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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217J3341999-10-19019 October 1999 Forwards Request for Addl Info Re Sale of Portion of Land Part of Oyster Creek Nuclear Generating Station Site Including Portion of Exclusion Area ML20217E0181999-10-0606 October 1999 Provides Nj Dept of Environ Protection Comments on Oyster Creek Nuclear Generating Station TS Change Request 267 Re Clarifications to Several TS Sections ML20216J7591999-09-30030 September 1999 Informs NRC That Remediation Efforts for Software Sys Etude & Rem/Aacs/Cico Have Been Completed According to Schedule & Now Y2K Ready 05000219/LER-1998-011, Forwards LER 98-011-02, Three Small Bore Pipe Lines Did Not Meet Design Bases for Siesmic & Thermal Allowables. Engineering Std Will Not Be Completed Until End of 4th Quarter of 1999 Due to Scheduling Conflicts1999-09-30030 September 1999 Forwards LER 98-011-02, Three Small Bore Pipe Lines Did Not Meet Design Bases for Siesmic & Thermal Allowables. Engineering Std Will Not Be Completed Until End of 4th Quarter of 1999 Due to Scheduling Conflicts ML20212J6721999-09-30030 September 1999 Informs of Completion of mid-cycle PPR of Oyster Creek Nuclear Generating Station on 990913.No Areas Identified in Which Licensee Performance Warranted Addl Insp Beyond Core Insp Program.Historical Listing of Plant Issues Encl ML20216K1421999-09-29029 September 1999 Provides NRC with Name of Single Point of Contact for Purpose of Accessing Y2K Early Warning Sys,As Requested by NRC Info Notice 99-025 ML20217D1661999-09-27027 September 1999 Forwards Proprietary Completed NRC Forms 396 & 398,in Support of License Renewal Applications for Listed Individuals,Per 10CFR55.57.Encl Withheld ML20217B2531999-09-24024 September 1999 Informs That on 980903,Region I Field Ofc of NRC Ofc of Investigations Initiated Investigation to Determine Whether Crane Operator Qualification/Training Records Had Been Falsified at Oyster Creek Nuclear Generating Station ML20212E1971999-09-16016 September 1999 Forwards Rev 11 of Gpu Nuclear Operational QAP, Reflecting Organizational Change in Which Functions & Responsibilities of Nuclear Safety & Technical Support Div Were Assigned to Other Divisions ML20212A7921999-09-13013 September 1999 Forwards Second RAI Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, Issued on 950817 to Plant ML20212B5571999-09-10010 September 1999 Forwards Rev 11 to Oyster Creek Emergency Dose Calculation Manual, IAW 10CFR50,App E,Section V ML20211N2941999-09-0303 September 1999 Responds to NRC 990802 Telcon Request for Environ Impact Assessment of TS Change Request 251 Concerning Movement of Loads Up to 45 Tons with RB Crane During Power Operations ML20211J9831999-09-0202 September 1999 Discusses 990804 Telcon Re Sale of Portion of Oyster Creek Nuclear Generating Station Land.Requests Info Re Location of All Areas within Property to Be Released Where Licensed Radioactive Matl Present & Disposition of Radioactive Matl ML20211J6771999-08-30030 August 1999 Submits Response to NRC 990802 Telcon Request for Gpu to Provide Environ Impact Assessment for Tscr 251 ML20211K2391999-08-23023 August 1999 Forwards fitness-for-duty Performance Data Repts for TMI, Oyster Creek & Corporate Headquarters Located in Parsippany, Nj ML20211C0161999-08-19019 August 1999 Advises That Info Submitted by Ltr,Dtd 990618, Licensing Rept for Storage Capacity Expansion of Oyster Creek Spent Fuel Pool, Holtec Rept HI-981983,rev 4,will Be Withheld from Public Disclosure,Per 10CFR2.790 ML20211B9011999-08-18018 August 1999 Forwards Rev 0 to EPIP 1820-IMP-1720.01, Emergency Public Info Implementing Procedure ML20210U4341999-08-17017 August 1999 Responds to to Chairman Dicus of NRC on Behalf of Fm Massari Concern About Oyster Creek Nuclear Generating Station Not Yet Being Fully Y2K Compliant ML20210Q7331999-08-12012 August 1999 Responds to Re TS Change Request (TSCR)264 from Oyster Creek Nuclear Generating Station.Questions Re Proposed Sale of Property within Site Boundary & Exclusion Area ML20210L6311999-08-0606 August 1999 Discusses Licensee Response to GL 92-01,Rev1,Suppl 1, Rv Structural Integrity, for Plant.Staff Has Revised Info in Rv Integrity Database & Releasing as Rvid Version 2 ML20210D2801999-07-22022 July 1999 Submits Response to Administrative Ltr 99-02 Operating Reactor Licensing Action Estimates. Estimate of Licensing Actions Projected for Fy 2000 Encl.No Projection Provided for Fy 2001 ML20209H5001999-07-14014 July 1999 Forwards Revised TS Pages 3.1-15 & 3.1-17 Which Include Ref to Note (Aa) & Approved Wording of Note H of Table 3.1.1, Respectively ML20210U4411999-07-12012 July 1999 Forwards Article from Asbury Park Press of 990708 Faxed to Legislative Officer by Mutual Constitute Fm Massari Indicating That Oyster Creek Nuclear Generating State Not Fully Y2K Compliant ML20209G1451999-07-0909 July 1999 Forwards Rev 1 to 2000-PLN-1300.01, Oyster Creek Generating Station Emergency Plan. Attachment 1 Contains Brief Summary of Changes,Which Became Effective on 990702 ML20209E0821999-07-0707 July 1999 Forwards TS Change Request 269 for License DPR-16,changing Component Surveillance Frequencies to Indicate Frequency of Once Per Three Months ML20209B7501999-07-0101 July 1999 Responds to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants.Generic Ltr 98-01 Requested Response on Status of Facility Y2K Readiness by 990701.Licensee Y2K Readiness Disclosure for Ocngs,Encl ML20196G1361999-06-23023 June 1999 Provides Status of Corrective Actions Proposed in in Response to Insp Rept 50-219/98-80 & Revised Schedule for Completion of Actions Which Are Not Yet Complete ML20196E6421999-06-22022 June 1999 Forwards Revised Pages of TS Change Request 261,dtd 990618. Replacement Requested Due to Several Dates Being Omitted on Certain Pages ML20195G6541999-06-0707 June 1999 Discusses 981204 Initiation to Investigate Whether Contract Valve Technician,Was Discriminated Against for Raising Concern Re Use of Untrained/Unqualified Workers Performing Valve Repairs.Technician Was Not Discriminated Against ML20195G6631999-06-0707 June 1999 Discusses 981204 Intiation to Investigate Whether Contract Valve Technician Was Discriminated Against for Raising Concern Re Use of Untrained/Unqualified Workers Performing Valve Repairs.Technician Was Not Discriminated Against ML20209B0561999-06-0404 June 1999 Informs That NRR Has Reorganized,Effective 990328.Forwards Organizational Chart ML20195D0551999-06-0303 June 1999 Forwards TS Change Request 226 to License DPR-16,permitting Operation with Three Recirculation Loops.Certificate of Svc & Tss,Encl ML20195C5511999-05-25025 May 1999 Forwards Book of Controlled Drawings Currently Ref But Not Contained in Plant Ufsar.Drawings Were Current at Time of Submittal ML20206N7711999-05-11011 May 1999 Forwards Rev 0 to Oyster Creek Emergency Plan, IAW 10CFR50.47(b) & 10CFR50.54(q).Changes Became Effective on 990413 ML20206H9441999-04-28028 April 1999 Forwards Application for Amend to License DPR-16,requesting Approval to Handle Loads Up to & Including 45 Tons Using Reactor Bldg Crane During Power Operations,Per NRC Bulletin 96-002 ML20206B6991999-04-26026 April 1999 Forwards Copy of Rev 11 to UFSAR & Rev 10 to Oyster Creek Fire Hazards Analysis Rept. Without Fire Hazard Analysis ML20206D3801999-04-26026 April 1999 Forwards Rev 11 to UFSAR, & Rev 10 to Fire Hazards Analysis Rept, for Oyster Creek Nuclear Generating Station, Per 10CFR50.712(e) ML20206A9931999-04-22022 April 1999 Forwards Number of Personnel & Person Rems by Work & Job Function Rept for Period Jan-Dec 1998. Included in Rept Is Listing of Number of Station,Util & Contractor Personnel as Well as Diskette Reporting 1998 Occupational Radiation ML20206C8261999-04-22022 April 1999 Submits Financial Info IAW Requirements of 10CFR50.71(b) & 10CFR140.21 ML20205P8411999-04-15015 April 1999 Forwards TS Change Request 267 to License DPR-16,modifying Items in Sections 2 & 3 of Ts,Expanding Two Definitions in Section 1 & Modifying Bases Statements in Sections 2,3 & 4. Certificate of Svc Encl ML20205P5381999-04-14014 April 1999 Ack Receipt of Re Request for Exception to App J. Intended Correction Would Need to Be Submitted as Change to TS as Exceptions to RG 1.163 Must Be Listed in Ts,Per 10CFR50,App J ML20205P9401999-04-12012 April 1999 Informs NRC That Gpu Nuclear Is Modifying Oyster Creek FSAR to Reflect Temp Gradient of 60 F & to Correct Historical Record ML20205P0651999-04-0909 April 1999 Discusses 990225 PPR & Forwards Plant Issues Matrix & Insp Plan.Results of PPR Used by NRC Mgt to Facilitate Planning & Allocation of Insp Resources 05000219/LER-1998-015, Forwards LER 98-015-01,as Original Submittal on 981028 Inadvertently Indicated That Suppl Would Be Submitted.Suppl Should Not Have Been Required as Only Change Is on Cover Page1999-04-0505 April 1999 Forwards LER 98-015-01,as Original Submittal on 981028 Inadvertently Indicated That Suppl Would Be Submitted.Suppl Should Not Have Been Required as Only Change Is on Cover Page ML20205J3281999-04-0101 April 1999 Discusses Arrangements Made on 990323 for NRC to Inspect Licensed Operator Requalification Program at Oyster Creek Nuclear Generating Station During Week of 990524 ML20205H1081999-03-31031 March 1999 Forwards Current Funding Status for Decommissioning Funds Established for OCNPP,TMI-1,TMI-2 & SNEC ML20205F0611999-03-25025 March 1999 Submits Info on Sources & Levels of Property Insurance Coverage Maintained & Currently in Effect for Oyster Creek Nuclear Generating Station,Iaw 10CFR50.54(w)(3) ML20205E1171999-03-24024 March 1999 Forwards Rev 39 to Oyster Creek Security Plan & Summary of Changes,Iaw 10CFR50.54(p).Rev Withheld ML20207F0331999-03-0404 March 1999 Forwards Insp Rept 50-219/98-12 During Periods 981214-18, 990106-07 & 20-22.Areas Examined During Insp Included Implementation of GL 89-10 & GL 96-05.No Violations Noted ML20207K2471999-02-25025 February 1999 Forwards Fitness for Duty Performance Data Repts for TMI, Oyster Creek & Corporate Headquarters Located in Parsippany, Ny 1999-09-30
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217E0181999-10-0606 October 1999 Provides Nj Dept of Environ Protection Comments on Oyster Creek Nuclear Generating Station TS Change Request 267 Re Clarifications to Several TS Sections 05000219/LER-1998-011, Forwards LER 98-011-02, Three Small Bore Pipe Lines Did Not Meet Design Bases for Siesmic & Thermal Allowables. Engineering Std Will Not Be Completed Until End of 4th Quarter of 1999 Due to Scheduling Conflicts1999-09-30030 September 1999 Forwards LER 98-011-02, Three Small Bore Pipe Lines Did Not Meet Design Bases for Siesmic & Thermal Allowables. Engineering Std Will Not Be Completed Until End of 4th Quarter of 1999 Due to Scheduling Conflicts ML20216J7591999-09-30030 September 1999 Informs NRC That Remediation Efforts for Software Sys Etude & Rem/Aacs/Cico Have Been Completed According to Schedule & Now Y2K Ready ML20216K1421999-09-29029 September 1999 Provides NRC with Name of Single Point of Contact for Purpose of Accessing Y2K Early Warning Sys,As Requested by NRC Info Notice 99-025 ML20217D1661999-09-27027 September 1999 Forwards Proprietary Completed NRC Forms 396 & 398,in Support of License Renewal Applications for Listed Individuals,Per 10CFR55.57.Encl Withheld ML20212E1971999-09-16016 September 1999 Forwards Rev 11 of Gpu Nuclear Operational QAP, Reflecting Organizational Change in Which Functions & Responsibilities of Nuclear Safety & Technical Support Div Were Assigned to Other Divisions ML20212B5571999-09-10010 September 1999 Forwards Rev 11 to Oyster Creek Emergency Dose Calculation Manual, IAW 10CFR50,App E,Section V ML20211N2941999-09-0303 September 1999 Responds to NRC 990802 Telcon Request for Environ Impact Assessment of TS Change Request 251 Concerning Movement of Loads Up to 45 Tons with RB Crane During Power Operations ML20211J6771999-08-30030 August 1999 Submits Response to NRC 990802 Telcon Request for Gpu to Provide Environ Impact Assessment for Tscr 251 ML20211K2391999-08-23023 August 1999 Forwards fitness-for-duty Performance Data Repts for TMI, Oyster Creek & Corporate Headquarters Located in Parsippany, Nj ML20211B9011999-08-18018 August 1999 Forwards Rev 0 to EPIP 1820-IMP-1720.01, Emergency Public Info Implementing Procedure ML20210D2801999-07-22022 July 1999 Submits Response to Administrative Ltr 99-02 Operating Reactor Licensing Action Estimates. Estimate of Licensing Actions Projected for Fy 2000 Encl.No Projection Provided for Fy 2001 ML20209H5001999-07-14014 July 1999 Forwards Revised TS Pages 3.1-15 & 3.1-17 Which Include Ref to Note (Aa) & Approved Wording of Note H of Table 3.1.1, Respectively ML20210U4411999-07-12012 July 1999 Forwards Article from Asbury Park Press of 990708 Faxed to Legislative Officer by Mutual Constitute Fm Massari Indicating That Oyster Creek Nuclear Generating State Not Fully Y2K Compliant ML20209G1451999-07-0909 July 1999 Forwards Rev 1 to 2000-PLN-1300.01, Oyster Creek Generating Station Emergency Plan. Attachment 1 Contains Brief Summary of Changes,Which Became Effective on 990702 ML20209E0821999-07-0707 July 1999 Forwards TS Change Request 269 for License DPR-16,changing Component Surveillance Frequencies to Indicate Frequency of Once Per Three Months ML20209B7501999-07-0101 July 1999 Responds to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants.Generic Ltr 98-01 Requested Response on Status of Facility Y2K Readiness by 990701.Licensee Y2K Readiness Disclosure for Ocngs,Encl ML20196G1361999-06-23023 June 1999 Provides Status of Corrective Actions Proposed in in Response to Insp Rept 50-219/98-80 & Revised Schedule for Completion of Actions Which Are Not Yet Complete ML20196E6421999-06-22022 June 1999 Forwards Revised Pages of TS Change Request 261,dtd 990618. Replacement Requested Due to Several Dates Being Omitted on Certain Pages ML20195D0551999-06-0303 June 1999 Forwards TS Change Request 226 to License DPR-16,permitting Operation with Three Recirculation Loops.Certificate of Svc & Tss,Encl ML20195C5511999-05-25025 May 1999 Forwards Book of Controlled Drawings Currently Ref But Not Contained in Plant Ufsar.Drawings Were Current at Time of Submittal ML20206N7711999-05-11011 May 1999 Forwards Rev 0 to Oyster Creek Emergency Plan, IAW 10CFR50.47(b) & 10CFR50.54(q).Changes Became Effective on 990413 ML20206H9441999-04-28028 April 1999 Forwards Application for Amend to License DPR-16,requesting Approval to Handle Loads Up to & Including 45 Tons Using Reactor Bldg Crane During Power Operations,Per NRC Bulletin 96-002 ML20206D3801999-04-26026 April 1999 Forwards Rev 11 to UFSAR, & Rev 10 to Fire Hazards Analysis Rept, for Oyster Creek Nuclear Generating Station, Per 10CFR50.712(e) ML20206B6991999-04-26026 April 1999 Forwards Copy of Rev 11 to UFSAR & Rev 10 to Oyster Creek Fire Hazards Analysis Rept. Without Fire Hazard Analysis ML20206C8261999-04-22022 April 1999 Submits Financial Info IAW Requirements of 10CFR50.71(b) & 10CFR140.21 ML20206A9931999-04-22022 April 1999 Forwards Number of Personnel & Person Rems by Work & Job Function Rept for Period Jan-Dec 1998. Included in Rept Is Listing of Number of Station,Util & Contractor Personnel as Well as Diskette Reporting 1998 Occupational Radiation ML20205P8411999-04-15015 April 1999 Forwards TS Change Request 267 to License DPR-16,modifying Items in Sections 2 & 3 of Ts,Expanding Two Definitions in Section 1 & Modifying Bases Statements in Sections 2,3 & 4. Certificate of Svc Encl ML20205P9401999-04-12012 April 1999 Informs NRC That Gpu Nuclear Is Modifying Oyster Creek FSAR to Reflect Temp Gradient of 60 F & to Correct Historical Record 05000219/LER-1998-015, Forwards LER 98-015-01,as Original Submittal on 981028 Inadvertently Indicated That Suppl Would Be Submitted.Suppl Should Not Have Been Required as Only Change Is on Cover Page1999-04-0505 April 1999 Forwards LER 98-015-01,as Original Submittal on 981028 Inadvertently Indicated That Suppl Would Be Submitted.Suppl Should Not Have Been Required as Only Change Is on Cover Page ML20205H1081999-03-31031 March 1999 Forwards Current Funding Status for Decommissioning Funds Established for OCNPP,TMI-1,TMI-2 & SNEC ML20205F0611999-03-25025 March 1999 Submits Info on Sources & Levels of Property Insurance Coverage Maintained & Currently in Effect for Oyster Creek Nuclear Generating Station,Iaw 10CFR50.54(w)(3) ML20205E1171999-03-24024 March 1999 Forwards Rev 39 to Oyster Creek Security Plan & Summary of Changes,Iaw 10CFR50.54(p).Rev Withheld ML20207K2471999-02-25025 February 1999 Forwards Fitness for Duty Performance Data Repts for TMI, Oyster Creek & Corporate Headquarters Located in Parsippany, Ny ML20206S2541999-01-20020 January 1999 Confirms Resolution of Thermo-Lag Fire Barriers in Fire Zones OB-FZ-6A & OB-FZ-6B (480 Switchgear Rooms) IAW Previous Commitments Contained in Gpuns Ltrs to NRC & 971001 ML20199J2631999-01-18018 January 1999 Requests That Listed Changes Be Made to Correspondence Distribution List for Oyster Creek Generating Station ML20199D0271999-01-11011 January 1999 Requests Listed Addl Info in Order to Effectively Review TS Change Request 264 Re Ownership of Property within Exclusion Area ML20199A6521999-01-0707 January 1999 Notifies That Reactor Operators G Scienski,License SOP-11319 & D Mcmillan,License SOP-3919-4 Have Terminated Licenses at Oyster Creek Nuclear Generating Station, Effective 990101 ML20198T1061999-01-0606 January 1999 Forwards Rev 15 to Gpu Nuclear Corporate Emergency Plan for TMI & Oyster Creek Nuclear Station. with Summary of Changes Which Reflect Use of EALs Approved in NRC Ltr to Gpun on 980908 & Other Changes Not Related to Use of New EALs ML20198K0331998-12-23023 December 1998 Forwards Change Request 268 for Amend to License DPR-16. Amend Would Change TS to Specify Surveillance Frequency of Once Per Three Months ML20198H0181998-12-22022 December 1998 Forwards Attachment Addressing New Info & Modifying 980505 Submittal Re Request for Change to Licensing Bases for ECCS Overpressure,In Response to NRC Bulletin 96-03, Potential Plugging of ECCS by Debris in Bwrs ML20198H8521998-12-16016 December 1998 Dockets Completion of Physical Inventory Performed in July 1997,as Addl Info to Nuclear Matl Balance Rept Submitted on 980416 ML20196H4461998-12-0202 December 1998 Provides Final Response to NRC GL 96-01, Testing of Safety-Related Logic Circuits ML20196B4471998-11-23023 November 1998 Provides Required Response 2 to NRC Bulletin 96-003, Potential Plugging of ECC Suction Strainers in Bwrs. During Recently Completed 17R Refueling Outage,New Strainers Were Installed ML20195J8451998-11-12012 November 1998 Forwards Rev 11 to 1000-PLN-7200.01, Gpu Nuclear Operational QA Plan, as Change Previously Made Without Appropriate Notification to NRC ML20195C7201998-11-11011 November 1998 Forwards 120-day Required Response to GL 98-04, Potential for Degradation of ECCS & CSS After LOCA Because of Construction & Protective Coating Deficiencies & Foreign Matl in Containment, ML20195E1221998-11-10010 November 1998 Notifies NRC of First Time Usage of Code Case N-504 & Inclusion Into OCNGS ISI Program,As Accepted by RG 1.147, Inservice Insp Code Case Acceptability ML20155J6851998-11-0505 November 1998 Forwards TS Change Request 266,to Modify Safety Limits & Surveillances of LPRM & APRM Sys & Related Bases to Ensure APRM Channels Respond within Necessary Range & Accuracy & Verify Channel Operability ML20155H5641998-11-0202 November 1998 Informs That Bne Has No Comments on Proposed Change 259 to Ts,Correcting Required Water Level in Condensate Storage Tank So That Design Basis Is Correctly Implemented ML20155G3741998-10-29029 October 1998 Forwards Response to NRC 980619 RAI Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions 1999-09-30
[Table view] Category:UTILITY TO NRC
MONTHYEARML20059L2551990-09-14014 September 1990 Advises of Preparation for Final Refueling Outage to Complete Second 10-yr Interval for Inservice Insps ML20059F5121990-09-0505 September 1990 Requests Exemption from Filing Requirement of 10CFR55.45(b)(2)(iii) to Allow Submittal of NRC Form 474, Simulator Facility Certification, After 910326 Deadline & to Allow Administering of Simulator Portion of Test ML20059F7441990-08-31031 August 1990 Forwards Util Review of NRC Backfit Analysis for Hardened Wetwell Vent.Nrc Analysis Does Not Support Conclusion That Hardening Existing Vent Is cost-beneficial Mod for Plant ML20059E9061990-08-30030 August 1990 Forwards Response to 900808 Request for Addl Info Re NRC Bulletin 90-002, Loss of Thermal Margin Caused by Fuel Channel Box Bow ML20059G1841990-08-29029 August 1990 Ack NRC Request to Perform Type C Testing During Unscheduled Outage,As Plant Conditions Will Allow.Type C Exemptions Should Remain in Effect Until New Outage Start Date ML20059C8231990-08-27027 August 1990 Advises That SPDS Enhancements Described in Completed,Per 900628 Request.Offline & Online Testing Completed & Enhancements Considered to Be Operational ML20059C8571990-08-24024 August 1990 Provides Results of Evaluation of Ability to Meet Acceptance Criteria for Eccs,In Response to 900804 Notice of Violation. Plant Meets Acceptance Criteria Contained in 10CFR50.46 W/ Valve Logic Design Deficiency in Containment Spray Sys ML20058N0781990-08-0909 August 1990 Submits Info Re pressure-temp Operating Limits for Facility, Per Generic Ltr 88-11.Util Recalculated Adjusted Ref Temp for Each Belt Line Matl as Result of New Displacement Per Atom Values ML20063P9521990-08-0909 August 1990 Advises That Response to NRC 900523 Request for Assessment of Hazardous Matl Shipment Will Be Sent by 910531 ML20058L9521990-08-0303 August 1990 Forwards Rev 2 to Security Contingency Plan.Rev Withheld (Ref 10CFR73.21) ML20058L9551990-08-0303 August 1990 Responds to SALP Rept 50-219/88-99.Although Minor,Several Factual Errors Noted.Dialogue Promotes & Identifies Areas Where Improvements Should Be Made ML20056A2071990-07-30030 July 1990 Forwards Response to NRC Bulletin 90-001, Loss of Fill-Oil in Transmitters Mfg by Rosemount. Record Review Performed & Sys Walkdowns Completed to Assemble Requisite List ML20055H7961990-07-20020 July 1990 Advises of Change to Preventive Maint Program for Electromatic Relief Valves.Rebuild Schedule Will Be Modified to Require Rebuilding Two or Three Valves During Refueling Outage & Remaining Valves During Next Refueling Outage ML20058N9911990-07-20020 July 1990 Partially Withheld Response to NRC Bulletin 90-002 Re Loss of Thermal Margin Caused by Box Bow (Ref 10CFR2.790(b)(1)) ML20055J0481990-07-19019 July 1990 Requests 2-wk Extension for Submittal of Response to Re Installation of Hardened Wetwell Vent W/ Appropriate Extension Period to Be Decided Pending Outcome of 900724 Meeting Discussion W/Bwr Owners Group ML20064A1221990-07-11011 July 1990 Discusses 900710 Telcon W/Nrc Re Util Corrective Actions in Response to NRC Finding That Operator Received Passing Grade on Administered Requalification Exam in 1989 Should Have Received Failing Grade.Corrective Actions Listed ML20055F8491990-07-10010 July 1990 Forwards Application for Amend to License DPR-16,consisting of Tech Spec Change Request 188,reducing Low Condenser Vacuum Scram Setpoint ML20043H7471990-06-21021 June 1990 Confirms Telcon W/A Dromerick Re Util Plans to Inspect CRD Hydraulic Control Units During Plant Walkdown to Address USI A-46, Seismic Qualification of Equipment in Operating Nuclear Power Plants. Walkdown Planned in Oct 1992 ML20043H2301990-06-14014 June 1990 Documents Licensee Commitment to Improve Seismic Restraints for Diesel Generator Switchgear Encls,Per 900613 Telcon W/ Nrc.Engineering Will Be Finalized & Mods Completed Prior to 900622 ML20043F7581990-06-0707 June 1990 Responds to Request for Info Re Util Compliance W/Generic Ltr 88-01 & Insp Plans for Upcoming 13R Outage.Frequency of Insp of Welds Classified as IGSCC Categories C,D & E Will Not Be Reduced During 13R Outage ML20043C5801990-05-25025 May 1990 Provides Descriptions & Conclusions of Three Remaining Issues of SEP Topic III-7B.Issues Include,Evaluation of Drywell Concrete Subj to High Temp & Thermal Transients ML20043C2461990-05-25025 May 1990 Forwards Rev 7 to EPIP 9473-IMP-1300.06 & Rev 4 to Radiological Controls Policy & Procedure Manual 9300-ADM-4010.03, Emergency Dose Calculation Manual. ML20043B2981990-05-21021 May 1990 Responds to NRC 900420 Ltr Re Violations Noted in Insp Rept 50-219/90-06.Corrective Actions:Incident Critique Rept Incorporated as Required Reading for Appropriate Operations Personnel & Change Made to Procedure 201.1 ML20043D0701990-05-17017 May 1990 Provides NRC W/Addl Info Re SPDS & Responds to Concerns Raised During 900117 & 18 SPDS Audit Documented in 900130 Ltr ML20043B3901990-05-0909 May 1990 Responds to NRC 900408 Ltr Re Violations Noted in Insp of License DPR-16.Corrective Actions:Two Narrow Range Drywell Pressure Monitoring Instruments to Be Provided During Cycle 14R Refueling Outage,Per Reg Guide 1.97,Category 1 ML20042G7071990-05-0808 May 1990 Forwards Summary of Initiatives & Accomplishments Re SALP, Per 891031 Commitment at mid-SALP Meeting.Plant Div Responsibilities Now Include Conduct of Maint Outages & Emergency Operating Procedure Training Conducted ML20042G2291990-05-0707 May 1990 Forwards Application for Amend to License DPR-16,consisting of Tech Spec Change Request 180,revising Tech Specs Re Fuel cycle-specific Parameters ML20042G2601990-05-0404 May 1990 Forwards Application for Amend to License DPR-16,consisting of Tech Spec Change Request 187,revising Tech Specs to Accommodate Implementation of 24-month Plant Refueling Cycle ML20042E9431990-04-20020 April 1990 Forwards Revised Epips,Consisting of Rev 7 to 9473-IMP-1300.01,Rev 4 to 9473-1300.11 & Rev 2 to 9473-ADM-1319.04.Deleted EPIPs Listed,Including Rev 3 to 9473-1300.19,Rev 2 to 9473-1300.21 & Rev 5 to 9473.1300.24 ML20042E6371990-04-16016 April 1990 Informs of Plans to Install Safety Grade Check Valve in Supply Line Inside Emergency Diesel Generator Fuel Tank Room Coincident W/Replacement or Repair of Emergency Diesel Generator Fuel Oil Tank ML20042E5001990-04-13013 April 1990 Forwards Rev 1 to Topical Rept 028, Oyster Creek Response to NRC Reg Guide 1.97. ML20012E8711990-03-28028 March 1990 Lists Property Insurance Coverage,Effective 900401,per 10CFR50.54(w)(2) ML20012D4391990-03-19019 March 1990 Forwards Application for Amend to License DPR-16,consisting of Tech Spec Change Request 186,allowing Idle Recirculation Loop to Be Isolated During Power Operation by Closing Suction,Discharge & Bypass Valves ML20012B6781990-03-0202 March 1990 Requests Exemption of Specified Local Leak Rate Test Intervals to Include Next Plant Refueling Outage Scheduled for Jan 1991,per 10CFR50,App J ML20012A1501990-02-23023 February 1990 Forwards Application for Amend to License DPR-16,consisting of Tech Spec Change Request 184,removing 3.25 Limit on Extending Surveillance Intervals,Per Generic Ltr 89-14 ML20011F2571990-02-21021 February 1990 Advises That 891003 Request for Appropriate Tech Specs for Chlorine Detection Re Control Room Habitability,Not Warranted ML20006G0101990-02-21021 February 1990 Discusses 900110 Meeting W/Nrr Re 13R Insp Criteria for RWCU Welds Outboard of Second Containment Isolation Valve. All Welds Required 100% Radiography Based on Review of Piping Spec.Response to Generic Ltr 88-01 Will Be Revised ML20006F5931990-02-20020 February 1990 Forwards Application for Amend to License DPR-16,consisting of Tech Spec Change Request 177.Amend Changes Tech Spec 4.7.B to Include Battery Svc Test Every Refueling Outage & Mod of Frequency of Existing Battery Performance Test ML20011F6641990-02-20020 February 1990 Responds to NRC 900122 Notice of Violation & Forwards Payment of Civil Penalty in Amount of $25,000.Corrective Actions:Change Made to Sys Component Lineup Sheets in 125- Volt Dc Operating Procedure to Include Selector Switches ML20006F9181990-02-15015 February 1990 Forwards Application for Amend to License DPR-16,consisting of Tech Spec Change Request 183,permitting No Limitation on Number of Inoperable Position Indicators for 16 ASME Code Safety Valves During Power Operation ML20006D2551990-01-30030 January 1990 Forwards Response to Generic Ltr 89-13 Re Plant Svc Water Sys.Insp Program for Intake Structure at Plant Implemented During Past Two Refueling Outages & Emergency Svc Water Currently Chlorinated to Prevent Biofouling ML19354E8571990-01-24024 January 1990 Forwards Omitted Pages of 900116 Ltr Re State of Nj DEP Comments on Draft full-term OL SER & Clarification of Page 10,fourth Paragraph on New Seismic Floor Response Spectra ML20006B2171990-01-23023 January 1990 Responds to Unresolved Items & Weaknesses Identified in Insp Rept 50-219/89-80.Corrective Actions:Procedure Re Containment Spray sys-diagnostic & Restoration Actions Revised to Stand Alone Re Installation of Jumpers ML19354E3891990-01-19019 January 1990 Responds to Violations Noted in Insp Rept 50-219/89-27. Corrective Actions:Procedure 108 Revised to Allow Temporarily Lifting of Temporary Variation ML19354E8441990-01-19019 January 1990 Forwards Revised Tech Spec Table 4.13-1, Accident Monitoring Instrumentation Surveillance Requirements, in Support of Licensee 890630 Tech Spec Change Request 179,per NRC Project Manager Request ML20006B2881990-01-18018 January 1990 Forwards Results from Feedwater Nozzle Exam,In Accordance w/NUREG-0619 Insp Format ML20005G8161990-01-16016 January 1990 Provides Assessment of State of Nj Concerns Re full-term OL Plant,Per NRC 891222 Request.Comments Did Not Raise Any Concerns That Refute Conclusions Reached by NRC That Facility Will Continue to Operate W/O Endangering Safety ML19354D8281990-01-15015 January 1990 Responds to Violation Noted in Insp Rept 50-219/89-21. Corrective Action:Procedure A000-WMS-1220.08, Mcf Job Order Revised to Provide Detailed Guidance for Performance of Immediate Maint ML20042D4891989-12-28028 December 1989 Forwards Response to Generic Ltr 89-10, Safety-Related Motor-Operated Valve Testing & Surveillance, Fulfilling 6-month Reporting Requirement ML20005E1401989-12-22022 December 1989 Forwards Integrated Schedule Semiannual Update for Dec 1989 1990-09-05
[Table view] |
Text
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
GPU Nuclear Corporation U ME 100 Interpace Parkway Parsippany, New Jersey 07054-1149 (201)263-6500 TELEX 136-482 Writer's Direct Dial Number:
June 14, 1985 Mr. John A. Zwolinski, Chief Operating Reactors Branch No. 5 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D. C. 20555
Dear Mr. Zwolinski:
Subject:
Oyster Creek Nuclear Generating Station Docket No. 50-219 IE Bulletin 80-11 This letter forwards updated information concerning masonry block walls at Oyster Creek. In our March 21, 1985 status letter we committed to provide you with a revision to Topical Report No. 019 by October 31, 1985. During a subsequent telephone conversation between members of our respective staffs, it was agreed that the Topical Report revision will be submitted to you by August 1, 1985. In addition, it was agreed that certain related information would be forwarded to you by June 15, 1985.
That information is contained in the attachments to this letter.
Attachment 1 provides a discussion of the effects of new modifications on walls 21 and 24, and a discussion of why walls 28 and 44 have been removed from the scope of Bulletin 80-11.
Revised stress results are contained in Attachment II for walls 8, 15, 17, 18, 24-1, 29, 30, 31, 32, 33, 43, 45 and 53. However, please note that revised out-of-plane flexural shear stresses for walls 19 and 20 are included but have not yet been verified and so are subject to change.
Also, note that the allowable in-plane shear stresses for reinforced masonry in stacked bond walls has been changed as in-plane shear stress dominates the stress pattern for these walls.
6 8506270152 850614 // ef PDR ADOCK 05000219 G PDR g// qv,fg} ara 05 ulI GPU Nuclear Corporation is a subsidiary of General Pubbc Utilities Corporation
Should you have any questions regarding the information contained in this correspondence, please contact Mr. Paul Czaya at (201) 299-2542.
tqly yo ,
/
I Pete -
Fiedler
'i President and Director Oyster Creek 1r/1915f cc: Dr. Thomas E. Murley, Administrator Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, Pa. 19406 NRC Resident Inspector Oyster Creek Nuclear Generating Station Forked River, N. J. 08731 t
! e 1
war-,-~_ am,-<-- ---,---,---,r------,,-,-,~,-,-se,-~nn-- ~ , ,--r
-e,- , e- . ~>- , a , ,-~m ,
Attachment I Walls 21 and 24 New modifications associated with wall 21 require that wall to be modified in accordance with the original design.
The.above also applies to wall 24-2.
Wall 24-1 will be modified by removing portions of the wall effecting identified components and installing seismically supported drywall in place of removed block.
Walls 28 and 44 The only equipment that could be effected by the failure of walls 28 and 44 are two conduits. The first conduit (No.62-155) is 4 inches in diameter and was originally installed as a power feed from Distribution Center C to the former Mechanical Equipment Room where a computer supply inverter was to be located. The Mechanical Equipment Room has been converted to the New Cable Spreading Room, the inverter was not installed, the conduit has been terminated in the Turbine Building and the cable was coiled up at the termination point and abandoned.
The second conduit (No. CNPT-2001) is 1 inch in diameter and was installed as part of the Plant Computer Project. This ccnduit runs from Motor Control Center lAl2 to a condensing unit and a HVAC unit for the Multiplexer Room. It is a balance-of-plant conduit which is not safety related.
Based on the above, it has been determined that walls 28 and 44 do not need to be evaluated as part of the scope of Bulletin 80-11.
i i
l 1
4 Attachmment II 4
I
.I I
i j
4 I
t i
l l
1 1
e e
i j
1 l
{
3 i .
l 1
1 L.____ ___ . _ , _ . , _ _ _ _ _ _ _ . _ ..__ _ _ _ _ __,-
SLM %RY OF RESULTS
. Office Bui'lding, Cable Tray Area, East Wall.
Imcation Intermediate plus small North & South Sections, Elev. 46'-6" Thic' mess: 6 In.
Dimensicns of Height: 1 Ft a In.
Medal Width: n Ft A In.
Bleck: AS'IM-C-90 ( ) Ru:ud.ng Bced a,
gbden h .s Mortar: Type "M"
( ) Reinforced
( x) Stacked Bcnd
( ) Other (x ) Unreinforced
^
f x) One Way
( x) Vertical Span 14.8 Tc 22.1
( ) Horizontal Span w/ supports
Range - Hz (Uncracked ( ) ?m Way Section) ( ) 4-Edge Support Tc
( ) 3- Edge Support
( ) Tcp, ( ) Side, Missing Response ( x ) One Way .21 g, ( ) Tsc Way- g, Acceleration (CBE) (CEE)
(Uncracked Section) .42 g, q, (SSE) (ss?)
( X) One Way: 17.3 25*0 I X ) Noral to M Joint, vs Flexural Tensile (CE_r.+DL) (Allcwacle)
Stresses - psi (Uncrakced 34.6 vs 41.5
- Section) (SSE+CL) (Allcwacle)
( ) Parallel to Bed Jcint, vs (CEE+DL) (Allcwacle) vs (SSE+DL) (Allcwacle)
( ) ?se Way:
( ) Ncral to Bed Joint, vs (CEE+CL) ( Al'.cwacle ) I vs (SSE+CL) (Allcwacle)
( ) Parallel to Bed Joint, vs (CEE,CL) (Allcwacle) vs (SSE,CL) (Allcwa le)
Intermediate & small north sections good Remarks for reduced height with top edge supports. Wall Nc: 8
., Small southern section good for intermediate SilDntiPP Q _
StM ERY OF RESULTS i
Office Building, Monitor and Change Room, j
. Iccaf. ion . South Wall Intermediate Section .
Elev. 46'-6" l 6
Dimensions of Height: 13 Ft 4 In. Thickness: In.
Model Width: 26 Ft 0 In. :
- t Block: ASTA-C-90 ( ) Running Bond Type of Mortar: Type "M" ( ) Stacked Bond Constmetion
( ) Reinforced ( X ) Other en=hinor4nn nf unning
( X ) Unreinforced & Seartrad Rnnd f X ) One Way
( X ) Vertical Span 9.75 To 12.6 Frequency ( ) Horizontal Span Range - Hz (Uncracked ( ) Tm Way Section) ( ) 4-Edge Support To ;
( ) 3- Edge Support
( ) Top, ( ) Side, Missing
( X ) One Way 0.25 g, ( ) Two Way: g, tion
,., (CBE) (CEE)
(Uncracked Section) 0.50 g, g, (SSE) fSSE1
, ( X ) One Way:
I X ) Nomal to Bed Joint, vs 25.0
! Flexural Tensile (C m_ +DL) W icwacle)
Stresses - psi (Uncrakced vs 41.5
- Section) (SSE+DL) (Allcwable) i ( ) Parallel to Bed Joint, , vs i (CBE+DL) (Allowacle)
I vs (SSE+DL) (Allcwable)
( ) Te Way:
( ) Nc ral to Bed Joint, vs (CBE+DL) (Allcwacle) vs (SSE+DL) (Allcwable)
( ) Parallel to Bed Joint, vs (CEE+0L) (Allewacle) vs (SSE+DL) (Allcwanle)
- In the vicinity of safety-related component s.
Remarks the wall is good for one way action with 30, Power-Strut members holding the wall in place ,
Wall No** 15 The remaining block wall may fall with no effects on safety-related items. The Power Strut support system is designed to take the full flexural load.
2
.s SLM9RY OF RESULTS Office Bldg. Battery Room
. Ia::ation South Wall, West Section F1. E. 35'-0" Dimensions of Height: 1i Ft 0 In. Thic.V.ess: 6 In.
Model Width: ia Ft 5 In.
Block: AS'IM-C-90 ( X ) Running Bond Type of Mortar: Type "M" ) Stacked Scrd
(
Ccnstr'#dm
( ) Reinforced ( ) Other (X ) Unreinforced
. SEE PAGE 17 FOR COMBINATION MODEL ANALYSIS l
l
,,0, Wall No: 17
~:.
-3
- 1 SLW.ARY & RESULTS Office Bldg. Battery Room West Wall, South Section h tien Fl. El. 35'-0" Dimensions of Height: 11 Ft 0 In. Thickness: 6 In.
Model Width: ia Ft 9 In.
Block: ASTM-C-90 ( x ) Running Band Type of Mortar: Type "M" ( ) Stacked Bcnd hedon ) Other
( ) Reinfcrced (
(x) Unreinforced f
1 SEE PAGE 17 FOR COMBINATION MODEL ANALYSIS 9-
>o.o Wall Nc: 18 e 4 e I
~
~
"'? '
- C:icter Cr n 2 !;:le* 3% C 3 T 1111
.s So' --
3eovaluation o:t Concre-o Usa:::
- ,' gg;; II 2
- lletts 30 - 11
. StMtuY 07 RCSULTS , .,
{" ,I, Location ,
O f fice Eldg. Switchgear Room ',
- North Wall, West Section Fl . El . 23.'.-6" ,
Di=ensions of Reight: 10 Tc 2.5 In. Thickness: 8 In.
] MoceL Wid..h : 23 Tc 0 In.
- i. ,, ,
(X) Ruaning 3 cad - I Type of . Block: ASTM - C-90 Mortar: Type "M" I
( ) Stacked Bond Construction
( ) Reinforced ( ) Other (X) Unreinforced
- Frequeccy ( ) One Way i Range - Ha ( ) Vertical Span . To (Uncracked ( ) Rorizontal Span Sec tica) w _
g,y 2
g
( ) 4-Edge Support
! (X) 3-Edge Support
( ) Top, (;9 Side, Missing _
~
R'esponse
~
( ) One Way: g, (X) Two Way: O /9 g,
(, '
Acceleration C3E.) CBE) *
(Uncracked ,, g, g ,,
3*** "I GSE)
(SSE)
-*
- Flexuisl Tensile ( ) One Way: '
Stresses - psi vs
( ) Norcal to 3ed Joint, Guerackad (03E+0L) (Allovaole)
Section) vs (SSEtDL) (Allowaole)
! ( ) Parallell to Bed Joint, vs l (03EtDL) , (Allowaole) vs _1 i
- (S SE+0 L) (ALL:uaole)
(x) Two Way:
2
. (X) Nor::.al to Bed Joint, f8 vs 2.5,0 (03E+DL) (Allowaole) j
/[.6 I vs 41.5 (SS E+0L) (Allowa3Le) l (x) Parallel to Bad Joint, Nd2.Li s 6f_ vs 60 0 j (OBE+0L) (Allowante) }
I '
NGLl4t&4 vs 750
' {d .
- (SSE+D Q _ (Allowaald)
%. is go ret M8 y W'N e04( (
2t ne= arks sea.7 w o m ,snee e r w ,o. o Ng v2tt No. ,
, f
SGNARY OF RESULTS Turbine Building, North East Stairwell, West Wall, Iccation L wer Part, Floor Elev. 3'-6" Fl. El. ( )
Dimensions of Height: 17 Ft 11 In. Thickness: 8 In.
Model Width: 13 Ft 8.25 In.
Type of Block: ASTM-C-90 (X ) Running Bond Construction Mortar: Type "M" ( ) Stacked Bond
( ) Reinforced (X ) Other nrvva11 construction *
( X ) Uttreinforced Remarks
- In the vicinity of safety-related components, block wall is replaced with seismically designed drywall construction. The remaining block wall may fall with no effects on safety-related items.
Wall No: 24-1
_ - _ _ - . _ _ . - _ . _ ~ . _ ~ - - - - - - -
SUt14ARY OF RESULTS
' Turbine Building, North East Stairwell, West Wall, !
, g Upper Par't, Floor Elev. 23'-6" Dimensions.of Height: 8 Ft 6 In. Diickness: 8 In,.
Model Width: 13 Ft a 2s In.
Type of B1cck: AS'IM-C-90 (X ) Running Bond construction M rtar: Type "M" ( ) Stacked Bond
( ) Reinforced ( ) Other
( x ) Unreinforced f x ) One Way 29.73
( x ) Vertical Span 23.03 To Fgency ( ) Horizontal Span Range - Hz (Uncracked ( ) Two Way Section) ( ) 4-Edge Support To
( ) 3- Edge Support
( ) Top, ( ) Side, Missing
Response
Acceleration ( x ) One Way 0 17 g, ( ) Two hy- g,
(Uncracked Section) nu g, g, (SSE) fc T)
( X ) One Way:
I X ) krmal t Bed Joint, .25.0 vs 25.0 Flexural Tensile (CBE W Stresses - psi 3 (Uncrakced vs Section) (SSE+CL) (Allca cle)
( ) Parallel to Bed Joint, vs (CBE+DL) (Allowacle) vs (SSE+DL) (Allcwacle)
( ) Tso Way:
( ) Nc::al to Bed Joint, vs (CEE+DL) (A11 cwa =le) vs (SSE+CL) (A11cwamie)
( ) Parallel to Bed Joint, vs (CBE+CL) (Allcwacle) vs (SSE,CL) (Allcwa:le)
Wall is good for one way model with top Remarks support. Wall No: 24-2
SUleARY OF RESULTS Reactor Bldg. Southeast Stairwell-North Wall Fl. El . ( -) 19'-6" Dimensions of Height: 36 Ft 8.5 In. Thickness: 8 In.
Model Width: 16 Ft 3.5 In.
g og Block: AS'IM-C-90 ( ) Running Bond Construction Mortar: Type "M" ( x) Stacked Bond
( x ) Reinforced ( ) Other
( ) Uttreinforced SEE PAGE '10. EUR CDMBINATION MODCL ANALYSIS
~k I?
Wall No: 29
-S- .
~
SLM1ARY OF RESULTS
)
Reactor Bldg. Southeast Stair Well Iccation West Wall Fl. El. (-) 19'-6" Dimensions of Height: 8 41 Ft 0- In. 211ckness: In.
Model Width: 7 Ft 11.5 In.
Type of Block: ASIM-C-90 ( ) Running Bond Constructicn Mortar: Type "M" (x ) Stacked Bond
(* ) Reinforced ( ) Other
( ) Unreinforced SEE PAGE 'to, M CDMBINATION MODEL ANALYSIS c
Wall No: 30
-D- .<
m
SLM4ARY OF RESULTS - (Cont'd.)
( ) One Way -
Frequency ( ) Vertical Span To Range - Hz ( ) Horizontal Span (Cracked section) -
( X ) Two Way s1 To A.9 (N-Si dir
( x) 4-Edge Support
( ) 3-Edge Support 12.8 To 15.7 (E-W) dir
( ) Top, ( ) Side, Missing i Response ( ) One Way: g, ( X) Two Way: 0. 374 (N-S )dir Acceleration (CBE) OBE 0.189(d-W)dir (Cracked Section) g, SSE 0.614 (N-S)dir
] (SSE) 0.339 (E-W)dir Flexural Tensile I X ) Wo Way*
Stresses - psi ( X) Normal to Bed Joint (Cracked f(Steel): 1,665 vs 20,000 Section) (CBE+DL) (Allowable) 3,330* vs 36,000 (SSE+DL) (Allowable) f(Conc.): -37.6/-55.4 -396/-165 (Bending / Membrane) (CBE+DL) (Allowable)
(Capression) 1
-75.2*/-110. % -1,020/-330
- (SSE+DL) (A11cwacle) l f
(X ) Two Way:
(X ) Parallel to Bed Joint f(Steel) : 19,843 vs 30,000 (CBE+DL) (A11cwacle) 39,686* vs 63.000 (SSE+DL) (Allowacle)
(Bending / Membrane f(Conc.) : -74.2/-63.9 vs -396/-195 (OBE+DL) (Allowable)
Compression)
-148.4*/-127. % -1,020/-390 (SSE+DL) (Allowable)
- (SSE + DL) Conservatively taken as 2.0X (OBE + DL)
Remarks Combination Model Good for Cracked Section with One Side Edge Support on Walls 29 and 30< II311 NC- 29 & 30 SUN 4ARY OF RESULTS Reactor Bldg. Southeast Elevator Shaft-West Wall Iccation F1. El. ( 123'-6" Dimensions of Height: 26 Ft 7 In. Thickness: 8 In.
Model Width: 9 Ft 5.5 In.
g og Block: AS1N-C-90 ( ) Running Bond Construction , Mortar: Type "M" ( x ) Stacked Bond (x ) Reinforced ( ) Other
( ) Unreinforced y
SEE PAGE ' 15. FOR COMBINATION MODCL ANALYSIS Wall No: 31
I SU!HARY OF RESULTS Reactor Bldg. Southeast Stairwell Iccation North Wall Fl. El. ( ) 23'-6" Dimensions of Height: 1 Ft o 2s In. Thickness: 8 In.
Model . Width: io Ft 2.2s In.
T:
Type of Block: ASTM-C-90 ( ) Running Bond Construction Mortar: Type "M" (x ) Stacked Bond
( x ) Iteinforced ( ) Other
. ( ) Unreinforced SEE PAGE 15 ECR C]MDINATION MODEL ANALYSIS i
Wall No:
~
SIM4ARY OF RESULTS Reactor Bldg. Southeast Stairwell Incation West Wall Fl. El. ( ) 23'-6" -
Dimensions of *-* Height: ?s Ft 3.25 In. Thickness: 8 In.
Model Width: a Pt n_s In. .
g og Block: ASTM-C-90 ( ) Running Bond Construction Mortar: Type "M" (X ) Stacked Bond
( X ) Reinforced ( ) Other
( ) Unreinforced SEE PAGE 15 ECR COMBINATION MODEL ANALYSIS I
1 I
l 33 Wall No:
t w
SUbMARY OF RESULTS Reactor Bldg. Southeast Elevator Shaft I4 cation North Wall Fl. El. ( ) 23'-6" Dimensions of Height: 26 ' Ft 7 In. 'Ihickness: 8 In.
Model Width: ~IU"~ Ft 4.5 In.
Type of Block: AS'IM-C-90 ( ) Running Bond Construction mm: % "M" (X)Su h M (X ) Reinforced ( ) Other
( ) Unreinforced SEE PAGE ~15 FOR CDMBINATION MODEL ANALYSIS e
Wall No 45
- 14 ' -
SIM4ARY CF RESULTS - (Cont'd.)
( ) One Way -
Frequency H
-( ) Vertical Span To Qz ( ) Horizontal Span Section) '
(X-) Two Way 9.1 To 11.1 (N-S) dir (X .) 4-Edge Support 10.7 13.1 (E-W)
( ) 3-Edge Support To dir
( ) Top, ( ) Side, Missing Response ( ) One Way: g, ( X) Two Way:0.276 (N-S)dir Acceleration (CE) OE 0.217 (d-W)dir (Cracked Section) g, SSE 0.462(N-S)dir (SSE) 0.394(E-W)dir Flexural Tensile (X ) Two Way:
Stresses - psi (X), Normal to Bed Joint (Cracked f(Steel): 830 vs 20.000 Section)
(CE+DL) (Allowable) 1.660* vs 36.000 (SSE+DL) (Allowable) f(Conc.): -18.7/-39.7 93 -396/-226 (Bending Membrane)
(CE+DL) (Allowable)
-37.4*/-79. g -1,020/-452 (S$E+DL) (A11cw bie)
(X ) Two Way:
(X) Parallel to Bed Joint f(Steel) : 9' 9 vs 30.000 (CBE+0L) (A11cwaDie) 19.30a* vs 6tnnn (SSE+DL) (A11cwacle) f(Conc. ) : -17.1/-31.4 vs -396/-238 (Bending / Membrane *'
Compression) . -34. 2 */-62.8 ts -1,020/-476 (SSE*DL) (A11cwable)
(SSE + DL) Conservatively taken as 2.0 x (OBE + DL)
Remarks Combination Model Good for Cracked Section with side edge support on Wall No. 33 Wall No. 31,32,33, LL%
SLT ARY OF RESULTS
, Reactor Bldg. Shutdown Heat Exchanger Room.
. 14 cation North Wall. Interm. Section Fl. El. 51 -3 Di:tensicns of Height: 10 Ft 1 In. Thickness: 24 In.
Model Width: 1s Ft n In.
Block: AS'IM-C-90 ( ) Running Bend Type of Mortar: Type "M" ( x ) Stacked Bend Cens*caction Other grouted double Wythe
( ) Reinforced ( x ) 12 in. each wythe.
( x ) Unreinforced (x) Cne Way
( x ) Vertical Span 15.2 To 23.0 Fr g ency ( ) Heri:: ental Span Range - Hz (Uncracked ( ) Te Way Section) ( ) 4-Edge Su p To
( ) 3- Edge Support
( ) Tep, ( ) Side, Missing Response .21 g, ) Two Way: g,
( X ) One Way (
Acceleration (CEE) (CEE)
(Uncracked Sectien) .42 g, _g, (ssE)
(ssr>
( X ) One Way:
I X ) Nc::al to Bed Joint, 6.7 v3 40,0 Fleraral Tensile (CEE+CL) (haule)
Stresses - psi (Uncrakced 13.4 vs 67.0 Section) (SSE+CL) (A11cwacle)
( ) Parallel to Bed Joint, vs (CEE+CL) (Allcwacle) vs (S3E+CL) (Allcwacle)
( ) ?so Way:
( ) Ncn al to Bed Joint, vs (CEE,CL) (Allcwacle) ,
vs (SSE+CL) (Allowacie)
( ) Parallel to Bed Joint, vs (CEE+CL) (Allcwaclo) vs (S3I,CL) (Allewacie) 0.K. for One Way Model with top support for Re' arks south Wythe & intermediate support for north Wall No: 43 1 ..
Wythe. Provide additional support for pipe spring.can on south side.
.s SLM4ARY OF RESULTS l _ ,
Office Blag. . Battery Room I
Io::ation South Wall, East Section Fl. El. 35'-0" East Dimensions of Height: 1 Ft o In. Thic.V.ess: 6 In.
Model Width: 18 Ft to In.
Type of Block: AS'm-C-90 (x) Running Bond Ccnst M on Mortar: Type "M" ( ) Stacked Bcnd
( ) Reinforced ( ) Other
( x ) Unreinferced
( ) One Way
( ) Vertical Span To Frequency ( ) Horizontal Span Range - Hz (Uncracked ( ) te Way Section) ( ) 4-Edge Support 12.0 To 16.5
( x ) 3- Edge Sp
( ) Tep, k ) Side, Missing (West)
Response
Acceleration ( ) One Way g, ( x ) Two Way: .173 g, (Uncracked (CBE) (CsE)
Section) g, .345 g, tssri ec ei
( ) One Way:
Flexural Tensile ( ) Nocal to Bed Joint, vs Stresses - psi (CSE+CL) (Allcwacle)
(Uncrakced vs Section) (SSE,CL) (Mlcwa=le)
( ) Parallel to Bed Joint, vs (CBE+CL) (A11cwacle) vs (S5E+CL) (Allcwacle)
(x ) ?4 Way:
(x ) Neral to Bed Joint, 13.1 vs 25.0 (CEE.CL) (A.10wa1e) 33.0 vs 41.5 (SSE+CL) (Allcwacle)
( ) Parallel to Bed Joint, 17.6 vs 50.0 (CBI+CL) IAllcwacle1 36.0 vs 93.0 (SSI+CL1 (Allewa=le>
Conbination model good with top edge supp-Remarks ort for walls 17,18 r 53. Also provide cast 53
)., g,11 go:
verticle edge support for wall 53 and vertic to 17 r, 18 angle at the junction of walls is r, 53, ct
l l
l cALCCLATED SHEAR STRESSES AND ALILWARTF9 FOR STACKED BOND WATL4 Ou t-o f-Pl ane In-Plane Shear Flexural Shear (PSI)
(Shear (PSI) .
Wall No OBE SSE OBE SSE RDIARKS g 8 9.1 18.2 6.4 12.8
_d 13.0 26.0 3.5 6.9 __
19 . 1.2 2.4 20 Results are calculated 1.2 2.4 for critical Wall No. 19 NOCD 29 & 30 Combination 29.2 49.7 29.3 48,1 Model with hot 3-0 Seismic Force p - . . . _ _ _ _ . . . . __-..
31,32,33 31.4 48.2 28.8 47.5 Combination Model un _
with 3-D Seismic Force 43 1.5 '3 . 0 Allow.
stresses (PSI) 25.4 20.A nny For Unrein" forced 33.0 27.1 1.3 (CBE)
Masonry bNies (PSI) for 38.1 69.0*
reinforced masonry 49.5 89.7* 1.3 (OBE)
. Note: In plane shear stress is not' critical wherever it is not given.
- tl alls 29 and 30 form a continuous L shape structure and walls 31, 32, 33 and 45 form a continuous "h shape section. The above walls are reinforced with vertical rebar and Dur-0-b'all. Stress results from 3-D scisnic combination models, shows that in-nlanc shear dominates the stress pattern for the masonry material. Therefore, these walls behave like shear walls.
For the case of ?! + 0. the allowable in-plane shear stresses for both OBE KI and SSE cases are 2.08and 1.3* (2.04) respectively in accordance with our design criteria.
~
l CAIC.UTED SEAR STRESSES AND AUC4ABI.ES FCR RCNNING BCND WAILS Out of Plane '
In Plane Shear Flexural (PSI) l- ,
Shear (PSI)
! Wall No. OBE SSE OBE SSE REMARKS 5 6.6 9.9 6 6.6 . 9. 9 Results are calcula-lated for the cr1*J.c-al wall Nc. 6.
7 6.6 9.9 2.7 5.3 Combination model 17,18853l9.4 18.9 ! 7.3 14.6 with 3-D seismic l l l 21 3.7 6.3 22 l 7.7 12.1 l 23 11.1 15.3 l
24-l N/A N/A N/A N/A 6
24-2 7.9 l3.6 l 25 l 13.3 l 8.9 j 26 l11.2 17.0 1
l 27 7.8 11.9 l
l 28 Deleted from Anal.
I 44 i Deleted fron Anal .
l l
All ow. 38.1 31. 2 OBE Stresses
,(PSI) 49.5 40.6 1.3 (CBE)
Note: In plane shear stress is net critical wherever it is not given.
L