edition as referenced in the FSAR. The ultimate stress allowables are based on ACI 531-79, as recommended by the "SEB Interim Criteria for Safety-Related Masonry Wall Evaluation", July 1981 multiplied by an increase factor.
The increase factors in the question result from comparing the ultimate stress allowables to the working stress allowables.
The increase factor based on ACI 531-79 for ultirate bearing stress is 2.5 (0.62/0.25) for bearing on full area and 2.5 (0.95/0.375) for bearing on one-third area or less. This is in agreement with the SEB criteria.
The increase factor of 1.5 for masonry shear, 1.67 for reinforcement shear and 1.33 f or bond are intended for use with load combinations involving abnormal and/
or extreme environmental conditions. Since ACI Code allowable stresses (refer-
, ence ACI 531-79 Commentary, Chapter 10-1) are generally associated with a factor of safety of 3, the increase factors provide the following factors of safety aga ins t failure: 2.0 (3/1.5) for masonry shear, 1.8 (3/1.67) for reinforce-nent shear and 2.3 (3/1.33) for bond. It is our engineering judgement that
, these factors of safety are conservative and provide sufficient margin for abnormal and/or extrene conditions.
I i The only ultimate stress allowables used f ron Table IV were 0.85 f'm for masonry compressive stress due to flexure which was checked when the energy balance tech-nique was utilized and 0.9Fy for rebar tension stress which was used for load combinations containing safe shutdown earthquake. I
- 13. Question With reference to Table IV (2), justify the value for maxinum allowable compres-sion for -reinforcement since it exceeds the ACI 531-79 maximum of 24,000 psi (6).
o *
- 10 Res po nse The maximum allowable compressive stress for reinforcement is given in the Uniform Building Code, 1970 Edition, Volume 1, Section 2418, page 152. No CMU walls were evaluated utilizing reinforcement to resist compressive loads. This is accepted 3 practice and is conservative.
- 14. Question Provide details of proposed wall modifications with drawings, and indicate how these modifications will help to correct the wall deficiencies. Indicate how out of plane drift ef fects due to bracing are considered in the analysis.
Res po nse Details of the wall modifications were reviewed with the NRC in a meeting held on May 27, 1982.
Twelve CMU walls were modified by adding bracing members external to the walls, but the original wall boundary assumptions are not modified by introduction of these membe rs . The boundary conditions were originally assumed as pinned (see response to Question 1), except for cantilever walls and, therefore, no forces are induced into the CMU walls due to out of plane drif t. Differential displacement of the floors at the top and bottom of the walls may produce a stretching effect in the I reinf orcing bars located in the walls. For a typical wall, this has been calculated to produce a reinforcing har stress of less than 30 psi for an OBE seismic event and less than 50 psi for a SSE seismic event. The magnitude of these stresses is insignificant.
- 15. Ques tio n Provide a schedule for wall modifications.
Res ponse The schedule for wall modifications will be provided in early July, 1982. I l
I i
. _ ~ , . - , . . - - , . , _ _ . , , .,. -
W REFERENCES
- 1. IE Bulletin 80-11
" Masonry Wall Design" NRC, May 8,1980
- 2. R. P. Crouse (Toledo Edison Company)
Letter with attachments to J. G. Keppler (NRC)
November 4, 1980
- 3. R. P. Crouse (Toledo Edison Company)
Letter with attachments to J. G. Keppler (NRC)
September 29, 1981 4 Standard Review Plan, Section 3.8.4, Appendix A "Interin Criteria for Safety-Related Masonry Wall Evaluation" NRC, July 1981
- 5. Uniforn Building Code International Conference of Building Of ficials, 1979
- 6. ACI 531-79 and Conmentary ACI 531R-79
" Building Code Requrements for Concrete Masonry Structures" Anerican Concrete Institute, 1979
- 7. Standard Review Plan, Section 3.7.2
" Seismic System Analysis" NRC, July 1981
- 8. Uniforn Building Code, 1970 Edition, Volume 1
- 9. Structural Observations of the Kern Country Earthquake, ASCE Transact ions, Paper No. 277 7, August 1953, H. J. Degenkolb
- 10. The Influence of Horiz ontally Placed Reinf orcement on the Shear Strength and Ductility of Masonry Walls, 6th Inter-national World Conference on Earthquake Engineering,1977, Sheppard, et al
- 11. Reinf orced Masonry - Seisnic Behavior and Design, Bulletin New Zealand Society for Earthquake Engineering, Vol. 5, No. 4, December 1972, J.C. Scrivner
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TABLE 1
SUMMARY
OF OPENINGS f. MESH SIZES FOR CiU WALLS ANALY7.ED BY BSAP LENCrli X LENCril X LENCrli X LENGTil X LENGTil X llEIGilT OF llEIGilT OF llEIGitT OF llEIGHT OF llEIGilT OF WALL NO. Tile WALL Tile RECTANGULAR Tile RECTANGULAR LARCEST ROUND MESil SI7.E MESil SIZE OPENINGS INCLUDED OPENINGS EXCLUDED OPENING EXCLUDED (MAXIMUM) (MINIMUM) 6097 (1) 37 1/4" x 196 1/2" None None None 21 5/8" x 17 1/2" 21 5/8" x 14" 306D 143 1/4" x 156 7/8" 40" x 85" 10 1/4" x 17 5/8" 1/2" 0 16" x 17" 7 1/2" x 13" 338D 108" x 282" None None None 12" x 24" 12" x 21" 308D 116 1/2" x 282" None None None 309D 108 1/2" x 276 3/4" None None None 310D 107 3/8" x 278 1/4" None None None 3247 111 3/4" x 166 1/2" 12" x 22" None 12" 0 12 1/2" x 15 3/4" 12" x 11" 4026 137" x 222 1/2" 40 1/2" x 85 5/8" 10" x 15 1/4" 1" 0 18" x 22 1/8" 8 1/4" x 12" 18" x 12" -
2207 104" x 132" 20" x 12" None 2 1/2" 0 12" x 12" 12" x 10" 1 2217 120" x 132" 15" x 12" None Approx. 3" 9 15" x 12" 9" x 12" 6037 103 1/2" x 196 1/2 48" x 94" None 4" 0 12" x 17 1/2" 11 1/8" x 14" 4137 176 1/4" x 113 3/4" 33 1/4" x 41 1/4" None None 25 1/2" x 20 5/8" 12 3/4" x 13 3/4" 96 3/4" x 15" 5137 72 1/2" x 168" 17" x 30" None Approx. 1" 0 17" x 18 1/2" 13" x 14 1/2" 4046 120" x 222 1/2" 40" x 86" None Approx. 4" 0 17 5/16" x 23 3/16" 10" x 18" 30" x 18" 3357 274" x 176 5/8" None None None 30" x 20" 14" x 16 5/8" 3016 153" x 198" 18" x 12" 2 3/4" x 4 1/2" (2) Approx. 4" 0 19 1/2" x 24" 18" x 12" 3026 74" x 198" None None Approx. 3 1/2" 0 18 1/2" x 24" 18 1/2" x 12" 3036 156" x 198" 78" x 108" None Approx. 5" 0 26" x 20" 12" x 12" 12" x 32" 18" x 12" 3287 96" x 202" 40" x 86" None 10" 0 20" x 29" 14" x 21 1/2" 2297 216 3/4" x 176 3/8" None 19" x 8 1/4" Approx. 4" 0 18 3/4" x 18" 18" x 14 3/8" 21 5/8" x 15" 4036 161 1/4" x 222 1/2" 15" x 34" None Approx. 4" 0 17 1/2" x 17" 13 1/2" x 14 1/2" 17 1/2" x 14 1/2" 27" x 34"
TABLE I (Cont inued )
LENCril X LENGTil X LENGTil X LENGTH X LENGTil X llEIGilT OF llEIGitT OF llEIGitT OF HEIGHT OF llEIQlT OF WALL NO. Tile WALL TIIE RECTANGULAR RECTANGULAR LARGEST ROUND. MESH SIZE ,
MESH SIZE OPENINGS INCLUDED OPENINGS EXCLUDED OPENING EXCLUDED (MAXIMUM) (MINIMUM) 478 83 1/4" x 223" None None Approx. 5" 0 18" x 18 3/4" 14 1/4" x 18" 490 (3) 15" x 36" None None 4796 155 3/4" x 222 1/4" 40" x 93 3/4" 6" x 27" Approx. 5" 0 19" x 16" 13" x 8 3/4" 1 48865(3) 19" x 88 3/4" 4896, 13" x 31" y n 5207 198" x 147 1/4" 22" x 14 1/4" None Approx. 1"0 22" x 24" 22" x 13" 311D 122 1/4" x 277 3/8" None None None 12 1/4" x 24" 12 1/4" x 18" 3237 108" x 170" 60" x 102" None None 12" x 17" 12" x 17" 1068 125 1/2" x 96" None None Approx. 2" 0 16" x 16" 13 1/2" x 16" ,
Notes:
(1) Combined f or Analysis with Wall 6037.
(2) 4" Deep Recess for Electrical Box.
(3) Combined f or Analysis.
P
*/ TABLE 2 FREQUENCY OF WALLS WITH SIMPLY SUPPORTED
- , BOUNDARY CONDITIONS i
Wall No. Thickness Wythes Frequencies (HZ)
(Inches) _
1177 8 1 21.165, 81.339, 186.786 24 2 113.316, 448.576, 961.638 2107 12 1 3.349, 13.17, 28.258 36 2 29.35, 115.782, 247.58 TABLE 3 l MAXIMUM SEISMIC MOMENTS AND 1 i TENSILE STEEL STRESS RATIOS OF WALLS WITil SIMPLY SUPPORTED BOUNDARY CONDITIONS.
Wall No. Thickness Wythes Seismic Moment Tensile Steel
_ (Inches) (Inch Kips) Stress Ratio 1177 8 1 10.30 0.37*
24 2 3.80 0.03 l
2107 12 1 139.60 1.66**
36 2 49.0 0.11
** Wall acceptable by " Energy Balance Technique"
*' Revised f ron value reported in " Masonry Wall Re-Evalaution, Response to NRC IE Bulletin No. 80-11, Davis-Besse Nuclear Power Station Unit 1, November 4, 1980}}