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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217F9941999-10-15015 October 1999 Discusses FPC 970819 Request for Temporary Relief from ASME Code Section XI Requirements to Repair ASME Class 3 Nuclear Service & Decay Heat Sea Water System Piping.Forwards SE Containing Results of Staff Review ML20217J5171999-10-13013 October 1999 Informs That on 990930,NRC Staff Completed mid-cycle PPR of Plant,Unit 3 & Did Not Identify Any New Areas That Warranted More than Core Insp Program.Previously Planned Regional Initiative Insp of safety-related Mod Will Be Performed 3F1099-14, Requests Copy of NRC Radtrad Code & Copy of User Instructions.Conditions for Receiving Code Listed1999-10-13013 October 1999 Requests Copy of NRC Radtrad Code & Copy of User Instructions.Conditions for Receiving Code Listed 3F1099-11, Provides Info on Requested Minor Permit Mod of Encl NPDES Permit.No New Regulatory Commitments Are Made1999-10-0404 October 1999 Provides Info on Requested Minor Permit Mod of Encl NPDES Permit.No New Regulatory Commitments Are Made ML20212L0771999-10-0404 October 1999 Forwards SER Accepting Licensee Relief Requests 98-012 Through 98-018 Involving Containment Insps at Crystal River Unit 3 Pursuant to 10CFR50.55a(a)(3)(i) & 10CFR50.55a(a)(3)(ii) ML20217D6551999-10-0101 October 1999 Requests That Natl Communication Sys Arrange for Licensee Participation in Government Emergency Telecommunications Service,Per NRC Info Notice 99-025 ML20212J8481999-10-0101 October 1999 Forwards Safety Evaluation Re Second 10 Yr Interval ISI Program Requests for Relief 98-009-II.Reliefs Granted for 98-009-II,Parts B & C & 98-010-II & 98-011-II 3F0999-03, Notifies of Approved Change to NPDES Permit Applicable to Crystal River Unit 3 IAW Section 3.2.3 of Epp.Proposed Change Was Approved on 990914 by State of Fl & Provided in Attachment1999-09-27027 September 1999 Notifies of Approved Change to NPDES Permit Applicable to Crystal River Unit 3 IAW Section 3.2.3 of Epp.Proposed Change Was Approved on 990914 by State of Fl & Provided in Attachment 3F0999-18, Notifies NRC That Due Date for Commitment Common to Ltrs 980115 & 980209 Will Be Extended.Revised Completion Date for Cable Ampacity Project Is 0003311999-09-27027 September 1999 Notifies NRC That Due Date for Commitment Common to Ltrs 980115 & 980209 Will Be Extended.Revised Completion Date for Cable Ampacity Project Is 000331 ML20212F7251999-09-23023 September 1999 Discusses Staff Review of Util 980330 Response,As Suppl on 990514,to GL 97-06, Degradation of SG Internals. Staff Concludes That Licensee Responses to GL Provide Reasonable Assurance That Condition of SG Internals Acceptable ML20212F7331999-09-23023 September 1999 Discusses Util Licensing Action for GL 98-01, Year 2000 Readiness of Computer Systems at Nuclear Power Plants. NRC Ack Efforts Util Completed to Date in Preparing Crystal River,Unit 3 for Y2K Transition 3F0999-20, Forwards Summary Re Justification to Defer USI A-46 Commitment,Per Work Needed to Resolve GL 87-03, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Usi A-461999-09-21021 September 1999 Forwards Summary Re Justification to Defer USI A-46 Commitment,Per Work Needed to Resolve GL 87-03, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Usi A-46 ML20212E6741999-09-21021 September 1999 Forwards Safety Evaluation Accepting Proposed EAL Changes Submitted by ,As Supplemented by 981120,990713 & 0831 Ltrs,Incorporating Guidance in NUMARC/NESP-007,Rev 2, Methodology for Development of Eals 3F0999-01, Forwards FPC Crystal River Unit 3 Plant Reference Simulator Four-Year Simulator Certification Rept Sept 1995-Sept 1999, Per 10CFR55.45(b)(5)(ii) & 10CFR55.45(b)(5)(iv)1999-09-17017 September 1999 Forwards FPC Crystal River Unit 3 Plant Reference Simulator Four-Year Simulator Certification Rept Sept 1995-Sept 1999, Per 10CFR55.45(b)(5)(ii) & 10CFR55.45(b)(5)(iv) 3F0999-19, Provides Clarification of Minor Inconsistency Identified During Review of NRC SE for Plant Third 10-year Interval Inservice Insp Program Plan & Associated Requests for Relief1999-09-15015 September 1999 Provides Clarification of Minor Inconsistency Identified During Review of NRC SE for Plant Third 10-year Interval Inservice Insp Program Plan & Associated Requests for Relief ML20212F3141999-09-13013 September 1999 Forwards Insp Rept 50-302/99-05 on 990704-0814.Violations Noted,But Being Treated as non-cited Violations ML20211L9081999-09-0303 September 1999 Informs of Completion of Licensing Action for GL 92-08, Thermo-Lag 330-1 Fire Barriers, Dtd 921217,for Crystal River Unit 3 ML20211Q7581999-09-0101 September 1999 Forwards Summary of 990812-13 Training Managers Conference in Atlanta,Georgia Re Recent Changes to Operator Licensing Program.List Conference Attendees,Copy of Presentation Slides & List of Participant Questions Encl 3F0899-23, Provides Addl Info in Response to Several NRC Staff Questions Needed to Complete Review of Request to Adopt NEI 97-03,Draft Final Rev 3, Methodology for Development of Eals1999-08-31031 August 1999 Provides Addl Info in Response to Several NRC Staff Questions Needed to Complete Review of Request to Adopt NEI 97-03,Draft Final Rev 3, Methodology for Development of Eals ML20211G7111999-08-30030 August 1999 Modifies Approval of 980521 Request for Exception to 10CFR50.4(b)(6) & Grants Util Approval to Submit Copies of Future Updates to FSAR as Listed ML20211G7031999-08-30030 August 1999 Informs of Approval of Util 980521 Request for Exception to 10CFR50.4(b)(6),allowing Util to Submit Updates to Plant Ufsar.Ltr Modifies That Approval & Grants Util Approval 3F0899-07, Provides Formal Notification to NRC of FPC Plans Relative to Renewal of Crystal River Unit 3,FOL DPR-72.FPC Plans to Submit Application for License Renewal by End of 20021999-08-27027 August 1999 Provides Formal Notification to NRC of FPC Plans Relative to Renewal of Crystal River Unit 3,FOL DPR-72.FPC Plans to Submit Application for License Renewal by End of 2002 ML20212C1351999-08-27027 August 1999 Requests Withholding of Proprietary Version of Enhanced Spent Fuel Storage Project Engineering Input 3F0899-20, Forwards six-month fitness-for-duty Program Performance Data for Period 990101-990630,IAW 10CFR26.711999-08-26026 August 1999 Forwards six-month fitness-for-duty Program Performance Data for Period 990101-990630,IAW 10CFR26.71 3F0899-05, Forwards Response to NRC 990716 RAI Re Proposed Alternate Repair Criteria for Axial Tube End crack-like Indications in Crystal River Unit 31999-08-20020 August 1999 Forwards Response to NRC 990716 RAI Re Proposed Alternate Repair Criteria for Axial Tube End crack-like Indications in Crystal River Unit 3 3F0899-17, Submits Relief Request 99-0001-RR,seeking NRC Approval for Evaluation Performed by Util on through-wall Flaw in Nuclear Svc & Decay Heat Sea Water (RW) Sys,Per Guidance of GL 90-051999-08-19019 August 1999 Submits Relief Request 99-0001-RR,seeking NRC Approval for Evaluation Performed by Util on through-wall Flaw in Nuclear Svc & Decay Heat Sea Water (RW) Sys,Per Guidance of GL 90-05 3F0899-16, Informs That Licensee Is Requesting State of Fl Dept of Environ Protection to Make Changes in Plant NPDES Permit to Modify Conditions on Use of Biocide in Instrument Air Compressor Sys.No New Commitments Are Made in Submittal1999-08-19019 August 1999 Informs That Licensee Is Requesting State of Fl Dept of Environ Protection to Make Changes in Plant NPDES Permit to Modify Conditions on Use of Biocide in Instrument Air Compressor Sys.No New Commitments Are Made in Submittal 3F0899-02, Forwards Rev 2 to Cycle 11 COLR IAW Plant TS Section 5.6.2.18.Rev 1 of Cycle 11 COLR Was Not Submitted Due to Administrative Error.Changes Made in Rev 1 Listed & Incorporated in Encl Rev 21999-08-16016 August 1999 Forwards Rev 2 to Cycle 11 COLR IAW Plant TS Section 5.6.2.18.Rev 1 of Cycle 11 COLR Was Not Submitted Due to Administrative Error.Changes Made in Rev 1 Listed & Incorporated in Encl Rev 2 3F0899-06, Forwards Monthly Operating Rept for July 1999 for Crystal River,Unit 3,per ITS 5.7.1.2.Revised Repts for Apr,May & June 1999,also Encl.Data on Line Item 6 Updated to Agree with More Accurate Computer Point That Measures Value1999-08-13013 August 1999 Forwards Monthly Operating Rept for July 1999 for Crystal River,Unit 3,per ITS 5.7.1.2.Revised Repts for Apr,May & June 1999,also Encl.Data on Line Item 6 Updated to Agree with More Accurate Computer Point That Measures Value 05000302/LER-1997-038, Forwards LER 97-038-01,IAW 10CFR50.73(c).Submittal Also Provides Notification That Commitment Common to LER 97-038-00 & Reply to NOV 50-302/97-16 Has Been Revised & Revised Commitment Has Been Implemented1999-08-13013 August 1999 Forwards LER 97-038-01,IAW 10CFR50.73(c).Submittal Also Provides Notification That Commitment Common to LER 97-038-00 & Reply to NOV 50-302/97-16 Has Been Revised & Revised Commitment Has Been Implemented ML20210Q4511999-08-0505 August 1999 Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licensing Exam on 991006 ML20210P0741999-08-0505 August 1999 Forwards SE Accepting Licensee 980416 & 1130 Ltrs Re Third 10-year Interval ISI Program Plan & Associated Requests for Relief for Plant,Unit 3 3F0799-30, Forwards List of Licensing Actions Currently Estimated for Fys 2000 & 2001,in Response to Administrative Ltr 99-02,dtd 9906031999-07-29029 July 1999 Forwards List of Licensing Actions Currently Estimated for Fys 2000 & 2001,in Response to Administrative Ltr 99-02,dtd 990603 ML20210G8551999-07-27027 July 1999 Forwards Insp Rept 50-302/99-04 on 990523-0703.One Violation Identified & Being Treated as Noncited Violation 3F0799-09, Provides Response to NRC 990625 Telcon RAI Re Util Use of Relief Request 98-009-II for Plant ASME Section XI, Inservice Insp Second Interval.Ltr Established No New Regulatory Commitments1999-07-19019 July 1999 Provides Response to NRC 990625 Telcon RAI Re Util Use of Relief Request 98-009-II for Plant ASME Section XI, Inservice Insp Second Interval.Ltr Established No New Regulatory Commitments ML20209H5211999-07-16016 July 1999 Forwards Request for Addl Info Re Licensee Proposed Alternate Repair Criteria for Axial Tube End crack-like Indications in CR-3 once-through Steam Generators in Order to Complete Review ML20209G3231999-07-15015 July 1999 Forwards Biological Opinion Issued by Natl Marine Fisheries (NMFS) of Dept of Commerce.Nmfs Concluded That Operation of Cw Intake Sys of Crystal River Not Likely to Jeopardize Existence of Species Listed in Biological Opinion ML20209G3481999-07-15015 July 1999 Transmits Natl Marine Fisheries Svc (NMFS) Biological Opinion Based on Review of Continued Use of Cw Intake Sys at Crystal River Energy Complex.Concludes That Continued Use of Cw Intake Sys Not Likely to Adversely Affect Gulf Sturgeon 3F0799-21, Forwards Copy of Revised NPDES Permit IAW Section 3.2.3 of Unit 3 Environ Protection Plan,Per 990430 Request to Allow Use of Biocide in Station Air Compressor Cooling Sys. Wastewater Permit FL0000159 Issued 990630 Also Encl1999-07-14014 July 1999 Forwards Copy of Revised NPDES Permit IAW Section 3.2.3 of Unit 3 Environ Protection Plan,Per 990430 Request to Allow Use of Biocide in Station Air Compressor Cooling Sys. Wastewater Permit FL0000159 Issued 990630 Also Encl 3F0799-05, Requests Exemption from 10CFR70.51, Matl Balance,Inventory & Records Requirements, as It Relates to 10CFR70.51(d) Re Physical Inventory of SNM for Crystal River Unit 3.Detailed Justification for Request,Encl1999-07-14014 July 1999 Requests Exemption from 10CFR70.51, Matl Balance,Inventory & Records Requirements, as It Relates to 10CFR70.51(d) Re Physical Inventory of SNM for Crystal River Unit 3.Detailed Justification for Request,Encl 3F0799-25, Forwards License Renewal Applications for Four Individuals, IAW 10CFR55.57.Without Encl1999-07-14014 July 1999 Forwards License Renewal Applications for Four Individuals, IAW 10CFR55.57.Without Encl 3F0799-26, Provides Notice of Change in Status for Senior Operator,Iaw 10CFR50.74(a).RD Demontfort,License Number SOP 20528-2,has Been Reassigned & No Longer Requires License Effective 9907301999-07-14014 July 1999 Provides Notice of Change in Status for Senior Operator,Iaw 10CFR50.74(a).RD Demontfort,License Number SOP 20528-2,has Been Reassigned & No Longer Requires License Effective 990730 3F0799-22, Provides Update & Rev to Submittal Made by Util Ltr with Regard to EAL Classification Methodology for Unit 3.Reponses to NRC Staff Questions Provided as Attachment D to Ltr & Reflects Discussions Held1999-07-13013 July 1999 Provides Update & Rev to Submittal Made by Util Ltr with Regard to EAL Classification Methodology for Unit 3.Reponses to NRC Staff Questions Provided as Attachment D to Ltr & Reflects Discussions Held 3F0799-03, Forwards Rev 5-0 to Safeguards Contingency Plan,Replacing Current Rev to Safeguards Contingency Plan,Rev 4,in Entirety.Rev Withheld,Per 10CFR73.211999-07-0808 July 1999 Forwards Rev 5-0 to Safeguards Contingency Plan,Replacing Current Rev to Safeguards Contingency Plan,Rev 4,in Entirety.Rev Withheld,Per 10CFR73.21 3F0799-02, Submits Rev 7-3 to Physical Security Plan,Replacing Current Rev to CR-3 Physical Security Plan,Rev 7-2,in Entirety.Rev Withheld,Per 10CFR73.211999-07-0808 July 1999 Submits Rev 7-3 to Physical Security Plan,Replacing Current Rev to CR-3 Physical Security Plan,Rev 7-2,in Entirety.Rev Withheld,Per 10CFR73.21 ML20196L1261999-07-0707 July 1999 Discusses Closeout of TAC MA0538 Re License Response to RAI Re GL 92-01,Rev 1,Suppl 1, Rv Structural Integrity, Issued on 950519 to Plant,Unit 3 3F0799-10, Submits Copy of Historical NPDES Permit Rev That Was Made in 1997 Re Use of Biocide at Crystal River Unit 31999-07-0707 July 1999 Submits Copy of Historical NPDES Permit Rev That Was Made in 1997 Re Use of Biocide at Crystal River Unit 3 ML20196J4991999-07-0101 July 1999 Advises That Info Contained in ,Which Included TR BAW-2346P,will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) ML20209C0811999-06-25025 June 1999 Forwards Overdue Controlled Document Transmittals for Listed Documents 3F0699-06, Submits Final Response to GL 98-01,Suppl 1 Re Year 2000 Readiness of Nuclear Power Plants.Year 2000 Readiness Disclosure for Crystal River,Unit 3,encl1999-06-23023 June 1999 Submits Final Response to GL 98-01,Suppl 1 Re Year 2000 Readiness of Nuclear Power Plants.Year 2000 Readiness Disclosure for Crystal River,Unit 3,encl 1999-09-03
[Table view] Category:NRC TO UTILITY
MONTHYEARML20062E6821990-11-14014 November 1990 Forwards Insp Rept 50-302/90-30 on 900924-28.No Violations or Deviations Noted IR 05000302/19900261990-11-13013 November 1990 Ack Receipt of Responding to Violations Noted in Insp Rept 50-302/90-26.Response Meets Requirements of 10CFR2.201 IR 05000302/19900321990-11-0707 November 1990 Discusses Insp Rept 50-302/90-32 on 900918-1005 & Forwards Notice of Violation ML20062E0781990-11-0202 November 1990 Forwards Requalification Exam Rept 50-302/OL-90-01 Administered During Wk of 900917.Attention Should Be Given to Concern Over Exam Matl Development ML20058F6371990-10-31031 October 1990 Forwards Insp Rept 50-302/90-29 on 900908-1005.No Violations or Deviations Noted ML20058D6621990-10-30030 October 1990 Informs That Util Response to Bulletin 90-003, Relaxation of Staff Position in Generic Ltr 83-28, Acceptable ML20062C1891990-10-24024 October 1990 Forwards Evaluation Rept Re Implementation of B&W Owners Group Safety & Performance Improvement Program at Plant ML20058F1491990-10-23023 October 1990 Confirms Arrangements for Enforcement Conference to Be Conducted on 901031 at Region II Re Containment Integrity & Design Requirements for Maintaining Containment Integrity ML20058B0811990-10-19019 October 1990 Forwards Insp Rept 50-302/90-32 on 900918-1005.Violations Noted ML20062B5701990-10-15015 October 1990 Advises of Suspension of Action on Tech Spec Change Request 170 Re Pressure/Temp Limits Rept Until Suitable Solution Can Be Worked Out within Framework of Tech Spec Improvement Program,Per 890726 & 1031 Ltrs ML20058B1561990-10-12012 October 1990 Ack Receipt of 900928 Response Re Violations Noted in Insp Rept 50-302/90-24 ML20062B6691990-10-12012 October 1990 Requests Analyses of Liquid Samples Spiked W/Radionuclides Be Completed within 60 Days of Sample Receipt ML20058A9621990-10-11011 October 1990 Forwards Insp Rept 50-302/90-31.No Violations or Deviations Noted ML20059N4111990-10-0404 October 1990 Forwards Insp Rept 50-302/90-27 on 900917-21.No Violations or Deviations Noted.Rept Withheld (Ref 10CFR2.790 & 73.21) ML20059L9501990-09-24024 September 1990 Forwards Insp Rept 50-302/90-25 on 900812-17.No Violations or Deviations Noted ML20059M1791990-09-11011 September 1990 Advises That Objectives & Scenario Package for Emergency Response Plan Exercise,Scheduled for 900927,acceptable ML20059G7391990-09-0606 September 1990 Accepts Util 890601 & 1218 Responses to Item 1.b of Bulletin 88-11, Pressurizer Surge Line Thermal Stratification. Certain Issues Must Be Resolved Before Plant Meets All Appropriate Code Limits for 40-yr Plant Life ML20059G5941990-08-31031 August 1990 Forwards Insp Rept 50-302/90-24 on 900707-0810 & Notice of Violation ML20059H1421990-08-28028 August 1990 Requests Approved Ref Matl Listed in Encl 1,by 900926 for Reactor Operator & Senior Operator Licensing Exams Scheduled for 901126 ML20056B5321990-08-23023 August 1990 Forwards Safety Evaluation Re Util 890417 & 900330 Responses to Station Blackout Rule.Plant Not in Conformance W/Station Blackout Rule.Revised Response Should Be Submitted within 60 Days of Ltr Date.Rev 1 to SAIC-89/1150 Also Encl ML20056B2651990-08-22022 August 1990 Advises That Review of Auxiliary Feedwater Pump Conceptual Design,Submitted in ,Continuing.Nrc Offers No Comment Presently ML20058L4241990-07-31031 July 1990 Forwards Request for Addl Info Re Spent Fuel Pool Rerack Amend.Response to Items Should Be Submitted by 900820 ML20058N2901990-07-31031 July 1990 Advises That 900613 Rev 5 to Physical Security Plan Consistent W/Provisions of 10CFR50.54(p) & Acceptable ML20058Q2001990-07-31031 July 1990 Requests Supplemental Response Describing Util Corrective Actions & Date of Full Compliance,Per Insp Rept 50-302/89-18 ML20056A9191990-07-27027 July 1990 Forwards Insp Rept 50-302/90-21 on 900602-0706.No Violations or Deviations Noted ML20055H3561990-07-11011 July 1990 Advises That 900620 Response to Notice of Violation of Insp Rept 50-302/90-09 Meets Requirements of 10CFR2.201 ML20055H3701990-07-10010 July 1990 Forwards Insp Rept 50-302/90-17 on 900501-03.Noncited Violations Noted.Corrective Measures to Assure Randomness of Chemical Testing Program & to Improve Reporting of Chemical Test Results to NRC Will Be Reviewed in Future Insps ML20055H5751990-07-10010 July 1990 Forwards Insp Rept 50-302/90-22 on 900612-16.Violations Noted But Not Cited ML20055H4361990-07-0505 July 1990 Advises That Requalification Program Evaluation Visit Scheduled for Wk of 900917.Licensee Requested to Furnish Approved Items Listed in Encl Ref Matl Requirements by 900716.NRC Rules & Guidance for Examinees Also Encl ML20055E5121990-07-0202 July 1990 Forwards Safety Evaluation Re Util 831104 & 840731 Responses to Generic Ltr 83-28,Item 2.2.1 Re Equipment Classification Programs for All safety-related Components ML20055D6551990-07-0202 July 1990 Ack Receipt of & Check for $100,000 in Payment of Civil Penalty Imposed by NRC Order .Corrective Actions Will Be Examined During Future Insp IR 05000302/19900051990-06-29029 June 1990 Forwards Meeting Summary & Slides from Presentation on 900523 Re SALP 50-302/90-05.No Formal Changes to SALP Rept Needed,Therefore 900511 Rept Constitutes Final Rept.W/O Encl ML20059M9381990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20055C5981990-05-24024 May 1990 Forwards Order Imposing Civil Monetary Penalty in Amount of $100,000,per Violations Noted in Insp Rept 50-302/89-09. Penalty Proposed to Emphasize Importance of Implementing Adequate Mgt & Programmatic Controls ML20248D7351989-09-28028 September 1989 Requests That Impell Rept 03-0920-1186,Rev 0, Pipe Rupture Analysis Criteria Outside Reactor Bldg, Be Revised & Modified to Include Listed Conditions,Per NRC Approval to Calculate High Energy Line Breaks,Per ANSI B31.1 1967 ML20248E4811989-09-25025 September 1989 Forwards Staff Position on Preoperational Testing of Upgraded Emergency Diesel Generators to Be Implemented During Refuel 7.Type Qualification Tests Not Required Provided Preoperational Test Program Successfully Completed ML20248E7881989-09-25025 September 1989 Advises That Encl Notice of Consideration of Issuance of Amend to License & Proposed NSHC & Opportunity for Hearing on 890809 Request to Extend Surveillance Period for Diesel Generator full-load Test Sent to Ofc of Fr for Publication ML20248B7501989-09-22022 September 1989 Confirms 890919 Telcon Re Rescheduling & Change in Topics for Enforcement Conference on 890928,per Insp Repts 50-302/89-200 & 50-302/89-24 Concerning Insp Issues & Improper Impeller Installed on Raw Water Pump ML20248D1381989-09-22022 September 1989 Ack Receipt of 890908 Response to Violations Noted in Insp Rept 50-302/89-17 IR 05000302/19890151989-09-19019 September 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-302/89-15 ML20248C8381989-09-18018 September 1989 Forwards Insp Rept 50-302/89-24 on 890907-08.No Notice of Violations Issued for Violations Described in Rept. Enforcement Conference to Discuss Violations Scheduled for 890928 ML20247K5711989-09-18018 September 1989 Advises That Voltage Levels Discussed in LER-86-015-1 & LER-87-007 & in Util 880229 & 0902 Ltrs Considered within Design Basis of Plant.Util Should Confirm Values for 480 & 120 Voltages by Testing During Next Refueling Outage IR 05000302/19892001989-09-18018 September 1989 Confirms 890912 Telcon Re Enforcement Conference to Be Conducted on 890928 to Discuss Issues from Insp Repts 50-302/89-200 & 50-302/89-24 & Items Reported by Plant Staff on 890907 & 08 ML20247K5911989-09-18018 September 1989 Advises That Plant PRA Considered Fair Evaluation of Most Likely Paths to Core Damage at Plant.W/Stated Exceptions, Review of PRA Did Not Uncover Any Reason Why PRA Could Not Be Used as Aid to Evaluate Plant Mods or for Decisions ML20247L0841989-09-18018 September 1989 Forwards Amend 8 to Indemnity Agreement B-54.Amend Increases Primary Layer of Nuclear Energy Liability Insurance Provided by ANI & Maelu ML20247K5531989-09-15015 September 1989 Advises That If Util Revises FSAR to Account for Revised Steam Generator Tube Rupture Mitigation Emergency Operating Procedure 10CFR50.59,NRC Will Review Evaluation as Part of Periodic Review of 10CFR50.59 Changes IR 05000302/19890091989-09-13013 September 1989 Discusses Insp Rept 50-302/89-09 on 890424-28 & Forwards Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $100,000.NRC Concerns Re Insp Findings Were Discussed During 890628 Enforcement Conference ML20247H0731989-09-12012 September 1989 Confirms 890914 Conference in Region II Ofc to Discuss Plans to Resolve Electrical Issue Prior to Restart ML20247H4451989-09-12012 September 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violation Noted in Insp Rept 50-302/89-16.Severity Level Reduced from IV to V,Based on Review of Response ML20247C2251989-09-0707 September 1989 Advises That Util 890608 Response to NRC Bulletin 89-001, Failure of Westinghouse Steam Generator Tube Mechanical Plugs, Acceptable.Acceptance Based on Implicit Assumption of Util Commitment to Perform Action of Item 2.D 1990-09-06
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217F9941999-10-15015 October 1999 Discusses FPC 970819 Request for Temporary Relief from ASME Code Section XI Requirements to Repair ASME Class 3 Nuclear Service & Decay Heat Sea Water System Piping.Forwards SE Containing Results of Staff Review ML20217J5171999-10-13013 October 1999 Informs That on 990930,NRC Staff Completed mid-cycle PPR of Plant,Unit 3 & Did Not Identify Any New Areas That Warranted More than Core Insp Program.Previously Planned Regional Initiative Insp of safety-related Mod Will Be Performed ML20212L0771999-10-0404 October 1999 Forwards SER Accepting Licensee Relief Requests 98-012 Through 98-018 Involving Containment Insps at Crystal River Unit 3 Pursuant to 10CFR50.55a(a)(3)(i) & 10CFR50.55a(a)(3)(ii) ML20212J8481999-10-0101 October 1999 Forwards Safety Evaluation Re Second 10 Yr Interval ISI Program Requests for Relief 98-009-II.Reliefs Granted for 98-009-II,Parts B & C & 98-010-II & 98-011-II ML20212F7251999-09-23023 September 1999 Discusses Staff Review of Util 980330 Response,As Suppl on 990514,to GL 97-06, Degradation of SG Internals. Staff Concludes That Licensee Responses to GL Provide Reasonable Assurance That Condition of SG Internals Acceptable ML20212F7331999-09-23023 September 1999 Discusses Util Licensing Action for GL 98-01, Year 2000 Readiness of Computer Systems at Nuclear Power Plants. NRC Ack Efforts Util Completed to Date in Preparing Crystal River,Unit 3 for Y2K Transition ML20212E6741999-09-21021 September 1999 Forwards Safety Evaluation Accepting Proposed EAL Changes Submitted by ,As Supplemented by 981120,990713 & 0831 Ltrs,Incorporating Guidance in NUMARC/NESP-007,Rev 2, Methodology for Development of Eals ML20212F3141999-09-13013 September 1999 Forwards Insp Rept 50-302/99-05 on 990704-0814.Violations Noted,But Being Treated as non-cited Violations ML20211L9081999-09-0303 September 1999 Informs of Completion of Licensing Action for GL 92-08, Thermo-Lag 330-1 Fire Barriers, Dtd 921217,for Crystal River Unit 3 ML20211Q7581999-09-0101 September 1999 Forwards Summary of 990812-13 Training Managers Conference in Atlanta,Georgia Re Recent Changes to Operator Licensing Program.List Conference Attendees,Copy of Presentation Slides & List of Participant Questions Encl ML20211G7031999-08-30030 August 1999 Informs of Approval of Util 980521 Request for Exception to 10CFR50.4(b)(6),allowing Util to Submit Updates to Plant Ufsar.Ltr Modifies That Approval & Grants Util Approval ML20211G7111999-08-30030 August 1999 Modifies Approval of 980521 Request for Exception to 10CFR50.4(b)(6) & Grants Util Approval to Submit Copies of Future Updates to FSAR as Listed ML20210Q4511999-08-0505 August 1999 Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licensing Exam on 991006 ML20210P0741999-08-0505 August 1999 Forwards SE Accepting Licensee 980416 & 1130 Ltrs Re Third 10-year Interval ISI Program Plan & Associated Requests for Relief for Plant,Unit 3 ML20210G8551999-07-27027 July 1999 Forwards Insp Rept 50-302/99-04 on 990523-0703.One Violation Identified & Being Treated as Noncited Violation ML20209H5211999-07-16016 July 1999 Forwards Request for Addl Info Re Licensee Proposed Alternate Repair Criteria for Axial Tube End crack-like Indications in CR-3 once-through Steam Generators in Order to Complete Review ML20209G3231999-07-15015 July 1999 Forwards Biological Opinion Issued by Natl Marine Fisheries (NMFS) of Dept of Commerce.Nmfs Concluded That Operation of Cw Intake Sys of Crystal River Not Likely to Jeopardize Existence of Species Listed in Biological Opinion ML20196L1261999-07-0707 July 1999 Discusses Closeout of TAC MA0538 Re License Response to RAI Re GL 92-01,Rev 1,Suppl 1, Rv Structural Integrity, Issued on 950519 to Plant,Unit 3 ML20196J4991999-07-0101 July 1999 Advises That Info Contained in ,Which Included TR BAW-2346P,will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) ML20207G3081999-06-0808 June 1999 Discusses Providing NRC Biological Assessment of Impact to Sea Turtles at Plant.Forwards Comments on Draft Biological Opinion Re Impact to Sea Turtles at Plant ML20195F3071999-06-0404 June 1999 Forwards Insp Rept 50-302/99-02 on 990411-0522.One Violation of NRC Requirements Occurred & Being Treated as non-cited Violation,Consistent with App C of Enforcement Policy ML20206N5511999-05-13013 May 1999 Informs That NRC Office of Nuclear Reactor Regulation Reorganized Effective 990328.As Part of Reorganization,Div of Licensing Project Mgt Created.Sr Peterson Will Be Section Chief for Crystal River Npp.Organization Chart Encl ML20206P5411999-05-0606 May 1999 Forwards Insp Rept 50-302/99-02 on 990228-0410.No Violations Noted.Three Violations of NRC Requirements Occurred & Being Treated as non-cited Violations,Consistent with App C of Enforcement Policy ML20206G1971999-05-0404 May 1999 Forwards Summary of 990412 & 14 Telcon with FPC Representatives Re NRC Questions Concerning Util 980729 & 1120 Ltrs Requesting Approval to Adopt NEI 97-03 Draft Final Rev 3, Methodology for Development of Eal ML20206K4461999-04-27027 April 1999 Forwards Notice of Withdrawal in Response to Util 990412 Request for Withdrawal of Application & Suppl by for Amend Re Normal Standby Position of Dh Removal Sys Valves DHV-34 & DHV-35 ML20206B9141999-04-20020 April 1999 Refers to Open Mgt Meeting Conducted at Licensee Request in Atlanta,Ga on 990414 Re Recent Crystal River 3 Plant Performance.List of Attendees & Copy of Presentation Handout Encl ML20205S4741999-04-20020 April 1999 Informs That NRC Determined FTI Topical Rept BAW-2342P,Rev 0,entitled OTSG Repair Roll Qualification Rept,Addendum a, Marked as Proprietary Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) ML20205T3241999-04-0909 April 1999 Informs That on 990402,K Mccall & Ho Christensen Confirmed Initial Operator Licensing Exam Schedule for Plant for Y2K Initial Exam Dates Are Wks of 000828 & 0911 for Approx Nine Candidates ML20205K6001999-04-0808 April 1999 Forwards Draft Biological Opinion from National Marine Fisheries Service Re Impact on Endangered Sea Turtles of Operation of Crystal River Energy Complex for Review & Comment ML20205K6111999-04-0202 April 1999 Forwards Request for Addl Info Re Util 980416 & Revised 981130 Submittals of Third 10-year Inservice Insp Program for Crystal River Unit 3 ML20205Q4871999-03-29029 March 1999 Forwards Insp Rept 50-302/99-01 on 990117-0227.No Violations Noted ML20205D5101999-03-26026 March 1999 Discusses FPC 961008 & 970228 Responses to NRC RAI Re Postulated Failure of RCP Seal Area Heat Exchanger Which Could Cause Overpressurization of Nuclear Svcs Closed Cycle Cooling Sys.Determined That in-depth Study Not Needed ML20205D3391999-03-22022 March 1999 Advises of NRC Planned Insp Effort Resulting from Plant PPR Completed on 990203,to Develop Integrated Understanding of Safety Performance.Historical Listing of Plant Issues & Details of Insp Plan for Next Eight Months Encl ML20204J5601999-03-22022 March 1999 Confirms 990309 Telcon Between R Mclaughlin of Licensee Staff & Ninh of NRC Re Mgt Meeting to Be Held at Licensee Request & Scheduled for 990313 in Atlanta,Ga to Discuss Recent Crystal River 3 Performance ML20207L3501999-03-0404 March 1999 Forwards Request for Addl Info Re 980730 License Amend Request 222 on Control Room Emergency Ventilation Sys IR 05000302/19982011999-02-16016 February 1999 Forwards Operational Safeguards Insp Rept 50-302/98-201 on 980504-06.No Violations Noted.Briefings,Observations,Drills & Exercises Indicated That Modified Protection Strategy Generally Sound.Without Encl ML20203G4891999-02-0505 February 1999 Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licensing Exam on 990407. Representative of Facility Must Submit Either Ltr Indicating No Candidates or Listing of Candidates for Exam ML20203A4301999-02-0303 February 1999 Forwards SE Re 3 EAL Changes.Nrc Has Concluded That Changes Meet Requirements of 10CFR50.47(b)(4) & App E to 10CFR50 & Therefore Acceptable ML20206S4191999-01-26026 January 1999 Forwards FEMA Final Exercise Rept for 981014,emergency Response Exercise.No Deficiencies or Areas Requiring Corrective Action Were Identified During Exercise ML20199J8701999-01-14014 January 1999 Informs That on 990117,Region II Will Implement Staff Reorganization as Part of agency-wide Streamlining Effort. Copy of Organization Charts Encl for Info ML20199F4971999-01-11011 January 1999 Confirms FPC Informing That Request for USNRC Review of Topical Rept Boron Dilution by RCS Hot Leg Injection Submitted on 970227 Was Being Withdrawn.Informs That All Remaining Review Effort for Request,Canceled ML20199E3441999-01-11011 January 1999 Confirms Licensee Informing NRC That Request for Exemption from Requirements of 10CFR70.24(a) for Crystal River Unit 3,submitted by Util by Ltr Being Withdrawn ML20199D6071999-01-0404 January 1999 Forwards Insp Rept 50-302/98-10 on 981025-1205 & Notice of Violation.Nrc Concluded That Info Re Reason for Violation, C/A Taken & Plan to Correct Violation & Prevent Recurrence Already Adequately Addressed ML20199E3991998-12-23023 December 1998 Discusses Training Managers Conference Conducted at RB Russell Bldg on 981105.Agenda Used for Conference,List of Attendees,Slide Presentation & Preliminary Schedule for FY99 & FY00 Encl ML20198N9051998-12-16016 December 1998 Forwards Insp Rept 50-302/98-13 on 981116-20.No Violations Noted.Insp Consisted of Selective Exams of Procedures & Representative Records,Interviews with Personnel & Observations of Activities in Progress ML20196H2511998-12-0101 December 1998 Forwards Insp Rept 50-302/98-12 on 981013-16.No Violations Noted.Insp Team Observed Selected Portions of Emergency Organizations Response in Key Facilities During EP Plume Exposure Exercise ML20196C2931998-11-24024 November 1998 Forwards Notice of Withdrawal of 971031 Application for Amend to License ML20196A5321998-11-23023 November 1998 Ack Receipt of That Informed of Clarifications Needed Re Time Necessary to Start Control Complex Chillers at Plant,After Loss of Offsite Power.Changes to Start Times Do Not Alter Conclusion in SE Supporting Amend 163 to TSs ML20196C6291998-11-20020 November 1998 Advises of Planned Insp Effort Resulting from Insp Planning Meeting Held on 981102.Insp Plan for Next 4 Months & Historical Listing of Plant Issues,Called Plant Issues Matrix, Encl ML20195G4461998-11-17017 November 1998 Discusses FPC 980518 Submittal of Operational Assessment of Once Through SG Tube Degradation at CR-3 in Accordance with License Commitment Submitted on 971207 1999-09-03
[Table view] |
Text
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- August 25, 1985 Docket No. 50-302 DISTRIBUTION (DecRet File?
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- ACRS-10 NRC PDR RIngram L PDR HSilver Mr. Walter S. Wilgus ORB #4 Rdg BMozafari Vice President, Nuclear Operations HThompson Gray File Florida Power Corporation OELD EBrach ATTN: Manager, Nuclear Licensing EJordan H0rnstein
& Fuel Management BGrimes WPaulson P. O. Box 14042; M.A.C. H-3 JPartlow GEdison St. Petersburg, Florida 33733 CTrammel
Dear Mr. Wilgus:
We have reviewed the information on masonry wall design (IE Bulletin 80-11) for Crystal River Unit 3 submitted with your letter dated February 29, 1984, and find that additional information is still needed in order to complete our review of this matter. The requested information is contained in the enclosure.
Please provide.the information requested within 30 days of receipt of this letter.
Sincerely,
%u aus w.a .,a Jow J. sivtJ.'
John F. Stolz, Chief Operating Reactors Branch #4 Division of Licensing
Enclosure:
As Stated cc w/ enclosure:
See next page ORBN:DL ORB . 'm4:DL HSilver;cr JStolz 8@5 8/n /85 8509030165 850826 PDR ADOCM 05000302 G PDR
REQUEST FOR ADDITIONAL INFORMATION MASONRY WALL DESIGN, IE BULLETIN 80-11 '
CRYSTAL RIVER UNIT 3 , -
DOCKET NO. 50-302
- - STRUCTURAL AND GE0 TECHNICAL ENGINEERING BRANCH STRUCTURAL ENGINEERING SECTION A 1.
According to Section 1.2.3 of Reference 1, a portion of wall I has been removed to eliminate the wall's possible effect on safety-related equipment (see Figure 4. Ref.1). Explain how this modification removes the safety concern of wall collapse on equipment near wall 1.
- 2. According to Reference 1, walls 2 and 3 exceed ACI 531-79 alloweble stresses by 50% to 60*; however, according to the cover 4 letter of Reference 1, a recent inspection has shown that the collapse of walls 2 and 3 would not have an adverse effect on safety-related equipment in the area. Indicate the recent findings that have permited these walls to be considered differently and 3inasthe than original eval'uation (Reference 2), which presented wall 2 safety-related. Also, provide the documentation of the evaluation of these walls that, according to the cover letter of Reference 1, was dut by April 30, 1984 but has not yet been provided.
3.
The response to Item 4 in Reference 1 indicates that for the five control ccmplex walls, a " fixed" boundary condition is assumed for nortared joints at masonry wall bases, top edges along a support slab, andwall.
masonry side edges where'the corner is integral with another No dcwels, anchcrs, or other boundary reinforcements are present. Provide the justification for the assumption typical connectionof fixed in ccnditions detail. for mortared joints by examining a on calculated results. Indicate the effect of joint flexibility 4
With respect to Section 3.1.2 of Reference 1, walls 1, 4, and 5 do not meet the ACI minimum requirements for 3hickness, so the ACI 531-79 formula, Fa = 0.255 f'm [1 - (h/4C4 ], for allowable axial ccmpressicn becomes negative.
the Southern Standard Building Code (SSBC) compression stressThese allowable of 70 psi. Also, fixed side boundary conditions in walls 4 and 5 were relaxed to allow for a redistribution of moment, which helped to keep stresses within allowable limits.
the reasons for accepting these walls as meeting the SGEC criteria, Provide s
5.
With respect to the seismic analysis of the instrument room walls in the turbine buildir.g, Section 3.2 in Reference I indicates that the effect of the first nede of vibration was increased by 5" to account for higher modes. Indicate why these walls were not checked control with an eight mode analysis as were the five walls in the complex. i Indicate whether there are other differences in
the criteria between the control complex walls and the instrument reem walls. Also, Figures 22 and 23 show " knife edge" boundary conditions for walls in the turbine building. Indicate whether these conditions were changed to " fixed" or " free" as in the control complex walls, and specify the physical boundary connections.
The staff cces not accept the use of arching or wedging action at boundary c'onnections in qualifying masonry walls (the staff position is attached).
REFERENCES
- 1. G.R. Westafer Letter
Subject:
with Attachment to J. R. Stolz (NRC)
Crystal River Unit 3 IE Bulletin 80-11, Request for Additional Information . '
Florida Power Corporation 29-Feb-84 .
- 2. P. Y. Baynard Letter to J. P. O'Reilly (NRC)
Subject:
Crystal River Unit 3, IE Bulletin 80-11, Masonry Wall Design Florida Power Corporation 17-Nov-80 6
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ATTACNENT
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SGEB Staff Position on Use of Arching Action Theory to Qualify Unreinforced Masonry Walls 1 ,
in Nuclear Power Plants a
INTP.00UCTION -
Unreinforced hollow block masonry walls have a very limited capacity under the action of out-of plane loads. Higher resistance could be i) -
ifeVeToped by' c9 eating large in-plane efamping forces 'thereby for61ng a ,
three hinged arch mechanism after mid-span and support flexural cracking j has occurred. The most important conditions'for the arching mechanism to develop are the existence of rotational restraint at the boundaries !
and the prevention of gross sliding of the wall at support sections. !
1 Some of the licensees have relied on the development of this arching .
j mechanism (referred to herein as ' arching action theory') to qualify i
unreinforced masonry walls in their plants.
The staff and their consultants have reviewed the basis provided by licensees to justify the use of arching action theory to qualify the ,
unreinforced masonry walls. The staff met with a group of licensees i .,
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representing approximately eleven utilities and twenty two units on I I
Novemoer 3,1982 and January 20, 1983 to discuss this issue. Further, a ,
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site visit and detailed review'of design calculations were conduc'ted by the staff and consultants to gain first-hand knowledge of field conditions and the application of arching action theory in qualifying in-place masonry walls. Based on the information gained through the above activities, the staff has formulated the following position on the
, acceptability of the use of arching action theo,ry to qualify unreinforced masonry walls in operating nuclear power plants. The staff's technical basis for the position is discussed in the attached repor't. .
i POSITION The use of a'rching action theory to qualify unreinforced masonry block '
walls is not acceptable. Therefore, the licensee shall fix the walls
. currently qualified by the use of arching action theory such that they meet the staff acceptance criteria based on the working stress approach.
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/ EVAI,UATION OF AEEING TEEORY IN UNREINFCEED MASONRY MAILS IN NUCLEAR POWER PLANTS 9
Prepared by
- Ahmed A. Bamid Barry G. Barris Vu Con e
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- 1. Department of Civil Engineering, Drexel University
- 2. Nuclear Engineering Department, Franklin Research Center
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In, response to IE Bulletin 80- M , a total of 16 nuclear power plants have indicated that the arching action technique has been employed to qualify some unreinforced masonry walls. Based on the review of submittals provided by the
- licensees and published literature, Franklin Research Center (FE) staff and FRC consultants have concluded that the available data in the literature do not give enough insight for understanding the mechanics and performance of l unreinforced ansonry walls under cyclic, fully reversed dynamic loading. As a j
i result, a meeting with representatives of the affected plants was held.at the
- NBC on November 3,1982 so that the NBC, FRC staff, and FRC consultants could I
explain why the applicability of arching theory to masonry walls in nuclear
{ power plants is questionable [1]. In a subsequent meeting on January 20, i
1983, consultants of utility companies presented their rebuttals (2] and
! requested that they should be treated on a plant-by-plant basis. In accordance with their requests, the NBC staff has started the process of I evaluating each plant on an individual basis. In this process, the NBC, FPC l
staff, and consultants have initiated visits to various nuclear plants to j
examine the field conditions of unreinforced masonry walls in the plants and to gain first-hand knowledge on how the arching theory is applied to actual walls.
Key calculations have been reviewed with regard to the arching theory.
1 EVALUATION OF AERING TEZCar 4
Test of unreinforced concrete masonry walls were recently conducted by Agbabian Associates, S. B. Barnes and Associates, and Kariotis and Associates l [3] (this joint venture work is designated as ARK) . Based on the visit to
! Oconee Nuclear Station, the results of the AEK tests, and all relevant A
information submitted by the licensees including the rebuttals given by the licensees in the January 20, 1983 meeting, the NE, FE staff, and consultants
! have made the following evaluations:
1 j 1. The design methodology used at various nbclear plants was developed 1
by McDowell et al. [4] in 1956 for solid brick walls under static j sonotonic loading. No test data are available to check the adequacy of hollow block ansonry under cyclic, fully reversed dynamic loading.
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n e only dynamic test data for arched masonry wa n s are the URS tests
{ 15] for blast loading. This type of loading is noti a true represen-N tation of earthquake loading because it is not fully reversed and has ,
a decayed nature. Under very short-duration blast loaoing, masonry walls, which have auch lower natural frequencies, would not fully respond to the applied load. In addition, only two wans were tested
{ under cyclic blast loading at URS for arched masonry wan s.
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Extrapolation is questionable.
of test data from solid masonry to hollow block ansonry i
Recent test data [6] of eccentricany loaded ansonry assemblages showed that the failure mechanism, strain ,
j distribution, and overan behavior of honow ansonry are quite different from those of solid or grouted masonry.
- 4. Ec uow block masonry walls are more susceptible to premature j
i wet >-shear failure or crushing compression failure. Precluding these types of failure is neccesary for the development of the arching mechanism. No data are available at the present time to determine the safety factors against these brittle failures under seismic l loading.
5.
i ascent ARK dymanic tests [3] showed that unreinforced block masonry j walls did fail (conapse) under earthquake loads with ground i
acceleration (effective peak acceleration) of about 0.3g to 0.4g, which is typical for nuclear plants. Also, some wan s experienced
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local crushing at the base before failure by instability, which emphasizes walls.
the possibility of premature compression failure of arched i
It must be noted, however, that the AEK test wans were not j restrained at top to develop arching. The effect of boundary conditions could be significant and cannot be evaluated without further testing. l 4
6.
' Unreinforced block masonry walls are extremely brittle, and flexural j
failure occurs without warning. The sensitivity of unreinforced i evident. toAlso, aasonry crack development due to temperature and shrinkage is the inherent strength variability indicates the necessity of different safety indexes in ultimate failure analysis.
- 7. Masonry wan s in nuclear plants usuan y have openings and j attachments.
Their effects on wall stability under seismic loading i
are unknown and cannot be rationally evaluated without testing.
j 8. No test data are available for gapped arching block wans under
! cyclic loading. In some cases, restrainers are provided around the gap to prevent gross sliding; this repair' measure does not necessarily change the wall behavior from gapped arch to rigid arch.
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- ,y CONCLCSICH A review and evaluation of the available information on the applicability of arching theory to unreinforced masonry walls in nuclear power plants has been presented.
NIC, FRC staff, and consultants are firmly convinced that their original position expressed to the licensees in the November 3,1983 meeting is still valid. It is evident that test data are needed to quantitatively determine the effects of different wall geometries, material properties, and boundary conditions on unreinforced block masonry walls'
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resistance to earthquake loading. It is recommended that a confirmatory ,
- testing program be performed to investigate the applicability of arching theory to unreinforced block masonry walls in nuclear > power plants.
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mr.rFJENCES
- 1. Basid, A. A. and Barris, E. G., " Applicability of Arching Theory to Unreinforced Block Masonry Walls Under Earthquake Loading," l'ranklin Research Center, Philadelphia, PA '
August 1982
- 2. ' Rebuttal to Applicability of Arching Theory to Unreinforced Block 1 Masonry Walls Under Earthquake Loading,' Computsch Engineering Services, Inc., URS/J. A. Blume & Associates and Bechtel Power ,
Corporation, January 1983 l
- 3. ' Methodology of Mitigation of Seismic Eazards in Existing Unreinforced Masonry Buildings: Wall Testing, out-of-Plane,"
i ARK report, El Segundo, CA i 1981
- 4. McDowell, E. L. , McKee, M. E. , and Sevin, E. , " Arching Action Theory of Masonry Walls," ASCE Proceedings, Journal of the Structural
! E17.111ED,ST2.
March 1956 t
- 5. Gabrielsen, B. , Wilton, C. , and Kaplan, K. , " Response of Arching Walls and Debris from Interior Walls caused by Blast Loading," Report i No. 7030-23, URS Research Company, San Mateo, CA i Pobruary 1975 j 6. Drysdale, R. G. and Hamid, A. A., " Capacity of Concrete Block Masonry l Prisons Under Eccentric Compressive Loading," ACI Journal, 1
Proceedings, Vol. 80 March-April 1983 i
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-4 j 4 UN'J a w Franklin as n r Research.Cente.r
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Mr. W. S. Wilgus Crystal River Unit No. 3 Nuclear Florida Power Corporation Generating Plant cc: l Mr. R. W. Neiser Bureau of Intergovernmental Relations i Senior Vice President 660 Apalachee Parkway and General Counsel Tallahassee, Florida 32304 Florida Power Corporation P. O. Box 14042 Mr. Wilbur Langely, Chairman St Petersburg, Florida 33733 Board of County Commissioners Citrus County Nuclear Plant Manager . Inverness, Florida 36250 Florida Power Corporation P. O. Box 219 Crystal River, Florida 32629 Mr. Robert G. Borsum Babcock & Wilcox Nuclear Power Generation Division Suite 220, 7910 Woodmont Avenue Bethesda, Maryland 20814 Resident Inspector U.S. Nuclear Regulatory Commission Route #3, Box 717 Crystal River, Florida 32629 Regional Administrator, Revion II U.S. Nuclear Regulatory Commission 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303 Mr. Ulray Clark, Administrator Radiological Health Services Department of Health and Rehabilitative Services 1323 Winewood Blvd.
Tallahassee, Florida 32301 Administrator Department of Environmental Regulation Power Plant Siting Section State of Florida 2600 Blair Stone Road Tallahassee, Florida 32301 Attorney General Department of Legal Affairs The Capitol Tallahassee, Florida 32304
.