|
---|
Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217F8911999-10-13013 October 1999 Forwards Copy of FEMA Region IV Final Rept for 990623-24, Grand Gulf Nuclear Station Exercise.Rept Indicates No Deficiencies or Areas Requiring Corrective Action Identified During Exercise ML20216J8891999-10-0404 October 1999 Forwards Details of Existing Procedural Guidance & Planned Administrative Controls.Util Respectfully Requests NRC Review & Approval of Changes by 991020.Date Will Permit to Implement Changes & Realize Full Benefit During Refueling ML20217B0361999-10-0404 October 1999 Refers to Investigation Conducted by NRC OI Re Activities at Grand Gulf Nuclear Station.Investigation Conducted to deter- Mine Whether Security Supervisor Deliberately Falsified Unescorted Access Authorizations.Allegation Unsubstantiated ML20212J8151999-09-29029 September 1999 Forwards Insp Rept 50-416/99-12 on 990725-0904.One Violation Noted & Being Treated as Noncited Violation.Licensee Conduct of Activities at Grand Gulf Facility Characterized by Safety Conscious Operations,Sound Engineering & Maint Practices ML20216J6811999-09-28028 September 1999 Ack Receipt of ,Transmitting Rev 31 to Physical Security Plan for GGNS Under Provisions of 10CFR50.54(p). NRC Approval Not Required,Based on Determination That Changes Do Not Decrease Effectiveness & Limited Review ML20212J7361999-09-28028 September 1999 Forwards Insp Rept 50-416/99-11 on 990830-0903.No Violations Noted.Purpose of Insp to Review Solid Radioactive Waste Management & Radioactive Matl Transportation Programs ML20212J5321999-09-27027 September 1999 Forwards Insp Rept 50-416/99-14 on 990830-0903.No Violations Noted.Inspectors Determined That Radioactive Waste Effluent Releases Properly Controlled,Monitored & Quantified ML20216J7101999-09-26026 September 1999 Forwards NRC Form 536,in Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator License Examinations ML20216J8141999-09-26026 September 1999 Forwards Proprietary Renewal Applications for Licensed Operators for Wk Gordon & SA Elliott at Grand Gulf Nuclear Station.Proprietary Info Withheld ML20212F5521999-09-23023 September 1999 Forwards SER Accepting Util Analytical Approach for Ampacity Derating Determinations at Grand Gulf Nuclear Station,Unit 1 & That No Outstanding Ampacity Derating Issues as Identified in GL 92-08 Noted ML20212D9211999-09-16016 September 1999 Informs That NRC Staff Completed Midcycle PPR of GGNS on 990818 & Identified No Areas in Which Licensee Performance Warranted Insp Beyond Core Insp Program.Details of Insp Plan Through March 2000 Encl ML20212A9331999-09-13013 September 1999 Forwards Partially Withheld Insp Rept 50-416/99-15 on 990816-20 (Ref 10CFR73.21).One Violation of NRC Requirements Occurred & Being Treated as Ncv,Consistent with App C of Enforcement Policy ML20211P7631999-09-10010 September 1999 Discusses Staff Issuance of SECY-99-204, Kaowool & FP-60 Fire Barriers at Plant.Proposed Meeting to Discuss Subj Issues Will Take Place in Oct or Nov 1999 ML20212A6951999-09-0909 September 1999 Requests That Licensees Affected by Kaowool Fire Barriers Take Issue on Voluntary Initiative & Propose Approach for Resolving Subj Issues.Staff Plans to Meet with Licensees to Discuss Listed Topics ML20212A8341999-09-0909 September 1999 Requests That Licensees Affected by Kaowool Fire Barriers Take Issue on Voluntary Initiative & Propose Approach for Resolving Subj Issues.Staff Plans to Meet with Licensees to Discuss Listed Topics ML20211Q3471999-09-0909 September 1999 Forwards Federal Emergency Mgt Agency Final Rept for 990623 Plant Emergency Preparedness Exercise.No Deficiencies Noted & One Area Requiring Corrective Action Identified ML20211Q3091999-09-0909 September 1999 Forwards Safety Evaluation Accepting BWROG Rept, Prediction of Onset of Fission Gas Release from Fuel in Generic BWR, Dtd July 1996 ML20211Q4861999-09-0808 September 1999 Informs That Util Has Discovered Dose Calculation Utilized non-conservative Geometry Factor for Parameter.Calculation Error Being Evaluated in Accordance with Corrective Action Program ML20211Q0091999-09-0808 September 1999 Forwards Request for Addl Info Re Individual Plant Exam of External Events for Grand Gulf Nuclear Station,Unit 1. Response Requested by 000615 ML20211N4301999-09-0808 September 1999 Discusses Proposed Meeting to Discuss Kaowool Fire Barriers. Staff Requesting That Affected Licensees Take Issue on Voluntary Initative & Propose Approach for Resolving Issues ML20211P4171999-09-0707 September 1999 Ack Receipt of ,Which Transmitted Addendum to Rev 30 to Physical Security Plan for Ggns,Per 10CFR50.54(p).NRC Approval Is Not Required,Since Util Determined That Changes Do Not Decrease Effectiveness of Plan ML20211P4121999-09-0707 September 1999 Requests NRC Staff Review & Approval of Integrated Nuclear Security Plan (Insp) & Integrated Security Training & Qualification Plan (Ist&Q), for Use by All Entergy Operations,Inc.Encl Withheld,Per 10CFR2.790(d) ML20211K6061999-08-31031 August 1999 Informs That Plant Has No Candidates to Take 991006 Generic Fundamentals Exam ML20211K5641999-08-31031 August 1999 Forwards Rev 39 to Grand Gulf Nuclear Station Emergency Plan Non-Safety Related, IAW 10CFR50,App E,Section V. Changes Do Not Decrease Effectiveness of Plan & Continues to Meets Stds of 10CFR50.47(b) & Requirements of App E ML20211J2321999-08-26026 August 1999 Advises That Info Contained in to Support NRC Review of GE Rept, Prediction of Onset of Fission Gas Release from Fuel in Generic BWR, Will Be Withheld from Public Disclosure ML20211J3761999-08-25025 August 1999 Corrected Ltr Informing That Info Provided (on Computer Disk & in Ltr to Ineel ) Marked as Proprietary Will Be Withheld from Public Disclosure Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954,as Amended.Corrected 990827 ML20211F4881999-08-25025 August 1999 Advises That Info Submitted by 990716 Application & Affidavit Containing Diskette & to Ineel Mareked Proprietary Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954 ML20211F7751999-08-24024 August 1999 Forwards Insp Rept 50-416/99-10 on 990809-13.No Violations Noted.Insp Covered Licensed Operator Requalification Program & Observations of Requalification Activities ML20211C4381999-08-20020 August 1999 Forwards Rev 31 to Physical Security Plan for Protection of Grand Gulf Nuclear Station,Iaw 10CFR50.54(p).Util Has Determined That Rev Does Not Decrease Effectiveness of Plan. Encl Withheld,Per 10CFR73.21 ML20211C5101999-08-19019 August 1999 Forwards Certified Copies of Liability Insurance Policy Endorsements Issued in First Half of 1999 for Each Entergy Operations,Inc Nuclear Unit,Per 10CFR140.15 ML20211B3761999-08-16016 August 1999 Submits Voluntary Response to NRC AL 99-02, Operating Reactor Licensing Actions Estimates, for Fys 2000 & 2001, ML20211A9501999-08-12012 August 1999 Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl ML20211A9481999-08-12012 August 1999 Informs of Completion of Analysis of Heat Transfer in Cooler During Fan Coast Down & Concludes That Potential Exists for Steam Foundation,Under Conditions Where Dcw Sys Flow Is Lost Prior to Full Isolation Valve Closure ML20210P8411999-08-0909 August 1999 Forwards Insp Rept 50-416/99-09 on 990613-0724.No Violations Noted.Activities at Facility Generally Characterized by safety-conscious Operations,Sound Engineering & Maint Practices & Careful Radiological Work Controls ML20210N6401999-08-0303 August 1999 Informs That Eighteeen Identified Penetrations Will Be Restored to Conformance with Licensing Requirements Prior to Restart from RFO10,scheduled for Fall 1999,per GL 96-06. Example of Piping Analysis Being Performed,Encl ML20210L1461999-08-0303 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams ML20210K1951999-07-30030 July 1999 Forwards Insp Rept 50-416/99-03 on 990405-08 & 0510-11.No Violations Identified ML20211K7491999-07-30030 July 1999 Forwards Ltr Rept Documenting Work Completed Under JCN-W6095,analyses Performed at Ineel to Calculate Minimum Time to Fuel Pin Failure in Boiling Water Reactors (BWR) ML20210K6661999-07-29029 July 1999 Forwards Fitness for Duty Program Performance six-month Rept for Period Covering Jan-June 1999,per 10CFR26.71 ML20210F3591999-07-26026 July 1999 Forwards Proprietary Version & Redacted Version of Wyle Test Rept M-J5.08-Q1-45161-0-8.0-1-0,re Pressure Locking & Thermal Binding Test Program.Proprietary Version Withheld ML20210E3251999-07-23023 July 1999 Forwards Insp Rept 50-416/99-07 on 990622-25.No Violations Noted.Emergency Plan & Procedures During Biennial Emergency Preparedness Exercise Was Conducted ML20210D2401999-07-21021 July 1999 Informs of Resignation of Operator WE Griffith,License OP-20806-1,from Entergy Operations,Inc ML20209J0311999-07-16016 July 1999 Forwards Proprietary Info Supporting Review of Generic Alternate Source Term Request.Proprietary Info Withheld Per 10CFR2.790 ML20209G4791999-07-15015 July 1999 Forwards Proposed Emergency Plan Change as Addendum to Changes Previously Submitted Via GNRO-98/00028 & GNRO-99/00007,for NRC Review & Approval ML20210B1031999-07-15015 July 1999 Forwards Insp Rept 50-416/99-08 on 990502-0612.Determined That Three Severity Level IV Violations Occurred & Being Treated as Noncited Violations ML20210H3211999-07-14014 July 1999 Forwards Proprietary Info Supporting Review of 970506 Submittal of BWROG Rept, Prediction of Onset of Fission Gas Release from Fuel in Generic Bwr. Proprietary Info Withheld Per 10CFR2.790 ML20209D7511999-07-0909 July 1999 Responds to RAI on GL 92-01,rev 1,suppl 1, Rv Structural Integrity. as Result of NRC Review of Util Responses,Info Revised in Rvid & Rvid Version 2 Will Be Released ML20209D7671999-07-0101 July 1999 Submits Response to Violations Noted in Insp Rept 50-416/99-02 on 990222-26 & 0308-12.Corrective Actions: Contractor Performance Has Been re-evaluated in Regards to UFSAR Reviews ML20196K4901999-07-0101 July 1999 Discusses Relief Requests PRR-E12-01,PRR-E21-01,PRR-E22-01, PRR-P75-01,PRR-P81-01,VRR-B21-01,VRR-B21-02,VRR-E38-01 & VRR-E51-01 Submitted by EOI on 971126 & 990218.SE Accepting Alternatives Proposed by Util Encl ML20196J5711999-06-30030 June 1999 Advises That Versions of Submitted Info in 990506 Application & Affidavit, Re Proposed Amend to Revise Ts,Marked Proprietary Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20216J8891999-10-0404 October 1999 Forwards Details of Existing Procedural Guidance & Planned Administrative Controls.Util Respectfully Requests NRC Review & Approval of Changes by 991020.Date Will Permit to Implement Changes & Realize Full Benefit During Refueling ML20216J7101999-09-26026 September 1999 Forwards NRC Form 536,in Response to NRC Administrative Ltr 99-03, Preparation & Scheduling of Operator License Examinations ML20216J8141999-09-26026 September 1999 Forwards Proprietary Renewal Applications for Licensed Operators for Wk Gordon & SA Elliott at Grand Gulf Nuclear Station.Proprietary Info Withheld ML20211Q4861999-09-0808 September 1999 Informs That Util Has Discovered Dose Calculation Utilized non-conservative Geometry Factor for Parameter.Calculation Error Being Evaluated in Accordance with Corrective Action Program ML20211P4121999-09-0707 September 1999 Requests NRC Staff Review & Approval of Integrated Nuclear Security Plan (Insp) & Integrated Security Training & Qualification Plan (Ist&Q), for Use by All Entergy Operations,Inc.Encl Withheld,Per 10CFR2.790(d) ML20211K6061999-08-31031 August 1999 Informs That Plant Has No Candidates to Take 991006 Generic Fundamentals Exam ML20211K5641999-08-31031 August 1999 Forwards Rev 39 to Grand Gulf Nuclear Station Emergency Plan Non-Safety Related, IAW 10CFR50,App E,Section V. Changes Do Not Decrease Effectiveness of Plan & Continues to Meets Stds of 10CFR50.47(b) & Requirements of App E ML20211C4381999-08-20020 August 1999 Forwards Rev 31 to Physical Security Plan for Protection of Grand Gulf Nuclear Station,Iaw 10CFR50.54(p).Util Has Determined That Rev Does Not Decrease Effectiveness of Plan. Encl Withheld,Per 10CFR73.21 ML20211C5101999-08-19019 August 1999 Forwards Certified Copies of Liability Insurance Policy Endorsements Issued in First Half of 1999 for Each Entergy Operations,Inc Nuclear Unit,Per 10CFR140.15 ML20211B3761999-08-16016 August 1999 Submits Voluntary Response to NRC AL 99-02, Operating Reactor Licensing Actions Estimates, for Fys 2000 & 2001, ML20211A9481999-08-12012 August 1999 Informs of Completion of Analysis of Heat Transfer in Cooler During Fan Coast Down & Concludes That Potential Exists for Steam Foundation,Under Conditions Where Dcw Sys Flow Is Lost Prior to Full Isolation Valve Closure ML20210N6401999-08-0303 August 1999 Informs That Eighteeen Identified Penetrations Will Be Restored to Conformance with Licensing Requirements Prior to Restart from RFO10,scheduled for Fall 1999,per GL 96-06. Example of Piping Analysis Being Performed,Encl ML20211K7491999-07-30030 July 1999 Forwards Ltr Rept Documenting Work Completed Under JCN-W6095,analyses Performed at Ineel to Calculate Minimum Time to Fuel Pin Failure in Boiling Water Reactors (BWR) ML20210K6661999-07-29029 July 1999 Forwards Fitness for Duty Program Performance six-month Rept for Period Covering Jan-June 1999,per 10CFR26.71 ML20210F3591999-07-26026 July 1999 Forwards Proprietary Version & Redacted Version of Wyle Test Rept M-J5.08-Q1-45161-0-8.0-1-0,re Pressure Locking & Thermal Binding Test Program.Proprietary Version Withheld ML20210D2401999-07-21021 July 1999 Informs of Resignation of Operator WE Griffith,License OP-20806-1,from Entergy Operations,Inc ML20209J0311999-07-16016 July 1999 Forwards Proprietary Info Supporting Review of Generic Alternate Source Term Request.Proprietary Info Withheld Per 10CFR2.790 ML20209G4791999-07-15015 July 1999 Forwards Proposed Emergency Plan Change as Addendum to Changes Previously Submitted Via GNRO-98/00028 & GNRO-99/00007,for NRC Review & Approval ML20210H3211999-07-14014 July 1999 Forwards Proprietary Info Supporting Review of 970506 Submittal of BWROG Rept, Prediction of Onset of Fission Gas Release from Fuel in Generic Bwr. Proprietary Info Withheld Per 10CFR2.790 ML20209D7671999-07-0101 July 1999 Submits Response to Violations Noted in Insp Rept 50-416/99-02 on 990222-26 & 0308-12.Corrective Actions: Contractor Performance Has Been re-evaluated in Regards to UFSAR Reviews ML20209B6081999-06-30030 June 1999 Submits Response to NRC GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants. Disclosure Encl ML20195J6351999-06-16016 June 1999 Forwards Addendum to Rev 30 of GGNS Physical Security Plan IAW 10CFR50.54(p).Addendum Is Submitted to Announce Relocation/Reconfiguration of Plant Central & Secondary Alarm Station Facilities.Rev Withheld,Per 10CFR73.21 ML20195G0281999-06-0909 June 1999 Submits Summary on Resolution of GL 96-06 Re Eighteen Penetrations Previously Identified as Being Potentially Susceptible to Overpressurization ML20207F5041999-06-0202 June 1999 Forwards Updated Medical Rept IAW License Condition 3 for DA Killingsworth License OP-20942-1.Without Encls ML20206P2981999-05-13013 May 1999 Forwards Responses to RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs, Cancelling 990402 Submittal ML20206N1921999-05-10010 May 1999 Provides Revised Attachment 2 for Alternative Request IWE-02,originally Submitted 990429 Re Bolt Torque or Tension Testing of Class Mc pressure-retaining Bolting as Specified in Item 8.20 of Article IWE-2500,Table IWE-2500-1 ML20206J0941999-05-0404 May 1999 Forwards Proprietary & Redacted ME-98-001-00,both Entitled, Pressure Locking & Thermal Binding Test Program on Two Gate Valves with Limitorque Actuators. Rept ME-98-002-00 Re Flexible Wedge Gate Valves,Encl.Proprietary Rept Withheld ML20206E7811999-04-29029 April 1999 Proposes Alternatives to Requirements of ASME B&PV Code Section XI,1992 Edition,1992 Addenda,As Listed.Approval of Alternative Request on or Before 990915,requested ML20206D8171999-04-29029 April 1999 Informs NRC of Results of Plant Improvement Considerations Identified in GGNS Ipe,As Requested in NRC . Licensee Found Efforts Have Minimized Extent of Radiological Release in Unlikely Event That Severe Accident Occurred ML20206D7281999-04-28028 April 1999 Forwards South Mississippi Electric Power Association 1998 Annual Rept, Per 10CFR50.71(b).Licensee Will Submit 1998 Annual Repts for System Energy Resources,Inc,Entergy Mississippi,Inc & EOI as Part of Entergy Corp Annual Rept ML20206C9551999-04-22022 April 1999 Forwards 1999 Biennial Emergency Preparedness Exercise Scenario. Without Encl ML20205M1311999-04-0202 April 1999 Forwards Response to RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves. Info Was Discussed During Conference Call with NRC on 990126.Wyle Position Paper Encl.Subj Paper Withheld ML20205H5861999-04-0101 April 1999 Requests Relief from ASME B&PV Code,Section XI for Period of Time That Temporary non-code Repair Was in Effect,Per 10CFR50.55a(g)(5)(iii) ML20205F1781999-03-31031 March 1999 Forwards Consolidated Entergy Submittal to Document Primary & Excess Property Damage Insurance Coverage for Nuclear Sites of Entergy Operations,Inc,Per 10CFR50.54(w)(3) ML20196K7101999-03-26026 March 1999 Submits Reporting & Recordkeeping for Decommissioning Planning,Per 10CFR50.75(f)(1) ML20205A6511999-03-25025 March 1999 Responds to NRC Re Violations Noted in Insp Rept 50-416/99-01 on 990201-05.Corrective Actions:Program Will Be Implemented to Ensure Accessible Areas with Radiation Levels Greater than 1000 Mrem/H ML20204E7391999-03-15015 March 1999 Forwards Objectives for June 1999 Emergency Preparedness Exercise for Plant.Without Encl ML20207H9291999-03-0404 March 1999 Submits Update to Original Certification of Grand Gulf Nuclear Station Simulation Facility IAW Requirements of 10CFR55.45(b)(5) ML20207E3081999-03-0303 March 1999 Informs That GGNS Severe Accident Mgt Implementation Was Completed on 981223.Effort Was Worthwhile & Station Ability to Respond & Mitigate Events That May Lead to Core Melt Has Been Enhanced ML20207E3221999-03-0303 March 1999 Notifies of Change in Status of Mj Ellis,License SOP-43846. Conditional License Requested to Accommodate Medical Condition.Revised NRC Form 396 with Supporting Medical Evidence Attached.Without Encls ML20207A8161999-02-24024 February 1999 Forwards 1998 Annual Operating Rept for Ggns,Unit 1. Listed Attachments Are Encl ML20207A9901999-02-24024 February 1999 Informs That Util Has No Candidates from GGNS to Nominate for Participation in Planned Gfes,Scheduled for 990407 ML20203A1551999-02-0101 February 1999 Forwards Grand Gulf Nuclear Station Fitness for Duty Program Performance six-month Rept for Reporting Period 980701-981231 ML20202G0791999-01-26026 January 1999 Informs That He Mcknight Has Been Permanently Reassigned from Position Requiring License to Perform Assigned Duties. License Is No Longer Needed,Effective 981231 ML20199K4151999-01-20020 January 1999 Forwards Proposed Addendum to Emergency Plan Changes Previously Submitted Via GNRO-98/00028 for NRC Review & Approval as Required by 10CFR50.54(q) & 50.4 ML20199K6771999-01-14014 January 1999 Provides Notification of Planned ERDS Software Change Scheduled to Take Place on 990215 ML20199D8811999-01-11011 January 1999 Submits Response to SE JOG Program on Periodic Verification of motor-operated Valves,In Response to GL 96-05 ML20199D9521999-01-0808 January 1999 Informs That CE Cresap,License SOP-4220-4,has Been Permanently Reassigned from Position Requiring License & No Longer Has Need for License,Per 10CFR50.74 ML20199A6081999-01-0606 January 1999 Submits List of Plant Info Brochures Disseminated Annually to Public & List of Updated State &/Or Local Emergency Plan Info,Per NRC Administrative Ltr 94-07, Distribution of Site-Specific & State Emergency Planning Info ML20202B7531998-12-21021 December 1998 Submits Ltr Confirming Discussion with J Tapia,Documenting Extension for Response to NOV 50-416/98-13.Util Response Will Be Submitted by 990212 1999-09-08
[Table view] Category:UTILITY TO NRC
MONTHYEARAECM-90-0169, Forwards Operator Licensing Natl Exam Schedule for FY91 Through FY94,per Generic Ltr 90-071990-09-17017 September 1990 Forwards Operator Licensing Natl Exam Schedule for FY91 Through FY94,per Generic Ltr 90-07 AECM-90-0172, Forwards Endorsement 67 to Nelia Policy NF-257 & Endorsement 46 to Maelu Policy MF-1061990-09-17017 September 1990 Forwards Endorsement 67 to Nelia Policy NF-257 & Endorsement 46 to Maelu Policy MF-106 AECM-90-0174, Forwards List of Submittals Pending NRR Review Re Grand Gulf Licensing Activities1990-09-14014 September 1990 Forwards List of Submittals Pending NRR Review Re Grand Gulf Licensing Activities AECM-90-0165, Forwards Addl Info on NRC Bulletin 90-001, Loss of Fill-Oil in Transmitters Mfg by Rosemount1990-09-12012 September 1990 Forwards Addl Info on NRC Bulletin 90-001, Loss of Fill-Oil in Transmitters Mfg by Rosemount AECM-90-0158, Forwards Quarterly Status Rept for Reg Guide 1.97 Re Neutron Monitoring Sys for Period Ending 900630.Rept Includes Major Actions Completed to Date for Unit ex-core Sys.Estimated Milestone Schedule for Activities Also Encl1990-09-0808 September 1990 Forwards Quarterly Status Rept for Reg Guide 1.97 Re Neutron Monitoring Sys for Period Ending 900630.Rept Includes Major Actions Completed to Date for Unit ex-core Sys.Estimated Milestone Schedule for Activities Also Encl AECM-90-0163, Forwards Endorsement 61 to Nelia Policy NF-257,Endorsement 40 to Maelu Policy MF-106,Endorsement 62 to Nelia Policy NF-257,Endorsement 41 to Maelu Policy MF-106 & Endorsement 63 to Nelia Policy NF-2571990-09-0606 September 1990 Forwards Endorsement 61 to Nelia Policy NF-257,Endorsement 40 to Maelu Policy MF-106,Endorsement 62 to Nelia Policy NF-257,Endorsement 41 to Maelu Policy MF-106 & Endorsement 63 to Nelia Policy NF-257 AECM-90-0161, Forwards Quarterly Status Rept Re Degraded Core Accident Hydrogen Control Program, for Apr-June 19901990-08-30030 August 1990 Forwards Quarterly Status Rept Re Degraded Core Accident Hydrogen Control Program, for Apr-June 1990 AECM-90-0149, Forwards Semiannual Radioactive Effluent Release Rept for Jan-June 1990 & Rev 3 to Process Control Program1990-08-30030 August 1990 Forwards Semiannual Radioactive Effluent Release Rept for Jan-June 1990 & Rev 3 to Process Control Program AECM-90-0162, Forwards fitness-for-duty 6-month Rept for Period Ending June 1990,per 10CFR26.Success of Program Evident in Statistical Data Indicating Extremely Low Incident Rate1990-08-29029 August 1990 Forwards fitness-for-duty 6-month Rept for Period Ending June 1990,per 10CFR26.Success of Program Evident in Statistical Data Indicating Extremely Low Incident Rate ML20028G8591990-08-27027 August 1990 Forwards Updated Svc List to Be Used for Licensee Correspondence.Requests That Author Be Primary Addressee for All Correspondence Re Plant AECM-90-0144, Forwards Security Boundary Upgrade Bimonthly Status Rept for Period Ending 900731,per 900330 Commitment.Rept Covering Period 900801-0930 Will Be Submitted in Oct 19901990-08-22022 August 1990 Forwards Security Boundary Upgrade Bimonthly Status Rept for Period Ending 900731,per 900330 Commitment.Rept Covering Period 900801-0930 Will Be Submitted in Oct 1990 ML20056B3511990-08-20020 August 1990 Suppls Info Re 900806 Application for Amend to License NPF-29,changing Tech Specs on Alternate DHR Sys,Per NRC Comments.Proposed Tech Spec 3/4.5.2 Encl AECM-90-0147, Informs That Annual Emergency Preparedness Exercise for Facility Scheduled for Wk of 9108261990-08-14014 August 1990 Informs That Annual Emergency Preparedness Exercise for Facility Scheduled for Wk of 910826 AECM-90-0142, Forwards Supplemental Info Re 900705 Application for Amend to License NPF-29,revising Tech Specs Due to Addition of Alternate DHR Sys1990-08-0909 August 1990 Forwards Supplemental Info Re 900705 Application for Amend to License NPF-29,revising Tech Specs Due to Addition of Alternate DHR Sys AECM-90-0143, Notifies That Cd Bland No Longer Employed by Util,Effective 9007191990-08-0202 August 1990 Notifies That Cd Bland No Longer Employed by Util,Effective 900719 AECM-90-0139, Forwards Endorsement 68 to Nelia Policy NF-257,Endorsement 47 to Maelu Policy MF-106 & Revised Endorsement 35 to Maelu Policy MF-1061990-08-0202 August 1990 Forwards Endorsement 68 to Nelia Policy NF-257,Endorsement 47 to Maelu Policy MF-106 & Revised Endorsement 35 to Maelu Policy MF-106 ML20055J0551990-07-27027 July 1990 Forwards Summary of Environ Protection Program Re Const of Unit for 6-months Ending 900630,per Exhibit 2-A in Subsection 3.E.1 of CPPR-119 AECM-90-0136, Forwards Executed Amend 4 to Indemnity Agreement B-72,per NRC 891214 Request1990-07-27027 July 1990 Forwards Executed Amend 4 to Indemnity Agreement B-72,per NRC 891214 Request AECM-90-0130, Forwards Corrected Pages to Rev 17 to Physical Security Plan.Pages Withheld (Ref 10CFR73.21)1990-07-17017 July 1990 Forwards Corrected Pages to Rev 17 to Physical Security Plan.Pages Withheld (Ref 10CFR73.21) ML20044A9251990-07-0909 July 1990 Forwards Rev 1 to Relief Request I-00018 Correcting Valve Number & Description of One Component.Review & Approval Requested Prior to 901001 ML20044A7861990-06-29029 June 1990 Responds to NRC 900601 Ltr Re Violations Noted in Insp Rept 50-416/90-08.Corrective Actions:Operations Superintendent Counseled Individuals Re Inoperable Reactor Water Level Transmitter & Met W/All Shift Senior Reactor Operators AECM-90-0121, Withdraws 880831 & 890324 Proposed Amends,Deleting Certain Test,Vent & Drain Valves from Tech Spec Table 3.6.4-11990-06-27027 June 1990 Withdraws 880831 & 890324 Proposed Amends,Deleting Certain Test,Vent & Drain Valves from Tech Spec Table 3.6.4-1 AECM-90-0115, Forwards List of Followup Actions as Result of NRC Requalification Reexam of Three Licensed Operators on 900531.Lessons Learned Guideline Will Be Prepared Re Ability of Training Personnel to Evaluate Simulator Crew1990-06-26026 June 1990 Forwards List of Followup Actions as Result of NRC Requalification Reexam of Three Licensed Operators on 900531.Lessons Learned Guideline Will Be Prepared Re Ability of Training Personnel to Evaluate Simulator Crew ML20044A2931990-06-22022 June 1990 Responds to NRC Request for Addl Info Re Boraflex Gap Analysis.If Vibratory Ground Motion Exceeding OBE Occurs,Per 10CFR100,App a & as Previously Committed,Plant Will Be Shut Down.Listed Addl Surveillance Will Be Performed ML20043G6231990-06-14014 June 1990 Forwards Evidence That Cash Flow Would Be Available for Payment of Deferred Premium Obligation for Facility.Sys Energy Resources,Inc Responsible for Generating 90% of Required Cash Flow ML20043G3341990-06-11011 June 1990 Forwards Rev 9 to GGNS-TOP-1A, Operational QA Manual, for Evaluation ML20043G5861990-06-0808 June 1990 Forwards Bimonthly Status Repts Re Security Boundary Upgrade Project for Period Ending 900531 ML20043F5121990-06-0808 June 1990 Forwards List of Directors & Officers of Entergy Operations, Inc.Operation of All Plants Transferred to Entergy on 900606 ML20043E8011990-06-0707 June 1990 Forwards Nonproprietary ANF-90-060(NP), Criticality Safety Analysis for Grand Gulf Fuel Storage Racks W/ANF-1.4 Fuel Assemblies. ML20043E7831990-06-0707 June 1990 Forwards Updated Svc List to Be Used Re Plant Correspondence.Requests WT Cottle Be Primary Addressee for All Correspondence Concerning Plant ML20043E8161990-06-0606 June 1990 Informs That Sys Energy Resources,Inc Received Necessary Regulatory Approvals to Transfer Performance Activities for Facility to Entergy Operations & All Conditions in Amend 9 to CP CPPR-119 Implemented,Effective on 900606 ML20043F2061990-06-0606 June 1990 Forwards 1989 Annual Financial Repts for Sys Energy Resources,Inc & South Mississippi Electric Power Assoc ML20043E8111990-06-0606 June 1990 Informs That Sys Energy Resources,Inc Received Necessary Regulatory Approvals to Transfer Operating Responsibility for Facility to Entergy Operations & All Conditions in Amend 65 to License NPF-29 Implemented,Effective on 900606 ML20043C8611990-05-31031 May 1990 Forwards Preliminary Drafts of Plant Specific Tech Specs in Order to Facilitate NRC Validation of BWR Owners Group Improved Tech Specs,Per NRC Request.Understands That Util & NRC Will Meet During Wk of 900716 to Discuss NRC Review ML20043B6811990-05-24024 May 1990 Forwards Degraded Core Accident Hydrogen Control Program, Quarterly Status Rept for Jan-Mar 1990 ML20043B6021990-05-23023 May 1990 Confirms NRC Understanding That Safety Evaluation Will Be Written for Use of New Tech Spec 3.0.4 Flexibility Regardless of Plant Condition at Time Flexibility Required ML20043B2471990-05-18018 May 1990 Forwards Final Response to Generic Ltr 89-04, Guidance on Developing Acceptable Inservice Testing Programs & Rev 4 to Pump & Valve Inservice Testing Program. ML20043A9651990-05-17017 May 1990 Forwards Draft Tech Specs for Power Distribution Limits,Rcs, ECCS & Plant Sys as Part of Util Involvement W/Bwr Owners Group as BWR-6 Lead Plant ML20042G6931990-05-0909 May 1990 Forwards Rev 4 to Fire Hazards Analysis. Design Changes Include Installation of Alternate DHR Sys & Access Hatch in Pipe Chase ML20042G8681990-05-0909 May 1990 Forwards Response to Recommendations Re Areas of Concern Noted in NRC SER Dtd 900316 & 900316 Request for Addl Info Re Design Criteria for Cable Tray Supports in Turbine Bldg ML20042G6731990-05-0909 May 1990 Notifies of Cancellation of Emergency Plan Procedure 10-S-01-13, Onsite Radiological Monitoring. Info Incorporated Into Procedure 10-S-01-14,Rev 13, Radiological Monitoring. ML20042F4891990-05-0404 May 1990 Requests Extension of 90 Days to Provide Addl Time for Securities & Exchange Commission Review Re Implementation of Amend 65 to License NPF-29 ML20042F4441990-05-0404 May 1990 Forwards Response to Generic Ltr 89-19 Re USI A-47, Safety Implications of Control Sys in LWR Nuclear Power Plants. Plant Has Adequate Automatic Reactor Vessel Overfill Protection,Procedures & Tech Specs ML20042F1791990-04-30030 April 1990 Responds to NRC 900402 Ltr Re Violations Noted in Insp Rept 50-416/90-03.Corrective Actions:Valves Closed,Effectively Isolating Flow of Contaminated Water Into Makeup Water Sys & Demineralized Water Sys Flushed & Cleaned of Contamination ML20042F1811990-04-30030 April 1990 Responds to Generic Ltr 89-15, Emergency Response Data Sys. Util Volunteers to Participate in Emergency Response Data Sys ML20042F3711990-04-30030 April 1990 Forwards Certificate of Insurance for Nuclear Property Insurance Submitted by Nuclear Mutual Ltd for Policy Period 900401-910401 & Certificate of Insurance Evidencing Increased Excess Property Insurance,Per 900330 Ltr ML20042F1751990-04-30030 April 1990 Advises That Util Will Not Be Able to Provide Complete Supplemental Summary Rept on Dcrdr by 900430,as Indicated in Util 891221 Ltr.Supplemental Rept Will Be Submitted by 900930 ML20012F3311990-04-0202 April 1990 Forwards GE Affidavit Requesting That All Drawings Presently Denoted as Proprietary in Rev 4 to Updated FSAR Re Offgas Sys Should Remain Proprietary (Ref 10CFR2.790) ML20012E2961990-03-26026 March 1990 Forwards Updated Svc List for NRC Correspondence to Util. Facility Fee Bills Sent to Wrong Primary Addressee ML20011F2171990-02-23023 February 1990 Responds to NRC 900131 Ltr Re Violations Noted in Insp Rept 50-416/89-30.Corrective Actions:Quality Deficiency Rept Initiated to Document & Resolve Incident & Incident Rept & Reportable Events Procedure Enhanced 1990-09-08
[Table view] |
Text
_ _ _ _ _ _ _ _ _ ____ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
MISSISSIPPI POWER & LIGHT COMPANY Helping Build Mississippi P. O. BOX 16 4 0. J A C K S O N , MISSISSIPPI 39205 U,"', N January 19, 1982 s @-g g# '; ' ,' 3 74Uf,1 E A H Pho(N JCitote id I' A HIDM P4I
~
U.S. Nuclear Regulatory Commission C. ,p Office of Nuclear Reactor Regulation ^ C ' '
Washington, D.C. 20555
[4
.,> ,f i
l Attention: f! r . liarold R. Denton, Director N.~/, ,
\
Dear f!r. Denton:
's '
SUlUECT: Grand Gulf Nuclear Station Units 1 and 2 Docket Nos. 50-416 and 50-417 File 0260/0217/L-860.0 IE Bulletin 80-11, Category I tlasonry Walls Reference AECt!-80/206 AECt!-82/29 Fli s s . s s i pp i power & Light's (FIP&L) letter, AECt!-80/206, was our response to your request of Apri1 21, 1980, entitled "Information Request on Category I flasonry Walls Employed by Plants under CP and OL Review."
Subsequent to the issuance of the NRC's information request on Category I masonry walls, IE Bulletin 80-11 was issued. Although this bulletin applies only to power reactor facilities with an Operating License, we initiated a re-evaluation of concrete masonry walls in Category I structures at Grand Gulf. To date, the following work has been completed:
- 1. A comprehensive field survey was carmiacted between November 1980, and Janua ry 1981. N s survey identified all safety-related items attached to or 1, ited in proximity to masonry walls at that time. In add;ttur., data was recorded to determine the wall geometry, location of penetrations and type of closures, location and magnitude of attachment loads, type of wall support, and any additional information which could affeet the structural int egrity of the walls.
- 2. I!pon completion of the survey, the information obtained was used to re-evaluate the ability of these walls to perform QQ [
their intended functions during all postulated loadings, V without impairing the integrity of Category I systems and 5 components attached to or in proximity to these walls.
Criteria were generated for the re-evaluation, which consider I /
present state-of-the-art analysis and design techniques, as well as licensing commitments contained in the FSAR.
- 3. Any masonry walls which did not conform with the criteria were modified as required, and appropriate design drawings were issued to implement these modifications.
8201260348 820119 PDR ADOCK 05000416 G PDR 1 ember Middle South Utilities System
. . _ _ _ _ _ _ _ _ . _]
AECrl-82/29 MICSISSIPPI POWER & LIGHT COMPANY Page 2 During the fall of 1981, a second field survey was initiated. The purpose of this survey was to identify any additional wall attachments or changes in wall configurations subsequent to the first survey. The walls were then re-evaluated as necessary, and modification designs, if required, were issued.
Attachment I constitutes our formal report on the re-evaluation of concrete masonry walls at Grand Gulf. This report contains all information requested in IE Bulletin 80-11, as well as a comparison of the Grand Gulf masonry wall design criteria with Revision 1 of the NRC's
'3E!! Interim Criteria for Safety Related ?!asonry Wall Evaluation" (July 1981). As further substantiated in Appendix D of Attachment 1, ali concrete masonry unit (CflU) walls, either as constructed or as i modified, satisfy the SEB Interim Criteria load combinations and allowable stresses.
Pfodifications determined to be required based on our CtlU wall review will be completed prior to restart after the first regularly scheduled refueling outage.
This completes our response on IE Bulletin 80-11. If you have any questions, please advise.
Yours truly,
/
^
.; C.b' Y L. F. Dale
,. 11anager of Nuclear Services DDW/Silli/JDR:Im
, Attachment i
a cc: tir. N. L. Stampley (w/a) fir. G. B. Taylor (w/a) 1 t!r. R. B. ficGehee (w/a) fir. T. B. Conner (w/a)
, tir. Richard C. DeYoung, Director (w/a)
Office of Inspection & Enforcement U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Dr. Franz Schauer, Chief (w/a)
Structural Engineering Branch Nuclear Regulatory Commission Washington, D.C. 20555 AE5J2
/ I
O 4
s M"
W REPORT ON THE RE-EVALUATION OF CONCRETE MASONRY WALLS IN RESPONSE TO NRC IE BULLETIN 80-11 FOR THE GRAND GULF NUGLEAR PLANT O
E
Attachment 1 i
i e
TABLE OF CONTETTS 1.0 General 2.0 Description of asonry Walls 3.0 Construction Practices 4.0 Re-evaluation Criteria and Co=centary 5.0 Results of Evaluation 6.0 Modifications 7.0 Conclusions 8.0 Planned Future Actions t
- y l
l t e
i
, Attachment I l i l l APPENDICES - !
i i, A- Survey Procedure for Concrete Masonry Wells in Category I Buildings i l
)
i B- Design Criteria for the Re-evaluation of Concrete Masonry Walls in i Category I Structures i
l C- Con:mentary on Criteria for the Re-evaluation of Concrete Masonry !
Walls i - D- Comparison of Grand Gulf CMU Wall Design Criteria with Revision 1 ;
i of NRC's "SEB Interim Criteria for Safety Related Masonej Wall i Evaluation" (July 1981) {
[
l '
E- Architectural Specifications l i
l F- Floor Plan Locations of Masonry Walls' !
i t G- Wall Configuration and Function Su==ary f l Table I - Control Building Walls i Table II - Auxiliary Building Walls
] H- Masonry, Reinforcement, and Lintel Details 1- Modification Design Examples {
{ J- Block Wall Program Manual l i
I i .
I i
i f
i
! L i
i e
I i
t i
F 5
h I. ,
\
I I L
. \
l 4 r
, . .-. . - - - . . _ . _ . - .- , - - - - - - - - . - . . . , , , . . - - , - - - . . - . , . ~ - , , , . , - . . - . . , . - - . , - - - , .
- L a
! [
] 1.0 GENERAL 2
' l This report contains the results of the re-evaluation of concrete !
masonry walls for the Grand Gulf Nuclear Station and serves as a !
complete response to the NRC's "SEB Interim Criteria for Safety l Pelated Masonry Wall Evaluation" and IE Bulletin 80-11 dated May 8, ,
1980. Walls in the Control Building (Units 1 & 2), and the
(
l Auxiliary Building (Unit 1 only) were evaluated. No concrete t j masonry walls were constructed in the Containment or Diesel Ge:wrator Buildings, or in the Standby Service Water Cooling Tower
] hasins.
i
}
[
2.0 DESCRIPTION
OF MASONRY WALLS [
t i
j 2.1 - Identification and Function of Walls j Concrete masonry walls are referenced by elevation number (shown on Architectural design drawings) and by survey number (see Appendix A
" Survey Procedure for Concrete Masonry Walls," Paragraph 3.0 for survey i numbering method). Wall Jocations are shown on Architectural design !
! drawings (see Appendix F for floor plan locations). Two field surveys !
(January 1981 and October 1981) were conducted to identify walls with ;
) safety-related items attached or which are located in proximity to !
safety-related systems or equipment. A summary which includes wall .
j dimensions, section properties andlwall function is tabulated in f
l Appendix C. '
[
f All concrete masonry walls within the scope of the survey are internal boundary / partition walls located in the Control and Auxiliary Buildings.
Forty-four walls in the Control Building are load bearing walls i
) supporting intermediate reinforced concrete slabs; all other walls are l non-load bearing. None of the Control or Auxiliary Building masonry ;
walls are subjected to thermal, missile impact, postulated pipe break, e pipe whip, or jet impingement forces. All are designed to resist !
t tornado depressurization loads. A secondary function of these walls is ;
to provide support for relatively lightweight equipment including small piping, conduit, in'strumentation lines and electrical, communication and l' i
fire protection panels.
}
2.2 - Wall Configuration and Details j t
l All masonry walls are single or multi-wythe units laid in a running bond 7 pattern. Each wall is constructed of lightweight, load bearing concrete l 3 masonry blocks with widths of 4", 8" or 12". In the Auxiliary Building.
' l 3/16" x #9 ga. heavy duty horizontal reinforcement is placed in every i bed joint for single wythe walls and in every other bed joint for !
, multi-wythe walls. In the Control Building, the same type of horizontal
- reinforcement is provided at every course for all vertically reinforced ,
valls and at every other course for remaining walls. Walls at Elev. i 111'-0" of the Control Building use bond beams with two #4 horizontal bars in every other course in lieu of the reinforcement described
- above.
i ;
l l
l i
. i
[
- i l
i i i i
l Vertical reinforcement for Auxiliary Building walls consists of two #5 i
bars at 8" 0.C. with all masonry cells filled with grout. Two f5 vertical bars at 16" 0.C. are used for typical valls in the Control Building and alternate cells are filled with grout. All vertical reinforcement is lapped with #5 dowels embedded in the supporting floor slab with epoxy grout.
Lintels are used above penetrations where required by design. Typical !
. lintel types included steel plates, channels and bond beams. !
The top of each wall designed to span vertically is supported by structural angles or tube steel members. Top supports are connected to
' structural steel beams or main concrete slabs and are designed to allow for dif ferential vertical slab displacements. Top supports are not required for walls designed to span horizontally, but nevertheless are generally provided. (See Appendix H for typical masonry, reinforcement t and lintel details, and boundary conditions.) -
t 2.3 - Materials of Construction -
2.3.1 Masonry Units - Concrete masonry units are either two-core standard, three-core standard, or two-core open end types. Each is Grade N-1, hollow, lightweight, load bearing and has a uniform color, texture and finish conforming to ASTM C-90.
2.3.2 Reinforcement - Horizontal joint reinforcement is Ladur type manuf actured by Dur-0-Wall. It is fabricated from 3/16" diameter longitudinal rods and #9 gauge cross rods conforming to ASTM A82 and has a yield strength of 70 ksi. Horizontal bond beam reinforcement, vertical reinforcement, and vertical dowels are all Grade 60 reinforcing bars meeting the requirements of ASTM A615.
2.3.2 Grout and Mortar - Grout used to fill masonry cells and .
mortar (Type M or Type PL) used at joints have minimum 28 day
+
compressive strengths of 2500 psi. Type M mortar conforms to the i requirements of ASTM C 270 and Type PL eortar and core grout each conform to ASTM C 476.
3.0 CONSTRUCTION PRACTICES -
! I All block walls were constructed in accordance with the requirements of \
Specification 9645-A-004.2 " Furnish, Delivery, and Erection of Concrete '
Masonry Units," Paragraph 8.0 Field inspection practices were governed '
by Paragraph 11.0 of the same specification. Attachments of Q-systems , x; and equipment to CMU walls are documented and shown on design drawings.
' All other attachments conform to the requirements set forth in '
Specification 9645-A-004.3 " Procedures Governing Concrete Masonry Unit Wall Attachments for Non-Category I, Non-Seismic Installations." '(See , '
Appendix E for Specifications 9645-A-004.2 and 9645-A-004.3.) "3
~
i . ;
s j
, 'A- s - ,
. ~; ;
1 I
/ \
- - - .. .. ,r. . - , . _ - _ , - - - - - - -. .--g n_. -,- ~ ,
._ _. _- - _. . . - =. - - -. __
,g _O 4 i
i 4.0 RE-EVALUATION CRITERIA _AND C0!!MENTARY 4.1 -Criteria Appendix B contains the criteria used for the re-evaluation of the cricrete masonry walls with safety related systems or equipment attached to or in prcximity to the walls in Category 1 structures. Appendix D compares the Grand Gulf masonry wall design criteria with the NRC SEB Interim Criteria and concludes that GGNS and SEB criteria are or will be satisfied
) by Ct!U walls at GGNS.
Licensing commitments contained in the Final Safety Analysis Report (FSAR) as related to loads and load combinations are incorporated
. in the criteria. In addition, the criteria considers present day state-of-the-art analysis and design techniques as follows:
4.1.1 Stress Criteria '
i
- a. Consideration of cracking for frequency determinations
- b. Recognition of potential plane of weakness at the collar joint.
- c. Stress increase factors for abnormal and extreme i environmental loa 4s.
- d. Realistic damping values
- e. Interstory drift F. Frequency variationr due to uncertainties in material properties and effective mass.
4.2 -Commentary on the Criteria
~
Appendix C is the commentary on the criteria and contains detailed justification of the criteria by reference to existing codes, test data and standards of practice.
4.3 -Loading Considerations e
' * = The concrete masonry walls in the Control and Auxiliary Buildings were analyzed subject to the loading combinations listed in Appendix B, " Design Criteria for Concrete Masonry Walls la Category I St ructuras. " 'The following is a consideration of the applicability of each design lodd:
- 1) There are no exterior masonry walls; therefore no walls are exposed to wind loads.
T
- 2) -Thermal loads are not applicable because there is no equipment or piping causing large temperature differentials on or in the proximity of the walls in the Control and Auxiliary Buildings.
f
, s T*
. u -
- a' ,
~
,g ~,
~,' '
1 l
. l 3
i The locations of.high energy piping is such that loads due 4
3) j to postulated pipe breaks do not i= pose additional forces on masonry walls.
1 i -
Because of the above considerations, dead load, attachment loads, seismic accelerations and tornado depressurization are the only forces acting on the masonry walls.
" 5.0 RESULTS OF EVALUATION A Bechtel survey team performed two detailed walkdowns per the " Survey Procedure for Concrete Masonry Walls" (see Appendix A) . Walkdown data (as-built sketches showing wall configuration, penetrations and I
attachments) was used in the analysis of the concrete masonry walls and l served as a basis for wall support modifications. As-built wall elevations showing all penetrations and wall support steel were prepared
, after the modification designs were completed. All wall penetrations and attachments subsequent to the second survey have required project engineering approval.
A total of 246 walls in the Control Building and 42 in the Auxiliary Building were surveyed and are listed in Table I & II of Appendix G.
I Masonry walls were considered accep' table only ~when stresses did not exceed the allowable stresses permitted by the evaluation criteria. -
Where necessary, modifications were designed to insure that stresses remained below allowables.
Intersjory drif t ef fects were considered in the analysis. The differential seismic deflections and the related masonry wall strains were found to result in very small stresses, and therefore, have no adverse effect on vall integrity.
All walls with safety-related equipment attached or in proximity were designed to resist SSE loadings. All other walls were required only to withstand UBC earthquake loadings.
Based on the results of the evaluation, a total of 67 walls in the Control Building and 13 valls in the Auxiliary Building required some type of modification.
6.0 MODIFICATIONS A typical masonry wall modification involved adding external support steel to reduce the horizontal span of the wall. Wide flange columns were normally provided to act as support points and utilize wall strength in the horizontal direction. An alternate modification approach was to provide horizontal support steel (usually WF beams, tube steel or channels) to reduce the vertical span of the wall. In addition, occasional strengthaning of existing wall support steel was necessary to permit the steel to carry attach =ent loads not present at the time of the original design.
7.0 CONCLUSION
S Based on the re-evaluation performed in accordance with the requirements of IE Bulletin 80-11, and the implementation of structural modi fications where needed, it is ccncluded that the concrete masonry walls will meet the SEB Interim Criteria and perform their intended functions. Therefore, the function of Category I systems and components attached or in proximity to the walls will not be impaired.
0.0 PLANNED FUTURE ACTIONS Outstanding items still to be completed at a future date to provide a final response to NRC IE Bulletin 80-11 include:
- 1) Survey and evaluation of Unit 2 Auxiliary Building CMU walls.
I e
l l
~
l l
- --a 2 k e L -A. .--a - w a.a 1
- . **
O I
e 4
k e
=
9 APPENDIX A I
e 9
4 J
G l
i e
i i
h L
l l
,, , ,. , ,n . - ,,--,- . . . , .- - --- - - - - - ,, - - - - , , , . , -- -- - , . ,- - - . , , - - .