Letter Sequence RAI |
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Results
Other: ML20062B275, ML20062B279, ML20062B282, ML20062B286, ML20062B419, ML20062B425, ML20062B959, ML20062C142, ML20062C627, ML20062D348, ML20126B604, ML20126C064, ML20147E632, ML20147E640, ML20147F089, ML20147F096, ML20148A060, ML20150A644, ML20150A665, ML20150F064, ML20195C143, ML20195C345, ML20195C351, ML20195C364, ML20195C374, ML20195C385, ML20195C400, ML20195C458, ML20195C462, ML20195C533, ML20197D480
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MONTHYEARML20195C3451978-04-28028 April 1978 Informs That Structure of Walls in Control Bldg Does Not Meet Seismic Criteria for Sar.Reanalysis Confirms Control Bldg Will Maintain Structural Integrity & Plant Will Retain Functional Capability Under Design Loads Project stage: Other ML20195C3641978-05-26026 May 1978 Clarifies Items 2 & 3 of DG Eisenhut 780502 Memo Re Proposed Mod to Plant Spent Fuel Storage Rack Proceedings.Design Engineer Activities in Fuel Bldg Design Should Be Considered Supporting Role Project stage: Other ML20195C3851978-06-29029 June 1978 Affidavit of Chales M. Trammel,Iii.* Staff Concluded That an Amendment Authorizing Operation of Trojan Nuclear Power Plant Pending Upgrading of Seismic Capability of Control Bldg Walls Would Constitute a Decrease in Safety Margin Project stage: Other ML20195C4001978-06-29029 June 1978 Affidavit of LC Shao Re Control Bldg Design Errors Resulting in Substantially Weaker Walls than Intended by Original Design criteria.As-built Structure Has one-half of Seismic Capacity & Safety Margin Project stage: Other ML20195C3511978-06-29029 June 1978 Forwards Affidavits of CM Trammell & LC Shao Re Safety Significance of Control Bldg Design Deficiencies & NRC Findings Concerning Significant Hazards Considerations Project stage: Other ML20195C3741978-06-30030 June 1978 Forwards Proposed Schedule of Actions to Bring Plant Control Bldg Into Substantial Compliance Ww/Requirements & Intended Design Margins.Detailed Description of Actions,Design Changes & Mods Will Be Submitted Prior to 780901.W/o Encl Project stage: Other ML20195C4581978-08-19019 August 1978 Forwards NRC Questions & Licensee Responses,780804-17 Based on Info Provided by Bechtel Re Control Bldg.All Walls Except 1B,2 & 3 Have Dowel Capacities Exceeding Shear Capacities Controlled by Either Shear or Bending Project stage: Other ML20195C4621978-08-21021 August 1978 Forwards Final NRC Responses to Questions 6 & 10 Re Control Bldg Mods,Based on Info Provided by Bechtel.Equipment in Structure Should Continue to Be Capable of Resisting Seismic Loadings Resulting from Real Earthquakes Project stage: Other ML20195C5331978-08-22022 August 1978 Responds to Re Amendment Permitting Temporary Operation of Plant Independent of Public Hearing.Law Requires Hearing to Be Held in Connection W/Amend to OL Project stage: Other ML20150A6081978-08-30030 August 1978 Forwards Request for Addl Info Re Control Bldg Per Seismic Nonconformance Project stage: RAI ML20150A6141978-09-0101 September 1978 Forwards Preliminary Results of Stardyne Finite Element Analysis of Trojan Control-Auxiliary-Fuel Bldg Complex & Assessment of Seismic Load Resistance of Bldg as Presented at 780828 Meeting. Lic. NPF-1 Project stage: Meeting ML20195C1431978-09-0707 September 1978 Responds to Commissioner Davis Addressed to Commissioner Bradford & Expressing Concerns Re non-conformance to Specs of Control Bldg at Plant & Effect of Facility Shutdown on Rate Payers Project stage: Other ML20147C2411978-09-12012 September 1978 Forwards Corrected Supplementary Info Transmitted by Ltr Project stage: Supplement ML20150A6651978-09-20020 September 1978 Responds to Specified SSE Event.Stardyne Dynamic Analysis Was Used to Determine Structural Capacities & Forces. Concludes That Control Bldg Can Withstand SSE Event Safely Project stage: Other ML20150A6441978-09-20020 September 1978 Forwards Final Results of Rev & Evaluation of Recent Stardyne Finite Element Analysis for Existing Control Bldg of Subj Facil.Suppl Structural Evaluation Response to Specified SSE Event,& Response to Questions Encl Project stage: Other ML20150A6581978-09-21021 September 1978 Order Re Responses to NRC Interrogatories by Coalition for Safe Pwr & Consolidation.Cfsp Must:Respond W/In 14 Days to S1,S2,E1,G1,G2,G3,G8 & All Other Interrogatories;Clarify the Status of Spokesmen.Motion for Reconsideration Is Denied Project stage: Approval ML20062B9611978-09-28028 September 1978 Forwards 780628 Memo to R Mattson Re Info on Failures of safety-related Pipe Supports at Millstone 1 & Design Deficiencies on Similar Equipment at Shoreham.Aslb Notified of Pipe Support Base Plate Design Project stage: Approval ML20147E6321978-10-0303 October 1978 Transcript of Dj Broehl Testimony Re Plant History, Chronology of Events Since Apr 1978 & Summary of Licensee Efforts to Ensure Safe Interim Operation of Control Bldg Project stage: Other ML20147E6401978-10-0303 October 1978 Transcript of SR Christensen Testimony Re Description of Seismic Instrumentation & Engineering Investigations to Be Conducted Following Earthquake Project stage: Other ML20148A0601978-10-0606 October 1978 Direct Testimony of Harold Laursen Re Assignment to Eval Ability of Subj Facil Bldg Shear Walls to Resist Seismic Loading.Determined Shear Walls Can Withstand .25g Safe Shutdown Earthquake Project stage: Other ML20062C1421978-10-11011 October 1978 Notice of Evidentiary Hearing on Issue of Interim Operation & Limited Appearance.Hearing to Determine Whether Interim Operation Should Be Permitted Prior to Mods Required by Order Will Be Held on 781023 & 1030-1101 Project stage: Other ML20062B2751978-10-13013 October 1978 Forwards Ks Herring Testimony on Structural Adequacy of Trojan Control Bldg for Interim Operation & Rt Dodds & Je Knight Testimony on Seismic Features Relevant to Facility Safety Project stage: Other ML20062B2791978-10-13013 October 1978 Testimony Verifying That Reasonable Assurance Exists That Shear Walls Will Withstand SSE or Obe.Original Intended Margins of Safety Reduced & Should Be Restored Project stage: Other ML20062B2821978-10-13013 October 1978 Testimony Describing Insp of Humboldt Bay Following 5.4 Richter Magnitude Earthquake on 750609 & Std Insp Procedures After Seismic Event.Procedures to Be Followed During Earthquake Detailed Project stage: Other ML20062B2861978-10-13013 October 1978 Testimony Responding to ASLB Questions Re Effects of Seismic Event on Plant Features Important to Maintaining Safety of Facility.Certificate of Svc Encl Project stage: Other ML20148C0251978-10-13013 October 1978 Responds to NRC 781011-13 Questions Re Supplemental Structural Evaluation of Control Bldg,Particularly Shear Wall Capacity.Certificate of Svc Encl Project stage: Supplement ML20147F0891978-10-16016 October 1978 Testimony of Bart Withers,As Superintendent of Subj Facil W/Statement of Qual Attached.Describes Capability of Plant to Function & Plant Staff to Respond Properly Immediately Following a Seismic Event Project stage: Other ML20147F0961978-10-16016 October 1978 Licensee'S Testimony on Capability of Subj Facil to W/Stand Seismic Events.Statements of Qualifications,Ref & Append Are Attached.Description of Affected Structure & Deficiencies Such as Amount & Arrangement of Reinforcing Steel Provided Project stage: Other ML20062B4191978-10-16016 October 1978 Forwards Ks Herring Testimony Re Suppl to Stardyne Analysis & Effect on Structural Capacity of Control Bldg.Certificate of Svc Encl Project stage: Other ML20062B4251978-10-17017 October 1978 Testimony Re Suppl to Stardyne Analysis & Effect of Structural Capacity of Control Bldg.Structure Can Withstand SSE & Less Severe Obe,But Suppl Info Alters Earthquake Level Requiring Plant Insp Project stage: Other ML20062B9591978-10-19019 October 1978 Forwards Recent Memoranda Re Certain Problems Experienced in Connection W/Pipe Support Base Plate Design.Staff Determining If Problems Have Generic Implications for Operating Facilities.Aslb Will Be Kept Informed Project stage: Other ML20062C6271978-10-27027 October 1978 Forwards Further Response to NRC Staff Tech Questions Re Stardyne Analysis & Review.Includes Description of Criteria & Procedures Used & Explanation of Dev of New Acceleration time-history.Cert of Svc Encl Project stage: Other ML20062D3481978-11-0606 November 1978 Cross-examination or Testimony Re Analysis & Review by Licensee Poge of safety-related Matls in Control-Auxiliary- Fuel Bldg Complex Will Be Taken at 781211 Hearing.Nrc Given Time to Reply to Interrogs.Proposed Findings Due 781120 Project stage: Other ML20197D4691978-11-22022 November 1978 Forwards Suppl Document Supporting Floor Response Spectra Provided in 781027 & 781102 Submittals to NRC in Response to Request for Additional Info Project stage: Request ML20197D4801978-11-22022 November 1978 Forwards Suppl Documentation in Support of Floor Response Spectra Provided in 781027 & 781102 Responses to NRC Info Requests.W/Cert of Svc Encl Project stage: Other ML20150F0221979-01-0303 January 1979 FOIA Request for 20 Documents Listed Re ECCS Performance Calculations & Calculational Errors Identified by Westinghouse & Portland GE, & on Pipe Cracks in Containment Vessel of Trojan Plant Project stage: Request ML20150F0641979-03-28028 March 1979 Forwards Response to NRC 790308 Technical Questions Re Control Bldg Design Mods.Response Also Being Served on ASLB & All Parties to Control Bldg Proceeding Project stage: Other ML20126B6041980-03-0707 March 1980 Forwards Info Re Environ Qualification of Class IE Equipment in Response to Reporting Requirement of IE Bulletin 79-01B. Info Includes List of Class IE Components Required to Function Under Accident Resulting in Harsh Environ Project stage: Other ML20126C0641980-03-20020 March 1980 Forwards Summary Tables Describing Reinforcing Steel in Shear Wall Panels of Control Auxiliary Fuel Bldg Complex in Response to NRC Verbal Request Project stage: Other 1978-06-30
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217E9711999-10-13013 October 1999 Submits Notification of Major Changes to Trojan Liquid Radioactive Waste Treatment Sys,Iaw PGE-1201.Detailed Description of Change Provided ML20217C8171999-10-0606 October 1999 Forwards Notice of Receipt of Availability for Comment & Meeting to Discuss License Termination Plan,Per 990805 Application ML20216F7621999-09-23023 September 1999 Forwards Corrected Response to Request 2 Contained in NRC 990920 RAI Re Application of Pacificorp for Transfer of License NPF-1.Response 2 Should Have Stated That Na General Partnership Is Partnership Formed in Nv ML20216F2871999-09-20020 September 1999 Informs NRC of Developments That Have Occurred Since 990524 Application Was Filed Re Pacificorp Transfer of License of FOL NPF-1.NRC Is Urged to Act & Approve Transaction Expeditiously by 990930.Supporting Documentation Encl ML20211Q3281999-09-0909 September 1999 Forwards Insp Rept 50-344/99-06 on 990630-0701,21 & 0408-08. No Violations Noted.Insp Conducted to Review Decommissioning Activities Underway at Trojan Site & to Accompany Shipment of Reactor Vessel to Hanford,Washington for Burial ML20211J2101999-08-30030 August 1999 Forwards Request for Addl Info Re Application for Approval of Proposed Corporate Merger of Pacificorp & Scottishpower ML20211B6611999-08-16016 August 1999 Forwards fitness-for-duty Program Performance Data Rept for Period of 990101-0630,IAW 10CFR26.71(d) ML20211B4091999-08-16016 August 1999 Forwards Environ Assessment & Finding No Significant Impact to Application for an Exemption & License Amend Dated 980129.Proposed Exemption & License Amend Would Delete Security Plan Requirements of 10CFR50.54(p) & 10CFR73.55 ML20211A7131999-08-16016 August 1999 Forwards Environ Assessment & Finding of No Significant Impact to Application for Exemption & License Amend Dtd 980827.Proposed Exemption & License Amend Would Delete EP Requirements of 10CFR50.54(q),10CFR50.47(b) & 10CFR50,app E ML20210R7691999-08-11011 August 1999 Forwards Proposed Rev 23 to PGE-8010, Trojan Nuclear QAP, in Response to NRC 990708 RAI Re Relocation of TS ACs to Qap.Revised QAP Will Be Made Effective Concurrently with Implementation of License Change Application Lca 245 ML20210H5971999-07-27027 July 1999 Forwards Notice of Consideration of Approval of Application Re Merger & Opportunity for Hearing.Notice Being Forwarded to Ofc of Fr for Publication ML20216D6611999-07-23023 July 1999 Submits Summary of Proprietary Submittals for Transtor Part 71 & Part 72 & Trojan ISFSI Applications ML20210F8601999-07-22022 July 1999 Forwards Rev 1 to PGE-1076, Trojan Reactor Vessel Package Sar. Changes to Rept Contained in Rev 1 Received NRC Approval by Ltr ML20210A6401999-07-19019 July 1999 Corrects Ref in Item 4 of Which Constitutes Rev 2 of Authorization from Wf Kane, for Trojan Reactor Vessel Package as Approved Package for Shipment Under General License,Subj to Listed Conditions ML20210B4481999-07-12012 July 1999 Forwards Rept Describing Effects of Earthquake That Occurred on 990702 Near Satsop,Wa,Iaw Trojan Nuclear Plant Defueled Sar,Section 4.1.3.1 ML20209D6231999-07-0808 July 1999 Forwards RAI Re Licensee 980827 Request for Amend That Would Delete Number of License Conditions & TS Requirements That Would Be Implemented After All Sf Has Been Removed from 10CFR50 Licensed Area.Response Requested within 30 Days ML20209C6481999-07-0606 July 1999 Forwards Rev 8 to Defueled Sar,Including Changes Since Last Submittal.Attachment Includes Brief Description of Each Change Included in Rev ML20209B7821999-07-0101 July 1999 Responds to NRC 990609 RAI Re License Change Application 244 & Accompanying Request for Exemption.Detailed Info Supports Estimation of Remaining Radioactive Matl Previously Provided by Licensee ML20212J3281999-06-15015 June 1999 Forwards Amend 22 to PGE-1012, Trojan Nuclear Plant Fire Protection Plan, IAW 10CFR50.48(f).Amend Reflects Revs Made During Decommissioning Activities & Does Not Reduce Effectiveness of Fire Protection ML20195J0111999-06-0909 June 1999 Responds to Requesting License & Exemption Re Emergency Preparedness ML20207D3861999-06-0101 June 1999 Forwards Rev 1 to PGE-1077, Trojan Nuclear Plant Reactor Vessel & Internals Removal Project Transportation Safety Plan ML20196L1251999-05-24024 May 1999 Forwards Application for Amend to License NPF-1 for Indirect Transfer of License,To Extent That Such Approval Required Solely to Reflect Change in Upstream Economic Ownership of Pacificorp ML20207A2751999-05-14014 May 1999 Informs That NRC Office of Nuclear Reactor Regulation Reorganized Effective 990328.As Part of Reorganization, Division of Licensing Project Mgt Created.Organization Chart Encl ML20206N9411999-05-11011 May 1999 Forwards Revised Epips,Including Rev 7 to EPIP 3, Response Organization Checklists & Rev 9 to EPIP 5, Emergency Preparedness Test Propgram. Changes to EPIPs 3 & 5 Ref New Owners of on-site Railroad Line,Portland & Western Railroad ML20206J8681999-05-0707 May 1999 Forwards Insp Repts 50-344/99-05 & 72-0017/99-04 on 990419-22.No Violations Noted.Insp Observed Work Activities Associated with Lifting of Reactor Vessel in Preparation for Removal & Shipment to Hanford Reservation for Burial ML20206J7931999-05-0707 May 1999 Forwards Insp Repts 50-344/99-04 & 72-0017/99-02 on 990322- 25 & 29-0408.One Violations Identified & Being Treated as non-cited Violation,Consistent with App C of Enforcement Policy ML20206H4331999-05-0505 May 1999 Forwards Amend 201 to License NPF-1 & Se.Amend Revises PDTSs by Deleting ISFSI Area,Revises Subsection 4.1.1,replaces Figure 4.1-1 with New Figure 4.1-1 & Adds New Page to Figure 4.1-1 to Reflect Access Control (ISFSI) Area ML20206N1571999-05-0404 May 1999 Forwards Util Quarterly Decommissioning Status Rept for First Quarter of 1999,IAW State of or Energy Facility Siting Council Order Approving Trojan Decommissioning Plan, ML20206E1731999-04-29029 April 1999 Informs That NRC Staff Has Performed an Acceptance Review of Trojan Nuclear Plant License Termination Plan,Submitted by ,To Determine Whether LTP Provides Adequate Info to Allow Staff to Conduct Detailed Review ML20206E0211999-04-28028 April 1999 Forwards Copy of Environ Assessment & Finding of No Significant Impact Re 970212 Application for Amend.Proposed Amend Would Revise Trojan Permanently Defueled TS to Delete ISFSI Area ML20206C9591999-04-23023 April 1999 Forwards Amend 200 to License NPF-1 & Safety Evaluation. Amend Changes License NPF-1 by Revising License Condition 2.C.(10), Loading of Fuel Into Casks in Fuel Building ML20206C9221999-04-23023 April 1999 Forwards Amend 199 to License NPF-1 & Safety Evaluation. Amend Changes License NPF-1 by Adding New License Condition Entitled, Loading of Fuel Into Casks in Fuel Building ML20205S9761999-04-21021 April 1999 Forwards Trojan Nuclear Plant,Radiological Environ Monitoring Rept for CY98. Rept Submitted in Accordance with Trojan Permanently Defueled TS 5.8.1.2 & Sections IV.B.2, IV.B.3 & Iv.C of App I to Title 10CFR50 ML20205T5471999-04-20020 April 1999 Forwards Insp Repts 50-344/99-03 & 72-0017/99-03 on 990301-04,15-18 & 22-25.No Violations Noted ML20205N9061999-04-13013 April 1999 Forwards Insp Rept 50-344/99-02 on 990329-0401.No Violations Noted.Inspectors Examined Portions of Physical Security, Access Authorization & FFD Programs ML20205P7301999-04-0808 April 1999 Forwards PGE-1009-98, Operational Ecological Monitoring Program for TNP,Jan-Dec 1998, Including All Existing non-radiological Effluents ML20205B3661999-03-25025 March 1999 Transmits Completed Application for Renewal of NPDES Permit for Trojan Nuclear Plant,Iaw License NPF-1,App B,Epp,Section 3.2 ML20204G1781999-03-18018 March 1999 Forwards Rev 4 to PGE-1063, Suppl to Applicants Environ Rept - Post Operating License Stage ML20204B7551999-03-18018 March 1999 Forwards Updated TS 5.6 Re High Radiation Area,Per Telcons with Nrc.Justification for TS Was Provided Previously with Util Ltr Dtd 990317,but Has Been Updated & Is Included as Encl 2 ML20204C5151999-03-17017 March 1999 Forwards Licensee Comments on NRC Preliminary SER & License Re Trojan Isfsi.Encl Includes Justification for Inclusion in ISFSI TS of Alternative Method to 10CFR20.1601(c) for Controlling Access to High Radiation Areas ML20207J3721999-03-10010 March 1999 Forwards License Amend Application 247 Requesting Amend to License NPF-1 to Add License Condition Denoting NRC Approval of PGE-1078, Trojan Nuclear Plant License Termination Plan, Also Encl.With Certificate of Svc ML20207L0011999-03-0808 March 1999 Transmits Tnp co-owners Annual Rept of Status of Decommissioning Funding for Tnp.Rept Is Based on Most Recent Analysis of Tnp Decommissioning Estimate & Funding Plan,Per Rev 6 to Pge, Tnp Decommissioning Plan ML20207G9691999-03-0303 March 1999 Forwards Rev 6 to PGE-1061, Trojan Nuclear Plant Decommissioning Plan. Summary of Changes,Attached.Revised Portions Denoted by Side Bars ML20207D7751999-03-0202 March 1999 Forwards Amend 21 to PGE-1012, Trojan Nuclear Plant Fire Protection Plan, Per 10CFR50.48(f).Amend Reflects Revs Made During Decommissioning Activities ML20207B0441999-02-24024 February 1999 Forwards Endorsements 139 to Nelia Policy NF-0225 & 2 to Nelia Policy NW-0602 ML20207J0701999-02-11011 February 1999 Forwards Proposed Ts,Update to ISFSI SAR & Revised Calculation,Per Application for Trojan ISFSI License ML20202G4291999-02-0202 February 1999 Forwards Rev 0 to PGE-1076, Trojan Reactor Vessel Package Sar. Approval,With Certain Conditions,For one-time Shipment of Trojan Reactor Vessel Package Granted by Commission Via Ltr ML20202G0931999-01-26026 January 1999 Submits Following Info That Will Be Needed for NRC Staff to Complete Review & Issue Trojan ISFSI License,As Result of 990121 Meeting with NRC Following Insp & Observation of ISFSI Preoperational Testing During Wk of 990118 ML20202F2551999-01-25025 January 1999 Forwards Fitness for Duty Program Performance Data Rept for July-Dec 1998 ML20202C1621999-01-21021 January 1999 Forwards Insp Repts 50-344/98-04 & 72-0017/98-01 & NOV Re Inadequate Actions Taken by Radiation Protection Technician to Ensure That Radiological Conditions Safe Prior to Removing Warning Signs for Airborne Radioactivity Area 1999-09-09
[Table view] Category:NRC TO UTILITY
MONTHYEARML20062F9241990-11-0808 November 1990 Forwards Insp Rept 50-344/90-29 on 900902-1006 & Notice of Violation ML20058F3761990-11-0101 November 1990 Ack Receipt of Re Corrective Actions Taken in Response to Violations Noted in Insp Rept 50-344/90-23 ML20058A3231990-10-12012 October 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-344/90-20 ML20058B6381990-10-12012 October 1990 Forwards Revised Section 1, Persons Contacted of Insp Rept 50-344/90-20,correcting Errors in Personnel & Positions ML20059M6981990-09-25025 September 1990 Ack Receipt of in Response to NRC Re Violations Noted in Insp Rept 50-344/90-21 ML20059M1941990-09-18018 September 1990 Forwards Insp Rept 50-344/90-25 on 900820-24.No Violations Noted ML20059L1711990-09-18018 September 1990 Provides Info Re Gfes of Operator Licensing Written Exam to Be Administered on 901010.W/o Encls ML20059F5331990-09-0707 September 1990 Ack Receipt of 900828 Response to NRC 900801 Request for Info Re FEMA Observations of 891115 Emergency Preparedness Exercise.Corrective Actions Described in Util Response Will Be Verified & Followed Through Routine Insp Program ML20059E8501990-09-0606 September 1990 Forwards Enforcement Conference Rept 50-344/90-26 on 900830. NRC Concludes That Corrective Actions Discussed Should Improve Plant Performance ML20059D5231990-08-30030 August 1990 Informs That Util Responses to Generic Ltr 88-14, Instrument Air Supply Sys Problems Affecting Safety-Related Equipment Confirms That All Requirements Completed & Implemented ML20059D0951990-08-30030 August 1990 Advises That Util 900126 Response to NRC Bulletin 89-003, Potential Loss of Required Shutdown Margin During Refueling Operations, Acceptable & Review Concluded ML20059D0971990-08-30030 August 1990 Forwards SER Accepting Util 880311,0401 & 1223 & 900319 & 0622 Responses to NRC Bulletin 88-002, Rapidly Propagating Fatigue Cracks in Steam Generator Tubes ML20059D3071990-08-29029 August 1990 Forwards Exam Rept 50-344/OL-90-03 Administered on 900717-19 & 23.All But One Initial Reactor Operator Passed Exam.Operating Portion of Initial Licensing Exam Revealed Some Generic Training Weaknesses ML20059C7801990-08-27027 August 1990 Forwards Amend 162 to License NPF-1 & Safety Evaluation. Amend Revises Tech Spec 3/4.6.1, Containment Integrity ML20056B2511990-08-21021 August 1990 Forwards Safeguards Insp Rept 50-344/90-23 on 900719-0817. Violation Noted But Not Cited.Characterization of Apparent Violation in Insp Rept May Change as Result of Further NRC Review.Enforcement Conference Scheduled for 900830 ML20059A6991990-08-17017 August 1990 Advises That Util 900119 Program Description Including Positions on Static Testing to Ensure Proper Switch Settings & motor-operated Valve Problem Trending Schedules May Be Reviewed During Possible Further NRC Insp ML20059C1951990-08-16016 August 1990 Forwards Insp Rept 50-344/90-21 on 900609-0721.Violations Noted.W/O Notice of Violation ML20056B2421990-08-15015 August 1990 Advises That 900712 & 31 Responses to SALP Rept 50-344/90-09 Appropriate.Page 18 of Initial Rept Changed to Relect Effort by Util Engineering Groups in Design of ATWS Mitigation Sys Actuation Circuitry,Per 900615 Board Meeting ML20056A5141990-08-0303 August 1990 Advises That Response to NRC Bulletin 88-010, Molded Case Circuit Breakers, Complete,Per 890331,0414,0725 & s.If Subsequent Insp Identifies Deficiencies in Actions & Responses,Issue Will Be Reopened ML20058L4401990-08-0202 August 1990 Forwards Corrected Amend 161 to License NPF-1,revising Items 6.4.1 & 6.4.2 Re Administrative Controls ML20058L5501990-08-0202 August 1990 Forwards Safety Evaluation Concluding That Instrumented Ammonia Detection Unnecessary for Protection of Control Room Personnel Based on Review of Submittals ML20056A6231990-08-0101 August 1990 Forwards FEMA Rept Re Observation of Offsite Activities During Plant Emergency Preparedness Exercise on 891115.NRC Understands That FEMA Rept for 900724,remedial Drill Will Close Five Deficiencies.W/O Encls ML20059A4011990-08-0101 August 1990 Forwards Insp Rept 50-344/90-17 on 900604-07.No Violations or Deviations Noted IR 05000344/19900111990-07-27027 July 1990 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-344/90-11 ML20056A0471990-07-20020 July 1990 Forwards SALP Mgt Meeting Insp Rept 50-344/90-22 on 900615 ML20055H3211990-07-13013 July 1990 Advises That 900330 & 0504 Amend 22 to Radiological Emergency Plan Meets 10CFR50.54(q) Requirements & Acceptable ML20055H5671990-07-11011 July 1990 Forwards Insp Rept 50-344/90-19 on 900611-15 & Notice of Violation IR 05000344/19900181990-07-10010 July 1990 Forwards Safeguards Insp Rept 50-344/90-18 on 900625-29.No Violations Noted.Rept Withheld (Ref 10CFR2.790(d)) ML20055E7851990-07-0909 July 1990 Forwards Safety Evaluation Re Procedures Generation Program for Plant,Per Util 831110 & s.Ltrs Should Be Reviewed to Address Programmatic Improvements Outlined in Section 2 of Rept ML20055G6311990-07-0606 July 1990 Forwards Insp Rept 50-344/90-16 on 900506-0609.No Violations or Deviations Noted ML20055E4061990-07-0303 July 1990 Discusses 900630 Submittal Re Reduced Measured Min RCS Flow for Plant.New Measured Min Flow Limit for RCS Flow Will Be Reflected in Proposed Change to Tech Specs to Be Submitted by 900713 ML20055C7481990-06-18018 June 1990 Forwards Amend 161 to License NPF-1 & Safety Evaluation. Amend Changes Qualification Requirements,As Specified in Tech Spec 6.3.1,that Must Be Met by Radiation Protection Manager ML20059M8941990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20055C3881990-02-12012 February 1990 Forwards Mgt Meeting Rept 50-344/90-01 on 900112.Licensee Must Thoroughly Follow Through on Implementation of Improvement Plans & Place High Priority on Assuring That Personnel Understands Goals & Objectives ML20248A8601989-09-27027 September 1989 Ack Receipt of 890828 & 0923 Responses to NRC 890727 Notice of Violation.Nrc Notes That Licensee Did Not Ack Violation B Re Proficiency of Security Officers in Use of Assigned Weapons IR 05000344/19890121989-09-27027 September 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-344/89-12.Contested Violation Re Interpretation of SNT-TC-1A Requirements Will Be Further Examined IR 05000344/19890181989-09-25025 September 1989 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-344/89-18 ML20248D3331989-09-25025 September 1989 Forwards Amend 6 to Indemnity Agreement B-78,reflecting Changes to 10CFR140,effective 890701 ML20248B7751989-09-19019 September 1989 Submits Info Re Generic Fundamentals Exam Section of Operator Licensing Written Exam to Be Administered 891004 & Forwards Map Describing Location of Exam & Other Info.W/O Encls IR 05000344/19890171989-09-12012 September 1989 Forwards Insp Rept 50-344/89-17 on 890618-0729 & Notice of Violation.Insp Identified That ESF Components Had Been Operated Outside Normal Design Limits ML20247H7401989-09-0101 September 1989 Forwards Enforcement Conference Rept 50-344/89-22 on 890824 Re Containment Recirculation Sump Debris & Design Problems ML20246N7881989-08-31031 August 1989 Informs That 880420 Rev 20 to Physical Security Plan Partially Consistent W/Provisions of 10CFR50.54(p).Trash Rack Functioning as Protected Area & Vital Area Barrier Unacceptable ML20247C1431989-08-29029 August 1989 Forwards Insp Rept 50-344/89-09 on 890522-0609 & 0719-21 & Notice of Violation.Licensee Generally Implemented Committed Programs to Enhance Understanding & Implementation of Plant Design Basis ML20246D8121989-08-21021 August 1989 Confirms 890821 Telcon Between Ae Chaffee & Td Walt Re Mgt Meeting/Enforcement Conference on 890824 at Plant to Discuss Insp Findings as Documented in Insp Rept 50-344/89-19 ML20246H9561989-08-15015 August 1989 Forwards Insp Rept 50-344/89-19 on 890712-0808.Violations Noted.Insp Findings Indicate That Util Mgt Oversight of Plant Activities Associated W/Sump Have Been Ineffective ML20245H3601989-08-10010 August 1989 Forwards Corrected Page to Amend 152 Issued to License NPF-1 on 890515 IR 05000344/19890141989-08-0707 August 1989 Ack Receipt of 890707 & 28 Ltrs Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-344/89-14. Handwritten Notes Encl ML20245L1301989-08-0404 August 1989 Forwards Insp Rept 50-344/89-12 on 890522-0601 & Notice of Violation.Insp Determined That Inservice Contractor & Licensee Oversight of Contractor Activities Need Significant Improvement ML20245K2541989-08-0303 August 1989 Forwards Insp Rept 50-344/89-18 on 890712-14 & Notice of Violation.Nrc Views Util Handling of Hydrogen Issues as Missed Opportunities to Focus on & Resolve long-standing & Potentially Significant Safety Issue IR 05000344/19890081989-07-27027 July 1989 Discusses Safeguards Insp Rept 50-344/89-08 & Security Insp Rept 50-344/89-02 & Forwards Notice of Violation Re Safeguards Info Protection & Firearms Training Adequacy.Encl Withheld (Ref 10CFR2.790) 1990-09-07
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217C8171999-10-0606 October 1999 Forwards Notice of Receipt of Availability for Comment & Meeting to Discuss License Termination Plan,Per 990805 Application ML20211Q3281999-09-0909 September 1999 Forwards Insp Rept 50-344/99-06 on 990630-0701,21 & 0408-08. No Violations Noted.Insp Conducted to Review Decommissioning Activities Underway at Trojan Site & to Accompany Shipment of Reactor Vessel to Hanford,Washington for Burial ML20211J2101999-08-30030 August 1999 Forwards Request for Addl Info Re Application for Approval of Proposed Corporate Merger of Pacificorp & Scottishpower ML20211A7131999-08-16016 August 1999 Forwards Environ Assessment & Finding of No Significant Impact to Application for Exemption & License Amend Dtd 980827.Proposed Exemption & License Amend Would Delete EP Requirements of 10CFR50.54(q),10CFR50.47(b) & 10CFR50,app E ML20211B4091999-08-16016 August 1999 Forwards Environ Assessment & Finding No Significant Impact to Application for an Exemption & License Amend Dated 980129.Proposed Exemption & License Amend Would Delete Security Plan Requirements of 10CFR50.54(p) & 10CFR73.55 ML20210H5971999-07-27027 July 1999 Forwards Notice of Consideration of Approval of Application Re Merger & Opportunity for Hearing.Notice Being Forwarded to Ofc of Fr for Publication ML20210A6401999-07-19019 July 1999 Corrects Ref in Item 4 of Which Constitutes Rev 2 of Authorization from Wf Kane, for Trojan Reactor Vessel Package as Approved Package for Shipment Under General License,Subj to Listed Conditions ML20209D6231999-07-0808 July 1999 Forwards RAI Re Licensee 980827 Request for Amend That Would Delete Number of License Conditions & TS Requirements That Would Be Implemented After All Sf Has Been Removed from 10CFR50 Licensed Area.Response Requested within 30 Days ML20195J0111999-06-0909 June 1999 Responds to Requesting License & Exemption Re Emergency Preparedness ML20207A2751999-05-14014 May 1999 Informs That NRC Office of Nuclear Reactor Regulation Reorganized Effective 990328.As Part of Reorganization, Division of Licensing Project Mgt Created.Organization Chart Encl ML20206J7931999-05-0707 May 1999 Forwards Insp Repts 50-344/99-04 & 72-0017/99-02 on 990322- 25 & 29-0408.One Violations Identified & Being Treated as non-cited Violation,Consistent with App C of Enforcement Policy ML20206J8681999-05-0707 May 1999 Forwards Insp Repts 50-344/99-05 & 72-0017/99-04 on 990419-22.No Violations Noted.Insp Observed Work Activities Associated with Lifting of Reactor Vessel in Preparation for Removal & Shipment to Hanford Reservation for Burial ML20206H4331999-05-0505 May 1999 Forwards Amend 201 to License NPF-1 & Se.Amend Revises PDTSs by Deleting ISFSI Area,Revises Subsection 4.1.1,replaces Figure 4.1-1 with New Figure 4.1-1 & Adds New Page to Figure 4.1-1 to Reflect Access Control (ISFSI) Area ML20206E1731999-04-29029 April 1999 Informs That NRC Staff Has Performed an Acceptance Review of Trojan Nuclear Plant License Termination Plan,Submitted by ,To Determine Whether LTP Provides Adequate Info to Allow Staff to Conduct Detailed Review ML20206E0211999-04-28028 April 1999 Forwards Copy of Environ Assessment & Finding of No Significant Impact Re 970212 Application for Amend.Proposed Amend Would Revise Trojan Permanently Defueled TS to Delete ISFSI Area ML20206C9221999-04-23023 April 1999 Forwards Amend 199 to License NPF-1 & Safety Evaluation. Amend Changes License NPF-1 by Adding New License Condition Entitled, Loading of Fuel Into Casks in Fuel Building ML20206C9591999-04-23023 April 1999 Forwards Amend 200 to License NPF-1 & Safety Evaluation. Amend Changes License NPF-1 by Revising License Condition 2.C.(10), Loading of Fuel Into Casks in Fuel Building ML20205T5471999-04-20020 April 1999 Forwards Insp Repts 50-344/99-03 & 72-0017/99-03 on 990301-04,15-18 & 22-25.No Violations Noted ML20205N9061999-04-13013 April 1999 Forwards Insp Rept 50-344/99-02 on 990329-0401.No Violations Noted.Inspectors Examined Portions of Physical Security, Access Authorization & FFD Programs ML20202C1621999-01-21021 January 1999 Forwards Insp Repts 50-344/98-04 & 72-0017/98-01 & NOV Re Inadequate Actions Taken by Radiation Protection Technician to Ensure That Radiological Conditions Safe Prior to Removing Warning Signs for Airborne Radioactivity Area ML20198E9871998-12-21021 December 1998 Informs That NRC Staff Acks Delay & Understands Bnfl Fuel Solutions Will Submit Revised Schedule for Responding to Second Transtor Shipping Cask RAI No Later than 981231. Current Schedule Last Updated on 981030 ML20198S1661998-12-17017 December 1998 Final Response to FOIA Request for Documents.Records Encl & Identified in App C & D.App E Records Withheld in Part & App F Records Withheld in Entirety (Ref FOIA Exemption 5) & App G Records Withheld in Entirety (Ref FOIA Exemptions 4 & 5) ML20195D9471998-11-0404 November 1998 Informs of NRC Final Decision on Portland General Electric Co Request for Approval of one-time Shipment of Decommissioned Rv Package from Trojan Nuclear Power Plant Near Richland,Wa.Commission Approved Request on 981022 ML20155F6471998-11-0202 November 1998 Informs of NRC Final Decision on Portland General Electric Co Request for Approval of one-time Shipment of Decommissioned Rv Package from Tnp Near Ranier,Or to Disposal Site at Hanford Nuclear Reservation ML20155G7371998-10-30030 October 1998 Forwards Insp Rept 50-344/98-202 on 980831-0903. No Violations Noted.Insp Program Covered Maint Program, Safety Review Program & Follow Up on Previous Inspector Follow Items Re Modular Sf Cooling Sys ML20155E0491998-10-29029 October 1998 Forwards SER Granting Two Specific Exemptions Under 10CFR71.8 for Approval of Trojan Reactor Vessel Package for one-time Shipment to Us Ecology Disposal Facility Near Richland,Wa ML20155H0171998-10-29029 October 1998 Informs of Us NRC Final Decision on Poge Request for Approval of one-time Shipment of Decommissioned Reactor Vessel Package from Trojan Nuclear Power Plant,To Disposal Site at Hanford Nuclear Reservation,Near Richland.Wa ML20155F6001998-10-29029 October 1998 Informs of NRC Final Decision on Portland General Electric Co Request for Approval of one-time Shipment of Decommissioned Rv Package from Plant Near Ranier,Or Disposal Site at Hanford Nuclear Reservation ML20151Z6461998-09-17017 September 1998 Refers to Insp Rept 50-344/98-02 Issued on 980701 Re Modular Spent Fuel Pool Cooling Sys.Info Provided in Re New Spent Fuel Pool Sys Reviewed.Insp 50-344/98-03 & 50-344/98-202 Also Included Reviews of Sys Design & Testing ML20151Y8761998-09-11011 September 1998 Responds to Re NRC Efforts on Review Activities for Proposed one-time Shipment of Trojan Reactor Vessel,For Disposal.Nrc decision-making Process Acting in Parrallel & in Concert with Other Necessary Approvals ML20237F1281998-08-27027 August 1998 First Partial Response to FOIA Request for Documents. Forwards App a Records Already Available in Pdr.App B Records Being Made Available in PDR ML20237E5781998-08-25025 August 1998 Forwards Insp Rept 50-344/98-03 on 980727-30.No Violations Noted ML20237B4271998-08-14014 August 1998 Expresses Appreciation for Contribution to NRC Public Meeting Held in Kelso,Wa on 980730 Re Proposed One Time Shipment of Trojan Decommissioned Rv for Disposal ML20237A4101998-08-11011 August 1998 Forwards RAI Re Plant Request for Amend to Support Repowering Site W/Natural Gas Fired,Combined Cycle Turbines. Response Requested to Be Provided within 60 Days of Date of Ltr ML20236T5651998-07-21021 July 1998 Responds to to Chairman Jackson Expressing Concern W/Nrc Schedules for Reviewing Portland General Electric Co Applications for on-site Sf Storage & for one-time Shipment of Reactor Vessel ML20236G9671998-07-0101 July 1998 Forwards Insp Rept 50-344/98-02 on 980601-04.No Violations Noted.Plans to Replace Existing Spent Fuel cooling,make-up Water & clean-up Sys W/New Self Contained Sys Were Discussed W/Staff ML20249B8581998-06-18018 June 1998 Informs That Tj Kobetz Has Assumed Project Management Responsbilities for Proposed Trojan Isfsi.Communications W/ NRC Should Be Directed to Tj Kobetz.Written Correspondence Should Continue to Go DCD ML20247N6681998-05-22022 May 1998 Forwards Insp Rept 50-344/98-01 on 980504-07.No Violations Noted.Insp Focused on Physical Security Program ML20217L0571998-04-29029 April 1998 Forwards Insp Rept 50-344/98-201 on 980223-26.No Violations Noted.Specific Areas Examined Included Training & Certification of Qualified Evaluators,Independent Reviewers & Independent Safety Reviewers;Procedural Controls IR 05000344/19970051998-03-25025 March 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-344/97-05.Actions Will Be Reviewed During Future Insp to Determine That Full Compliance Has Been Achieved & Will Be Maintained ML20217A5491998-03-18018 March 1998 Submits Update on Actions Taken by NRC Since 970613 Response Re Portland General Electric Co Request for Approval of 1-time Shipment of Decommissioned Reactor Vessel.Two Issues Identified for Review in Utility Request,Submitted ML20217A4221998-03-11011 March 1998 Submits Update on Actions Taken by NRC Since 970613 Response Re Portland General Electric Co Request for Approval of one-time Shipment of Decommissioned Reactor Vessel.Two Issues for Review in Utility Request Submitted ML20202J0741998-02-18018 February 1998 Grants Request for Extension of Response to NOV in Insp Rept 50-344/97-05.New Response Deadline 980317 ML20203A9061998-02-18018 February 1998 Informs of 980209 Meeting W/Poge in Region IV to Discuss Proposed Changes to Security Provisions for Protected Area at Plant.List of Attendees & Handouts Provided by Util Encl ML20202C1791998-02-0909 February 1998 Returns Responses to 970731 RAI-2 Re 960326 Application for Trojan Isfsi,Due to Overall Poor Quality.Proprietary Documents Are Being Returned Under Separate Cover as Required Affidavits Were Not Provided ML20203F4661998-01-30030 January 1998 Requests That Staff Ask Us Ecology,In Coordination W/Portland General Electric Co,To Perform Comprehensive & Defensible Pathways Analysis to Demonstrate Suitability of Proposed Wastes for Disposal at Hanford Disposal Site ML20199D7481998-01-23023 January 1998 Forwards Omitted Cover Page for Insp Rept 50-344/97-05 on 971201-03 ML20199F0021998-01-23023 January 1998 Forwards Omitted Page of Insp Rept 50-344/97-05 ML20199F0241998-01-15015 January 1998 Forwards Insp Rept 50-344/97-05 on 971201-03 & Notice of Violation.Areas Reviewed as Part of Insp Included;Sfp TS Compliance,Cold Weather Preparations,Results of 1997 Emergency Exercise & Followup on Notification to NRC ML20198F7411998-01-0707 January 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-344/97-03. Implementation of Corrective Actions Will Be Reviewed During Future Insp to Determine That Compliance Achieved 1999-09-09
[Table view] |
Text
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,8 , UNITED STATES 3* -'t NUCl. EAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 August 30, 1978
%,,...* +-[/j' Docket No. 50-344 :
Portland General Electric Company ATTN: Mr. Charles Goodwin, Jr.
Assistant Vice President 121 SW Salmon Street Portland, Oregon 97204 Gentlemen:
l Confinning our oral request made at the conclusion of our meeting i in Bethesda on August 28, 1978, enclosed is a request for additional information resulting from the infonnation presented at this meeting.
It is our understanding that you will be able to provide a written response by September 11, 1978. Please contact us if you have any questions concerning this request.
Since rely , ,
I i y (kdlNY
! A. Schwencer, Chief Operating Reactors Branch #1 Division of Operating Reactors l
Enclosure:
i Request for Additional /
Information cc: w/er. closure '
. See next page l
, v y! !/
g 7 QD ..
Portland General Electric Company '
cc: Mr. H. H. Phillips Portland General Electric Company 121 SW Salmon Street Portland, Oregon 97204 Warren Hastings, Esquire Counsel for Portland General Electric Company 121 SW Salmon Street Portland, Oregon 97204 Mr. J. L. Frewing, Manager i Generation Licensing and Analysis i Portland General Electric Company
- . SW Salmon Street
, Portland, Oregon 97204 ,
Columbia County Courthouse Law Library, Circuit Court Room i St. Helens Oregon 97501 Director, Oregon Department i of Energy
, Labor & Industries Building, Rm. 111-Salem, Oregon 97310 l
}
Richard M. Sandvik, Esquire' Counsel for Oregon Energy Facility
- Siting Counsel and Oregon
! Department of Energy '
500 Pacific Building 520 SW Yamhill
. Portland, Oregon 97204 Dr. Harold Laursen 1520 NW 13th Street Corvallis, Oregon 97330 V
TROJAN CONTROL BUILDING SEISMIC NON-CONFORMANCE REQUEST FOR ADDITIONAL INFORMATION
- 1. Provide a detailed comparison of the original and the refined seismic analyses of the Turbine Building and a discussion of why the results of the new analysis do not alter any previous conclusions regarding the integrity of the structure. Identify any safety related components, equipment and systems located in the Turbine Building, and discuss the impacts of the results of this refined seismic analysis on each of these items and why the impacts of these results are acceptable.
- 2. Discuss in detail the discrepancies between the original Bechtel analyses, the TABS analysis and the STARDYNE analysis of the Control-Auxiliary-Fuel Building complex. Provide a comparision of the results and the basis for any conclusions regarding the acceptability of these inconsist-l ancies. Substantiate (1) that there is no detrimental impact on previous statements and conclusions regarding the integrity of the Fuel 9uilding, j and (2) that the statements in the FSAR regarding the conservatism of the fixed-base seismic analyses perfonned previously for all Seismic l
Category I structures are not invalidated.
- 3. Given the results of the supplenental STARDYNE analysis and considering all of the nonlinearities in the response of the structure indicated by these resuits:
(a) Identify each of the expected nonlinearities and quantify the effects of each on the benavior of the structure.
l (b) Provide a detailed discussion of the impact of these results on the floor response spectra for the Control Building. Identify all safety related components, equipment and systems in the Control Building. Discuss the impacts that any changes in the response spectra and the increased displace.9ents of the structure would have on each of these items and why these impacts are acceotable.
(c) Provide a sumary of the stress lavels in the most critical wall elements (i.e., consider those walls which are the most highly stressed, those walls with the highest and lowest height to length ratios, those walls with the highest and lowest reinforcement ratios, etc.), and the corresponding strength ratios and acceptance criteria. Discuss the impact of cyclic degradation on wall strengths at these stress levels and provide a basis for all conclusions regarding these effects. In addition, discuss the strain compati-bility betweso the concrete core and the masonry at these stress levels to substantiate that each of these materials will reach
the assumed stress levels at about the same overall wall dis-placement such that significant degradation of either one of these materials does not occur before the other has reached its required stress level.
(d) Discus; in detail the effects cf the "Basic Shear Wall Capacity Criteria" utilized in the supplemental analysis on tha shear transfer capability at the wall-slab interfaces.
(e) Provide a detailed discussion of shear transfer into transverse walls and the tensile and compressive stresses in these trans-verse walls to substantiate the assumption that the gross over-turning moments in the structure will be resisted by the trans-verse walls. Include a basis for any conclusions regardin) the adequacy of these walls to transmit the required forces.
(f) Discuss the adequacy of the shear transfer mechanism at the foundation level from the walls into the rock. Include the N ses for any conclusions regarding the adequacy of these mechanism.
- 5. Discuss in detail the impacts of the supplemental STARDYNE analysis results on all analysis results submitted previously. Quantify the differences between the supplemental and previous basic shear wall acceptance criteria for the varicus extremes of shear wall behavior (i.e., consider the walls with the highest and lowest reinforcement ratios for walls in the various height to length ratio caterories, the walls which were both moment controlled and shear controlled under the previous criteria, etc.), Include a basis for using a wall's dowel capacity, determined by considering that the steel reinforcement will reach its ultimate strength, in the supplemental analysis as the capacity of a wall if the dowel capacity is greater than the shMr capacity calculated from the "Basic Shear Wall Acceptance Criteria" for walls with height to length ratics less than or equal to 0.5.
- 6. At what OBE level below 0.15 "g" does the supplemental analysis indicate that nonlinear behavior of the wall systems will begin.
I 7. Considering the nonlinear behavior of the Control Building indicated l by the supplemental STAROYNE analysis, provide a detailed discussion l
of the expected impact of this behavior on the Fuel Building to sub-stantiate that there will be no detrimental effects of this behavior on the integrity of the Fuel Building.
- 8. Discuss the consistency of the "Basic Shear Wall Acceptance Criteria" with the results of the Schneider, Mayes and Clough, PCA, and other appropriate test data, especially with regard to cyclic loadings. Consider and discuss the differences among the various test specimen and how the results for the test specimen are related to the Control Building walls. Include a quantification of any differences.