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Category:CORRESPONDENCE-LETTERS
MONTHYEARTXX-9924, Forwards Responses to Questions by NRC Re Application for Amends to Licenses NPF-87 & NPF-89,by Incorporating Changes Increasing RWST low-level Setpoint from Greater than But Equal to 40% to Greater than But Equal to 45% of Span1999-10-22022 October 1999 Forwards Responses to Questions by NRC Re Application for Amends to Licenses NPF-87 & NPF-89,by Incorporating Changes Increasing RWST low-level Setpoint from Greater than But Equal to 40% to Greater than But Equal to 45% of Span ML20217M5711999-10-20020 October 1999 Forwards Insp Repts 50-445/99-15 & 50-446/99-15 on 990822- 1002.Two Severity Level IV Violations of NRC Requirements Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy TXX-9923, Forwards Monthly Operating Repts for Sept 1999 for CPSES, Units 1 & 2,per Plant TS 5.6.4.No Failures of Challenges to PORVs of SV for Units Occurred1999-10-15015 October 1999 Forwards Monthly Operating Repts for Sept 1999 for CPSES, Units 1 & 2,per Plant TS 5.6.4.No Failures of Challenges to PORVs of SV for Units Occurred ML20217E7951999-10-12012 October 1999 Forwards COLR for Unit 1,Cycle 8,per TS 5.6.5 ML20212L2891999-10-0101 October 1999 Discusses Closeout of GL 97-06, Degradation of Steam Generator Internals. Purpose of GL Was to Obtain Info That Would Enable NRC to Verify That Condition of Licensee SG Internals Comply with Current Licensing Bases TXX-9922, Forwards Revised COLR, for Cycle 5 for Unit 21999-10-0101 October 1999 Forwards Revised COLR, for Cycle 5 for Unit 2 ML20216J5571999-10-0101 October 1999 Provides Final Response to GL 98-01,suppl 1, Y2K Readiness of Computer Sys at Npps ML20212G0721999-09-24024 September 1999 Forwards Rev 4 to Augmented Inservice Insp Plan for CPSES, Unit 1. Future Changes & Revs to Unit 1 Augmented Inservice Insp Plan Will Be Available on Site ML20212H0461999-09-24024 September 1999 Forwards Rev 6 to CPSES Glen Rose,Tx ASME Section XI ISI Program Plan for 1st Interval on 990820 ML20212F7481999-09-24024 September 1999 Forwards SER Authorizing Relief from Exam Requirement of 1986 Edition ASME Code,Section XI Pursuant to 10CFR50.55a(a)(3)(ii) for Relief Request A-3 & 10CFR50.55a(g)(6)(i) for Relief Requests B15,16,17 & C-4 ML20212F1041999-09-23023 September 1999 Requests That NRC Be Informed of Any Changes in Scope of Y2K System Deficiencies Listed or Util Projected Completion Schedule for Comanche Peak Steam Electric Station,Units 1 & 2 ML20212E6661999-09-21021 September 1999 Advises That Info Contained in Application & Affidavit, (CAW-99-1342) Re WCAP-15009,Rev 0, Comache Peak Unit 1 Evaluation for Tube Vibration Induced Fatigue, Will Be Withheld from Public Disclosure ML20212D9111999-09-16016 September 1999 Informs That on 990818,NRC Completed Midcycle PPR of CPSES & Did Not Identify Any Areas in Which Performance Warranted Insp Beyond Core Insp Program.Core Insp Plan at Facility Over Next 7 Months.Insp Plan Through March 2000 Encl ML20212A7601999-09-14014 September 1999 Forwards Insp Repts 50-445/99-14 & 50-446/99-14 on 990707-0821.Four Violations Occurred & Being Treated as Ncvs.Conduct of Activities Was Generally Characterized by safety-conscious Operations & Sound Radiological Controls TXX-9921, Suppls 981221 LAR 98-010 to Licenses NPF-87 & NPF-89, Clarfying Conditions of Use Re Analytical Methods Used to Determine Core Operating Limits,Per Telcon with NRC1999-09-10010 September 1999 Suppls 981221 LAR 98-010 to Licenses NPF-87 & NPF-89, Clarfying Conditions of Use Re Analytical Methods Used to Determine Core Operating Limits,Per Telcon with NRC ML20211P3761999-09-0707 September 1999 Ack Receipt of Ltr Dtd 990615,transmitting Rev 30 to Physical Security Plan,Per 10CFR50.54(p).No NRC Approval Is Required ML20211L9871999-09-0303 September 1999 Forwards Rev 31 to Technical Requirements Manual. All Changes Applicable to Plants Have Been Reviewed Under Util 10CFR50.59 Process & Found Not to Include Any USQs TXX-9915, Responds to 990701 & 0825 RAI Telcons Re Spent Fuel Pool Temp,Per LAR 98-008,which Requested Increase in Spent Fuel Storage capacity.Marked-up Page 4-1 of CPSES Fuel Storage Licensing Rept, Encl1999-09-0303 September 1999 Responds to 990701 & 0825 RAI Telcons Re Spent Fuel Pool Temp,Per LAR 98-008,which Requested Increase in Spent Fuel Storage capacity.Marked-up Page 4-1 of CPSES Fuel Storage Licensing Rept, Encl ML20211K2231999-08-31031 August 1999 Forwards Txu Electric Comments of Rvid,Version 2 ML20211J3801999-08-27027 August 1999 Forwards Corrected TS Page 3.8-26 to Amend 66 to Licenses NPF-87 & NPF-89,respectively.Footnote on TS Page 3.8-26 Incorrectly Deleted ML20211G7301999-08-26026 August 1999 Forwards Revs 29 & 30 to CPSES Technical Requirements Manual (Trm). Attachments 1 & 2 Contain Description of Changes for Revs 29 & 30 Respectively ML20211G1081999-08-26026 August 1999 Responds to NRR Staff RAI Re Util Mar 1999 Submittal for NRC Review & Approval of Changes to CPSES Emergency Classification Procedure ML20211G3441999-08-25025 August 1999 Forwards Response to NRC RAI on LAR 98-010 for Cpses,Units 1 & 2.Communication Contains No New Licensing Commitments Re Cpses,Units 1 & 2 ML20211B2861999-08-18018 August 1999 Forwards Insp Repts 50-445/99-13 & 50-446/99-13 on 990720- 23.No Violations Noted.Insp Included Implementation of Licensee Emergency Plan & Procedures During Util Biennial Emergency Preparedness Exercise ML20211C4661999-08-18018 August 1999 Discusses Proprietary Info Re Thermo-Lag.NRC Treated Bisco Test Rept 748-105 as Proprietary & Withheld It from Public Disclosure,Iaw 10CFR2.790 ML20210U3981999-08-17017 August 1999 Forwards Monthly Operating Repts for July 1999 for CPSES, Units 1 & 2,per TS 6.9.1.5.No Failures or Challenges to PORVs or SVs for Plant Occurred ML20211C0991999-08-17017 August 1999 Forwards Rev 3 to ASME Section XI ISI Program Plan,Unit 2 - 1st Interval, Replacing Rev 2 in Entirety ML20211C4571999-08-16016 August 1999 Forwards Omitted Subj Page of Contractor TER TXX-9919, Forwards Relief Request A-3,Rev 1 to Unit 1 ISI Program,Per Conversations Between NRC & Txu Electric on 9908021999-08-16016 August 1999 Forwards Relief Request A-3,Rev 1 to Unit 1 ISI Program,Per Conversations Between NRC & Txu Electric on 990802 ML20210R6561999-08-13013 August 1999 Forwards Response to NRR 990805 Telcon RAI Re License Amend Request 98-010,to Increase Power for Operation of CPSES Unit 2 to 3445 Mwth & Incorporating Addl Changes Into Units 1 & 2 TS 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 ML20210S6411999-08-12012 August 1999 Informs That Wg Guldemond,License SOP-43780,is No Longer Performing Licensed Duties.Discontinuation of License Is Requested ML20210R2221999-08-12012 August 1999 Forwards Insp Repts 50-445/99-10 & 50-446/99-10 on 990510-0628.Violations Noted & Being Treated as Ncvs, Consistent with App C of Enforcement Policy ML20210N1101999-08-0404 August 1999 Provides Supplemental Info to Util 990623 License Amend Request 99-005 Re Bypassing DG Trips.Info Replaces Info Contained in Subject Submittal in Attachment 2,Section II, Description of TS Change Request 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 ML20210J2301999-08-0202 August 1999 Forwards Amend 96 to CPSES Ufsar.Replacement of FSAR Figures with Plant Process Flow Diagrams Meets Intent & Requirements of NRC Reg Guide 1.70,Rev 2 ML20210J6071999-08-0202 August 1999 Forwards line-by-line Descriptions of Changes in Amend 96 to CPSES UFSAR Transmitted by Util Ltr TXX-99166,dtd 990802. Replacment of FSAR Figures with Plant Process Flow Diagrams Meets Intent & Requirements of NRC Reg Guide 1.70,rev 2 TXX-9916, Notifies NRC That CPSES Units 1 & 2,improved TS Implemented on 9907271999-08-0202 August 1999 Notifies NRC That CPSES Units 1 & 2,improved TS Implemented on 990727 TXX-9918, Forwards CPSES 10CFR50.59 Evaluation Summary Rept 0008,for 970802-990201 & CPSES Commitment Matl Change Evaluation Rept 0003,for 970802-9906301999-08-0202 August 1999 Forwards CPSES 10CFR50.59 Evaluation Summary Rept 0008,for 970802-990201 & CPSES Commitment Matl Change Evaluation Rept 0003,for 970802-990630 ML20210K2321999-07-29029 July 1999 Forwards Insp Repts 50-445/99-12 & 50-446/99-12 on 990530-0710.No Violations Noted ML20210G5861999-07-29029 July 1999 Forwards fitness-for-duty Program Performance Data for Six Month Period of Jan-June 1999 ML20210J0121999-07-27027 July 1999 Forwards Summary of Methodology for Determination of NDE Measurement Uncertainty,In Response to Recent Discussions with NRC Re LAR 98-006 Concerning Rev to SG Tube Plugging Criteria TXX-9917, Provides Info Re Augmented Inservice Insp Plan,Which Requires Periodic Insp of Rv Head & Internals Lifting Devices at CPSES1999-07-26026 July 1999 Provides Info Re Augmented Inservice Insp Plan,Which Requires Periodic Insp of Rv Head & Internals Lifting Devices at CPSES ML20210F3121999-07-26026 July 1999 Responds to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal, ML20210D8231999-07-23023 July 1999 Forwards Safety Evaluation of Relief Requests Re Use of 1998 Edition of Subsections IWE & Iwl of ASME Code for Containment Insp ML20210D3211999-07-21021 July 1999 Provides List of Estimates of Licensing Actions,In Response to Administrative Ltr 99-02,dtd 990603 ML20210C2931999-07-21021 July 1999 Supplements 880323 Response to NRC Bulletin 88-02, Rapidly Propagating...Sg Tubes, Non-proprietary WCAP-15010 & Proprietary Rev 0 to WCAP-15009, CP Unit 1 Evaluation for Tube Vibration... Encl.Proprietary Rept Withheld ML20209H0111999-07-16016 July 1999 Forwards Relief Request C-4 to CPSES Unit 2 ISI Program for Approval ML20210C3331999-07-16016 July 1999 Forwards Exam Repts 50-445/99-301 & 50-446/99-301 on 990618- 24.Exam Included Evaluation of Six Applicants for Senior Operator Licenses ML20209H2551999-07-16016 July 1999 Forwards ISI Summary Rept for Fourth Refueling Outage of CPSES Unit 2 & Containment ISI Summary Rept for Fourth Refueling Outage of CPSES Unit 2,per ASME Boiler & Pressure Vessel Code,Section Xi,Paragraph IWA-6230 1999-09-07
[Table view] Category:EXTERNAL CORRESPONDENCE
MONTHYEARTXX-9914, Responds to 990525 RAI Re Renewal of Tpdes Permit Number 01854.Explanation & Response to Each Item,Listed1999-06-16016 June 1999 Responds to 990525 RAI Re Renewal of Tpdes Permit Number 01854.Explanation & Response to Each Item,Listed ML20206E7271999-04-29029 April 1999 Submits Original & Four Complete Copies of Application for Renewal of Permit to Discharge,Deposit or Dispose of Wastes Into or Adjacent to Water in State. with Three Oversize Drawings ML20045D3451992-06-16016 June 1992 Discusses Util Review of 920603 Ltr Outlining Thermal Science,Inc Field Surveillance of Application of Thermo-Lag 330 Fire Barrier Sys on Util Test Assemblies at Omega Poing Labs.Supporting Documentation Encl ML20091Q2891992-01-27027 January 1992 Forwards Rev 7 to Quarterly Plant Performance & Other Indicator Data for Fourth Quarter of 1991 & Gross Heat Rate Data Form for 1991 ML20070T7651991-04-0101 April 1991 Forwards 910327 License Amend Request 91-001 Re Addition of Spec 3/4.7.12 & Bases 3/4.7.12 for Safety Chilled Water Sys ML20073D1051991-03-29029 March 1991 Comments on Final Rept Addressing Scaling for Unit 1,dtd Feb 1991 Per Insp Repts 50-445/90-47 & 50-446/90-47.Concerns Raised That Util Selected Criterion XI Re Test Control as Sole Mgt Std to Control safety-related Activities ML20066A5711990-12-19019 December 1990 Forwards Update to ASME Section Iii,Div 1 Code Control Program Documents for Incorporation Into State of Tx Dept of Licensing & Regulation Controlled Manual CCPM-15,authored by Ebasco ML20056B3741990-08-21021 August 1990 Forwards Update to ASME Section Iii,Div 1 Code Control Program Documents for Incorporation Into State of Tx Dept of Licensing & Regulation Controlled Manual CCPM-15 ML20011E1521990-01-27027 January 1990 Forwards Addl Case Concern Repts 89-0025 Re Apparent Substandard Shop Applied Welds Internal to Secondary Side of Steam Generators & 89-0034 on Specific Wiring & Connection Method Damaging safety-related Electrical Wiring ML20248D0661989-09-21021 September 1989 Notifies Util of Case Position on Concerns & Problems in Scaling Calculation Program at Plant.Documentary Info Supporting Util Position on Aspect of Dispute Should Be Provided ML19332C7971989-09-14014 September 1989 Forwards Offsite Portion of Annual Emergency Preparedness Independent Review & Status of Corrective Actions Initiated, Per 10CFR50.54(t) ML19332E0011989-09-14014 September 1989 Forwards Offsite Portion of Annual Emergency Preparedness Independent Review Per 10CFR50.54(t) ML19332D4781989-09-14014 September 1989 Forwards Offsite Portion of Annual Emergency Preparedness Independent Review to Be Conducted Every 12 Months.Review Must Include Evaluation for Adequacy of Interfaces W/State & Local Govts ML19332C8171989-09-14014 September 1989 Forwards Offsite Portion of Annual Emergency Preparedness Independent Review & Status of Corrective Actions Initiated, Per 10CFR50.54(t) ML20246A0421989-08-18018 August 1989 Advises That S&W Notified by Util That Responsibility for Facility Code Control Program Will Be Terminated Effective on 890823.EBASCO Svcs,Inc Selected to Assume Responsibility for Code Control Program Effective on 890824 ML20247R7291989-07-28028 July 1989 Advises That Status of Suspect molded-case Curcuit Breakers, Identified in Initiative Element One Will Be Provided by 890815.Util Estimates That 750 nonsafety-related Breakers in Warehouse Stock Examined as Part of Initiative Element Two ML20247D2491989-07-12012 July 1989 Forwards Communications Repts Associated W/Design Control Review ML20247A9261989-05-11011 May 1989 Forwards State of Tx & Local Govt Objectives for Graded Exercise Scheduled for 890725-26 ML20245J3341989-04-0707 April 1989 Forwards Summary of Points of Agreement Reached at 890308 Meeting.Agreements Will Be Subj to Further Discussion Among Parties.W/Certificate of Svc.Served on 890427 ML20246H4791989-03-0606 March 1989 Forwards Communications Repts Associated W/Corrective Action Programs for Plant Independent Assessment Program Phases ML20206F7201988-11-14014 November 1988 Forwards Communications Rept Transmittal 47 Re Independent Assessment Program on All Phases of Conduit Support Design Review ML20151X2621988-08-19019 August 1988 Forwards Rev 4 to Independent Assessment Program:Conduit Support Design Review Issues List for Comanche Peak Electric Station - Unit 1 ML20154H6281988-05-21021 May 1988 Requests to Be Advised at Earliest Opportunity Whether Projected Schedule for Issuance of Phase IV Rept Available. Related Correspondence ML20147G2941988-03-0303 March 1988 Forwards Communication Repts Re Cable Tray Audits,Per Independent Assessment Program ML20147F8911988-03-0303 March 1988 Forwards Communications Repts Associated W/Piping/Pipe Support Audits ML20147H4891988-03-0303 March 1988 Forwards Communications Repts Associated W/Independent Assessment Program Conduit Audits ML20147G2261988-03-0303 March 1988 Forwards Communications Repts Associated W/Civil/Structural Audits ML20196F7451988-02-23023 February 1988 Forwards Surveillance Repts Associated W/Phase 4 Independent Assessment Program Obtained During Util Review ML20196D4541988-02-0909 February 1988 Forwards Rev 4 of Mechanical Review Issues List (Ril). Rev Includes Review Issue 10 Re Component Cooling Water Sys Butterfly Valve at Outlet of Residual Heat Removal Hx.Rev of Ril Reflects Info That Cygna Gained Prior to Dec 1987 ML20236X2701987-11-25025 November 1987 Forwards Communications Repts on Independent Assessment Program,Phase 4 Re Cable Tray,Civil/Structural & Conduit Audits ML20236S1281987-11-13013 November 1987 Forwards Communications Repts Associated W/Civil/Structural Audits.List of Communications Repts Encl ML20236R9531987-11-13013 November 1987 Forwards Communications Repts Associated W/Cable Tray Audits.List of Communication Repts Encl ML20236S3231987-11-13013 November 1987 Forwards Communications Repts Associated W/Conduit Audits. List of Communications Repts Encl ML20236R9361987-11-13013 November 1987 Forwards Communications Repts Associated W/Piping/Pipe Support Audits.Repts Also Listed in Attachment ML20236M3131987-11-0909 November 1987 Forwards Communications Repts Associated W/Cable Tray Audits,Per Communication Repts Transmittal 33 for Independent Assessment Program - All Phases.List of Encl Communication Repts Provided on Attachment 1 TXX-6932, Advises That Value of 7.43 Ph Units Reported in Performance Evaluation Rept DMR-QA Study 7 Re 1987 NPDES QA Program Incorrect Due to Clerical Error.Reported Value Should Have Been 8.43 Ph Units,Which Is within Acceptable Range1987-11-0606 November 1987 Advises That Value of 7.43 Ph Units Reported in Performance Evaluation Rept DMR-QA Study 7 Re 1987 NPDES QA Program Incorrect Due to Clerical Error.Reported Value Should Have Been 8.43 Ph Units,Which Is within Acceptable Range ML20235W3331987-10-10010 October 1987 Forwards Communications Repts Re Civil/Structural Audits,Per Independent Assessment Program,Phase 4 ML20235V4691987-10-10010 October 1987 Forwards Communications Repts Re Cable Tray Audits,Per Facility Independent Assessment Program,Phase 4 ML20235R4941987-09-30030 September 1987 Notifies of Confirmation That Util Given Extension Until 871026 to Respond to Case Motion to Compel Applicants to Supply Complete Answers to Consolidated Intervenors Interrogatories & Request for Production of Documents ML20235R1961987-09-18018 September 1987 Forwards Rev 4 of Pipe Support Review Issues List. Any Procedural Control Issues Associated W/Author Original Pipe Support Reviews of Gibbs & Hill Being Processed as Part of Ongoing Design Control Assessments ML20235R0571987-09-18018 September 1987 Forwards Communications Repts Re Cable Tray Audits ML20234B1451987-09-16016 September 1987 Forwards Rev 4 to Pipe Stress Review Issues List (Ril).All Technical Issues Associated W/Discipline Closed.Still Waiting for S&W Calculation 15454-NZ(B)-GENX-035,Rev 2 to Verify Completion of Commitments Associated W/Ril 11 TXX-6718, Forwards Listed Outstanding Documents Requested Through Audits of Ebasco Svcs,Inc1987-09-0404 September 1987 Forwards Listed Outstanding Documents Requested Through Audits of Ebasco Svcs,Inc ML20238E5591987-09-0303 September 1987 Confirms That Brazos Understanding of Phrase,As Set Forth in Objections & Responses of 870814,essentially Correct. Related Correspondence ML20237K7081987-09-0101 September 1987 Forwards Communications Rept Transmittal 28,transmitting Cable Tray Audits Re Independent Assessment Program - Phase 4 for Plant.Delay in Processing Telcons Noted Due to Word Processing Sys Conversion.W/O Encl ML20237K7931987-09-0101 September 1987 Forwards Communications Rept Transmittal 29,transmitting Piping/Pipe Support Audits for Independent Assessment Program Phase 4.W/o Encl ML20237J9981987-09-0101 September 1987 Forwards Communications Rept Transmittal 27,transmitting Conduit Audits Re Independent Assessment Program - Phase 4 for Plant.Delay in Processing Telcons Noted Due to Word Processing Sys Conversion.W/O Encls ML20237K0091987-08-11011 August 1987 Memorializes Recent Conversations & Resulting Agreement Re Extension of Time Until 870908 for Filing Case & M Gregory Response to Applicant 870713 Motion for Reconsideration of Board 870622 Order.Related Correspondence ML20237J1281987-08-10010 August 1987 Forwards Rev 14 of Cable Tray Supports Review Issues List. Rev Based on Info Provided in Util Rev 2 to Generic Issues Rept for Cable Tray Hangers,Transcripts of Public Meetings & Results of Cynga Audits Through 870731 ML20236D3271987-07-22022 July 1987 Forwards Rev 0 to Civil-Structural Review Issues List, Based on Ref Info,Transcripts of Public Meetings,Documents Provided by Util & Results of Cygna Audits Through 870613 1999-06-16
[Table view] Category:EXTERNAL LETTERS ROUTED TO NRC
MONTHYEARML20056B3741990-08-21021 August 1990 Forwards Update to ASME Section Iii,Div 1 Code Control Program Documents for Incorporation Into State of Tx Dept of Licensing & Regulation Controlled Manual CCPM-15 ML20011E1521990-01-27027 January 1990 Forwards Addl Case Concern Repts 89-0025 Re Apparent Substandard Shop Applied Welds Internal to Secondary Side of Steam Generators & 89-0034 on Specific Wiring & Connection Method Damaging safety-related Electrical Wiring ML20248D0661989-09-21021 September 1989 Notifies Util of Case Position on Concerns & Problems in Scaling Calculation Program at Plant.Documentary Info Supporting Util Position on Aspect of Dispute Should Be Provided ML19332E0011989-09-14014 September 1989 Forwards Offsite Portion of Annual Emergency Preparedness Independent Review Per 10CFR50.54(t) ML19332D4781989-09-14014 September 1989 Forwards Offsite Portion of Annual Emergency Preparedness Independent Review to Be Conducted Every 12 Months.Review Must Include Evaluation for Adequacy of Interfaces W/State & Local Govts ML19332C8171989-09-14014 September 1989 Forwards Offsite Portion of Annual Emergency Preparedness Independent Review & Status of Corrective Actions Initiated, Per 10CFR50.54(t) ML19332C7971989-09-14014 September 1989 Forwards Offsite Portion of Annual Emergency Preparedness Independent Review & Status of Corrective Actions Initiated, Per 10CFR50.54(t) ML20246A0421989-08-18018 August 1989 Advises That S&W Notified by Util That Responsibility for Facility Code Control Program Will Be Terminated Effective on 890823.EBASCO Svcs,Inc Selected to Assume Responsibility for Code Control Program Effective on 890824 ML20247R7291989-07-28028 July 1989 Advises That Status of Suspect molded-case Curcuit Breakers, Identified in Initiative Element One Will Be Provided by 890815.Util Estimates That 750 nonsafety-related Breakers in Warehouse Stock Examined as Part of Initiative Element Two ML20247D2491989-07-12012 July 1989 Forwards Communications Repts Associated W/Design Control Review ML20247A9261989-05-11011 May 1989 Forwards State of Tx & Local Govt Objectives for Graded Exercise Scheduled for 890725-26 ML20245J3341989-04-0707 April 1989 Forwards Summary of Points of Agreement Reached at 890308 Meeting.Agreements Will Be Subj to Further Discussion Among Parties.W/Certificate of Svc.Served on 890427 ML20246H4791989-03-0606 March 1989 Forwards Communications Repts Associated W/Corrective Action Programs for Plant Independent Assessment Program Phases ML20206F7201988-11-14014 November 1988 Forwards Communications Rept Transmittal 47 Re Independent Assessment Program on All Phases of Conduit Support Design Review ML20151X2621988-08-19019 August 1988 Forwards Rev 4 to Independent Assessment Program:Conduit Support Design Review Issues List for Comanche Peak Electric Station - Unit 1 ML20154H6281988-05-21021 May 1988 Requests to Be Advised at Earliest Opportunity Whether Projected Schedule for Issuance of Phase IV Rept Available. Related Correspondence ML20147F8911988-03-0303 March 1988 Forwards Communications Repts Associated W/Piping/Pipe Support Audits ML20147G2941988-03-0303 March 1988 Forwards Communication Repts Re Cable Tray Audits,Per Independent Assessment Program ML20147H4891988-03-0303 March 1988 Forwards Communications Repts Associated W/Independent Assessment Program Conduit Audits ML20147G2261988-03-0303 March 1988 Forwards Communications Repts Associated W/Civil/Structural Audits ML20196F7451988-02-23023 February 1988 Forwards Surveillance Repts Associated W/Phase 4 Independent Assessment Program Obtained During Util Review ML20196D4541988-02-0909 February 1988 Forwards Rev 4 of Mechanical Review Issues List (Ril). Rev Includes Review Issue 10 Re Component Cooling Water Sys Butterfly Valve at Outlet of Residual Heat Removal Hx.Rev of Ril Reflects Info That Cygna Gained Prior to Dec 1987 ML20236X2701987-11-25025 November 1987 Forwards Communications Repts on Independent Assessment Program,Phase 4 Re Cable Tray,Civil/Structural & Conduit Audits ML20236S3231987-11-13013 November 1987 Forwards Communications Repts Associated W/Conduit Audits. List of Communications Repts Encl ML20236S1281987-11-13013 November 1987 Forwards Communications Repts Associated W/Civil/Structural Audits.List of Communications Repts Encl ML20236R9531987-11-13013 November 1987 Forwards Communications Repts Associated W/Cable Tray Audits.List of Communication Repts Encl ML20236R9361987-11-13013 November 1987 Forwards Communications Repts Associated W/Piping/Pipe Support Audits.Repts Also Listed in Attachment ML20236M3131987-11-0909 November 1987 Forwards Communications Repts Associated W/Cable Tray Audits,Per Communication Repts Transmittal 33 for Independent Assessment Program - All Phases.List of Encl Communication Repts Provided on Attachment 1 TXX-6932, Advises That Value of 7.43 Ph Units Reported in Performance Evaluation Rept DMR-QA Study 7 Re 1987 NPDES QA Program Incorrect Due to Clerical Error.Reported Value Should Have Been 8.43 Ph Units,Which Is within Acceptable Range1987-11-0606 November 1987 Advises That Value of 7.43 Ph Units Reported in Performance Evaluation Rept DMR-QA Study 7 Re 1987 NPDES QA Program Incorrect Due to Clerical Error.Reported Value Should Have Been 8.43 Ph Units,Which Is within Acceptable Range ML20235V4691987-10-10010 October 1987 Forwards Communications Repts Re Cable Tray Audits,Per Facility Independent Assessment Program,Phase 4 ML20235W3331987-10-10010 October 1987 Forwards Communications Repts Re Civil/Structural Audits,Per Independent Assessment Program,Phase 4 ML20235R4941987-09-30030 September 1987 Notifies of Confirmation That Util Given Extension Until 871026 to Respond to Case Motion to Compel Applicants to Supply Complete Answers to Consolidated Intervenors Interrogatories & Request for Production of Documents ML20235R1961987-09-18018 September 1987 Forwards Rev 4 of Pipe Support Review Issues List. Any Procedural Control Issues Associated W/Author Original Pipe Support Reviews of Gibbs & Hill Being Processed as Part of Ongoing Design Control Assessments ML20235R0571987-09-18018 September 1987 Forwards Communications Repts Re Cable Tray Audits ML20234B1451987-09-16016 September 1987 Forwards Rev 4 to Pipe Stress Review Issues List (Ril).All Technical Issues Associated W/Discipline Closed.Still Waiting for S&W Calculation 15454-NZ(B)-GENX-035,Rev 2 to Verify Completion of Commitments Associated W/Ril 11 TXX-6718, Forwards Listed Outstanding Documents Requested Through Audits of Ebasco Svcs,Inc1987-09-0404 September 1987 Forwards Listed Outstanding Documents Requested Through Audits of Ebasco Svcs,Inc ML20238E5591987-09-0303 September 1987 Confirms That Brazos Understanding of Phrase,As Set Forth in Objections & Responses of 870814,essentially Correct. Related Correspondence ML20237K7931987-09-0101 September 1987 Forwards Communications Rept Transmittal 29,transmitting Piping/Pipe Support Audits for Independent Assessment Program Phase 4.W/o Encl ML20237J9981987-09-0101 September 1987 Forwards Communications Rept Transmittal 27,transmitting Conduit Audits Re Independent Assessment Program - Phase 4 for Plant.Delay in Processing Telcons Noted Due to Word Processing Sys Conversion.W/O Encls ML20237K7081987-09-0101 September 1987 Forwards Communications Rept Transmittal 28,transmitting Cable Tray Audits Re Independent Assessment Program - Phase 4 for Plant.Delay in Processing Telcons Noted Due to Word Processing Sys Conversion.W/O Encl ML20237K0091987-08-11011 August 1987 Memorializes Recent Conversations & Resulting Agreement Re Extension of Time Until 870908 for Filing Case & M Gregory Response to Applicant 870713 Motion for Reconsideration of Board 870622 Order.Related Correspondence ML20237J1281987-08-10010 August 1987 Forwards Rev 14 of Cable Tray Supports Review Issues List. Rev Based on Info Provided in Util Rev 2 to Generic Issues Rept for Cable Tray Hangers,Transcripts of Public Meetings & Results of Cynga Audits Through 870731 ML20236D3271987-07-22022 July 1987 Forwards Rev 0 to Civil-Structural Review Issues List, Based on Ref Info,Transcripts of Public Meetings,Documents Provided by Util & Results of Cygna Audits Through 870613 ML20216D1721987-06-20020 June 1987 Ack Receipt of .Clarifies Agreement Made During Telcon Re Date for Case to File Initial Supplementary Responses Deferred Until 870706.Necessary Discovery & Response Should Be Completed Also.Related Correspondence ML20215D7141987-06-0303 June 1987 Informs All Concerned W/Facility Independent Assessment Program of Address Correction ML20214S0641987-05-26026 May 1987 Ack Receipt of Applicant 870518 Fifth Progress Rept.Requests That Recipient Notify of When Substantive Matls Will Be Made Available So Case May Decide on Course of Action Re Comanche Peak Response Team Adequacy Issues.Related Correspondence ML20234C6731987-05-0101 May 1987 Forwards Communications Repts Associated W/Cygna Audits of S&W Civil/Structural Action Plan Re Plant Independent Assessment Program - Phase 4 ML20234C4401987-05-0101 May 1987 Forwards Communication Repts Re Cygna Audits of S&W Piping & Pipe Support Verification Activities,Per Phase 4 of Independent Assessment Program.Submittal Constitutes Communications Rept Transmittal 23 TXX-6361, Forwards Receipt to Ack Part 21 Rept Re Qualification Test Rept F-C5205-3, Nuclear Qualification - Terminal Blocks1987-03-23023 March 1987 Forwards Receipt to Ack Part 21 Rept Re Qualification Test Rept F-C5205-3, Nuclear Qualification - Terminal Blocks ML20205C0741987-03-18018 March 1987 Forwards Comments & Questions on Ebasco & Util Procedures & Criteria Re Responses to Conduit Support Review Issues List for Upcoming 870324 & 25 Conduit Support Meetings Per Rev 0 to Generic Issues Rept 1990-08-21
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TENAS UTILITIES GENERATING CO.11%NY
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- 47 Cygna Energy Services y , /, f Af , g 101 California Street !m.
f Suite 1000 // Ar - dc / 6 San Francisco, Califomia 94111 [cPoss arr. FILE Attention: Ms. Nancy Williams ProjectManager 00mNGE PEAK STEAM ELECTRIC STATION .
Gentlemen:
In response to your handwritten questions provided to WGC0 on March 16, 19, 20, 21 and 22, enclosed is a copy of the questions followed by WGCO's response. Several questions are still under review and will be answered shortly. In addition, questions asked via telephone to Dave Rencher on March 30, 1984, are presently being reviewed and responses will be for-warded by April 27th.
If there are any further questions or comments, please contact me or George Grace (Site Ext. 500).
Very truly yours, TEXAS UTILITIES GENERATING COfPANY ENGINEERING DIVISION
. 7J L. M. Popplewell Project Engineering Manager gggg A/N W M l IJfP/cp h0N d.tu.abga) c YC C. (skMf In.%Lmar l
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March 16, 1984 ,
CYGNA COPMENT:
- 1. In reviewing supports MS-1-002-006-572R and MS-1-004-006-S72R.
CYGNA has noted use of A563, Grade A nuts on 1-1/8" diamet'er 197 B7 threaded rod. Per the ASTM specification for this nut.
Please pmvide Grade A is suitable only for A307 material.
documentation justifying this material usage.
TUGC0 RESPONSE:
- 1. It is common practice to use A 194 2H (or equivalent) nuts on A 193 B7 rods. However, use of double A563, Grade A, nuts will allow sufficient thread area that the use of high strength rod allowables is justified, since the tensile allowable load for high strength bolting material is approximately twice that .
of standard material ( A563).
CYGNA COMMENT:
- 2. In reviewing a number of supports inside containment (for example, MS-1-003-008-C72K), CYGNA has noted tube steel with bolts through the steel into inserts. In all cases, the mtation about I in the In most cases, the rotation "STRUDL" model is released at the bolts.
about X is also released. While this is conservative for the member, the subsequent calculations do not account for the possibility of prying by the tube / washer on the concrete. Attached is a calculation Has the prying by CYGNA which indicates potential design impact.
effect been considered? If so, where is this documented 7 TUGC0 RESPONSE:
- 2. (This question has been assigned to NPSI. A formal response will be issued by the Secaucus office by 4/23/84).
March 19, 1984 CYGNA COMfiENT:
- 1. In reviewing the calculations for U-bolts used in supports, CYGNA has noted instances where:
a) A 2" p U-bolt is called out, with no vendor specified, nor any design calculation supplied (MS-1-003-001-C725. Rev. 3).
b) A PUH-340 (21s" p) U-bolt is called out, but this does not appear in the NPSI catalogue. The designer then qualified the bolt based on a pure tensile check (.6Fy). ( MS-1-002-001-c)
S72R, Rev. 3)(2-3/4" p) ITT U-bolt is called out. Since no A Fig. 1375N allowable is supplied, the designer qualifies the bolt based on a combination of tensile and side load (because of swing angle). When the side load causes failure, a memo from IfT is used to accept side loads (due to swing angles up to 5 )
.- without tensile load reduction. The designer then qualifies the bolt based on tensile alone. (MS-1-002-004-572R. Rev. 2)
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' ' page 2 i
1 .
l* d) Again, in MS-1-003-006-572R, a designer qualifies a Fig.
137N 2-3/4" p U-bolt based on tensile stress only, although l the designer does use the root area of the bolt (conservative).
In all cases, except where no check was done, there was no attempt !
j to consider the complex stress pattern of the U-bolt as a bent beam t i
with a distributed load.
i TUGC0 RESPONSE:
)
1 1. U-bolt' allowable loads i
a) TUGC0 answer will be provided later.
b, c, d) ITT-Grinnell is preparing a statement based on a test
! program they are conducting. Release of that statement in 4 .
the week of 4/23/84 will supplement this statement. Vendor !
supplied Load Capacity Data Sheets (LCD's) contain U-bolt *
- allowable load information based on MSS-58 which limits allowable stress to 9000 psi. This low allowable is desira-ble to use for original design and quick checking, but is certainly not required by NF.
At the designer's discretion and in the absence of published '
j 4
allowables, a pure tension (or combination of tension and i shear) check is acceptable, comparing calculated stresses l with NF allowables. Attempting to consider the U-bolt as a 1
bent beam with a distributed load is a very complex task and is not realistic. The above tests will indicate clearly that the methods of analyses being used are conservative.
- The vendors (ITT and NPSI) have not provided documentation l
on qualification methods for non-standard U-bolts. (Note:
ITT is reviewing calculations pertaining to item (c) and i will issue a supplement to their calculation package.)
l i :
i CYGNA COMMENT:
i l
- 2. CVGNA has noted instances in the CCW system (CC-1-028 003-A33R, ,
4 CC-1-028-001-A33R) where no gap is specified for a pipe within [
a frame. Has TUSI done a' study to show that, below a certain l
! l j
pipe temperature, pipe growth effects are negligible, since it !
is standard practice to use a 1/16" gap?
J i
l TUGC0 RESPONSE:
j i
- 2. The 1/16" gap is required in a rigid frame to allow fme axial
' thermal expansion of the pipe. For rigid frames at CpSES all vendors specify the appropriate gaps in accordance with their design procedures. On the two supports in question, the frame
' is on a pinned connection and hence the entire trapere will i displace as'the pipe moves; no axial support is introduced into !
l the system, therefore no gap is required.
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1 Diametrical thermal expansion of the pipe can induce additional
!' loads into the support frame (and especially the welded connections). f 1
These loads need to be combined only with nomal and upset mechanical loads from the pipe onto the frame and are self-relieving in nature.
The allowable for this load combination from NF is increased by a factor of 3 over nomal allowables. A study has been conducted on l
j j
this issue and is summarized below:
Frame - 6x4xis tube steel (4" contacting pipe)
Pipe - 24 Component Cooling (3/8" wall)
Resulting 1.oad F Resulting Additional Pipe Stress Temp. Pipe 454 lbs 7104 psi 200* F 1886 psi 130 F 163 lbs
! The detailed calculations are available at the site. The additional '
- load is quite low compared to the NF allowables increased by a factor of 3. '
CYGNA COMMENT:
! 3. In reviewing the MS pipe support design calculations, CYGNA has j
seen many instances where components are not checked. In some In there is reference to previous cales which are not included.
j others, there is no reforence. As an example, CYGNA has chosen i
MS-1-003-013-C72K.
As noted on the attached sheets, most of the l
! items are acceptable.
i ,
Question a) Why are there no calculations or documentation for the standard supports?
! b) Who is responsible for insuring that the data on drawings ,
is correct? l c) What size U-bolt is in the field, Ik" p or 1-3/4" p?
i d) How does NPSI/ITT ensure that all parts of a design have i'
been checked, if a package does not contain or reference
! all the data?
! TUGC0 RESPONSE: ,
I Before responding to the specific questions some general comments
~
3.
are in order. It is not uncommon for a designer to use standard catalog callouts for convenience, even thoughCommon the item is not examples are vendor supplied, but is fabricated at site.
l thmaded rods (RAT RET, RFT), washer plates (RWP), and U-bolts (PUS,PIM). Explanatory information in the bill of meterial over-i For example, !
3 rides standard size designations from the catalogue.
an RET may be specified with an extended thread length; an RWP may show a larger thickness; and a PUS may be specified with a larger rod diameter.
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Page 4 Specifically, (a) ,many standard support items are verified in the original design calculations and not re-checked as part of the vendor certification process when the as-built load decreases from or stays the same as the original design load. (b) The design engineer is responsible for assuring that data on t.he drawings is correct; QC is responsible for assuring)that the For the product in the field matches the design drawing. (c support in questions, a 1-3/4" 9 U-bolt is installed in the field.
(d) All design changes to a support must be reviewed and approved If the cumulative changes to by the original design organization. the a support are minor (from original design to final product),The otiginal certification calculation will only verify the changes.
calculation package will contain data to assure acceptability of the rest of the support. For substantial design changes, entire net; This methodology is ad-calculations are generated for the support.
dressed in the procedures of the support vendors.
CYGNA COMMENT:
- 4. In reviewing certain U-bolt and beam combinations, CYGNA has noted instances where the local effect of the U-bolt on the beam is not For example, in MS-1-003-001-C725, the U-bolt has an considered. As shown in applied load of 23.7K, and is attached to 6x6xh" TS.
the CYGNA calculations, the local bending stress in the top portion of the tubesteel is quite high. How does TUSI/NPSI/ITT determine if connections can carry the applied load? Are standard tables available?
TUGC0 RESPONSE:
- 4. Local stresses in this type of connection are normally checked standard on a case by case basis when considered significant;This unreinforce tables are not in use.
not used where a large load is present and should not have been used here. This is an isolated case that was overlooked in the support certification. This is a spring hanger which has already experienced its full load and a field observation hasthere Thus, clearlywill indicated that there is no local deformation.In addition we feel not be ultimate failure of this member.
CYGNA calculations are incorrect since they have not taken into effect the rounded corners of the tubesteel Out nortotheout correct loaded ares under the nut (see sketch on attached sheet).
on the nut almost covers the entire flat portion of the top of the tube steel. Pursuant to good, conservative engineering practice, however, washer plates will be added.
CVGNA C00 MENT:
- 5. In reviewing installations with 0" gap around U-bolts, CVGNA has the following questions:
a) On Page 11 of CP-CPM-9.10. Rev.11. snug tight is defined twice.
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" NOTE: Snug tight is defined as the tightness attained by a few impacts on an impact wrench or the full effort of.a man using an ordinary spud wrench."
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"When U-bolts are specified on the design document as hot having any clearances, the U-bolt shall be snug tight so ,
4 that the U-bolt cannot be moved by hand. The nuts on the :
U-bolt shall be installed on the side of the plate as shown on the design drawing."
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Which is used for installation of U-bolts?
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b) In support CC-1-028-007-533R, a PUS-240 U-bolt is used to '
l provide support stability. If " snug tight" is taken as the ;
i first definition, this could mean--80 ft-lbs of torque since:
1 i
' T = .2FD '
i T = 80 ft-1b = 960 in-lb l
" D = 1" for a PUS-240
' .F = 4800 lb/ leg i 5
For piece 15 (1/4x4x4 (,)
rf 4800 (2) , , p, i
4(.25) 6 How does the installation procedure insure that the). will I
not be deformed?
c) In reviewing support MS-1-004 003-572R, CYGNA has noted no gap shown on the drawing and both nuts on the same side of the beam, implying the U-bolt is " snug tight."
1 Have the local pipe stress and increased U-bolt load due
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to .500 F thermal expansion been considered? ,
l TUGC0 RESPONSE:
i i 5. (a) For the installation of U-bolts, snug tight is defined as i
" ... the tightness attained by a few impacts on an impact wrench When
- or the full effort of a man using an ordinary spud wrench."
QC inspects U-bolts, if the nuts are tight and the U-bolt cannot ;
be moved by hand, then their inspection criteria for snup and tight i
is satisfied. (b) The expression "T=0.2FD" is empirica may not be applicable to U-bolts, Visual inspection of the support in the field has shown no defor- l t
mation of the clip angle. QC, as part of their normal support !
l inspection, assures that structural members (including these angles) 4 We have performed calculations that show that clip l
are not deformed.
i angles used for these type supports may be highly stressed, r perform their function.
l and as a matter of geod conservative practice, we are in the process i l of modifying these supports to remove the clip angles as support for i
. the U-bolts. (c) No gap shown on the design drawing with both nuts on the same side of the beam is the proper configuration for snug
Page 7 tight installation. Local pipe stresses and U-bolt stress increases due to diametrical' pipe expansion will be addressed at the completion of the ongoing,U-bolt test program. Our original assumption was that thermal stress effects on both the U-bolt and pipe would be negligible because the pipe and U-bolt were in contact and wrapped in. insulation, yielding a low temperature differential between the two. Calculations have been performed that substantiate our original assumptions. .
March 20,1984 CYGNA COMMENT:
- 1. For the MS springs, CYGNA has not found any design for hydrotest loads. The G&H stress analysis did not include any hyrdotest loading, but an approximation would be:
F hydro - normal (W water W. pipe + W pipe) -
" - 1.7 normal Since the springs are pinned during hydro, they do not need checking. What calculations have been done for the base plates, welds, rods, and bolting to ensure acceptability during hydrotest? If temporary supports are used, are there cales. for design?
(
TUGC0 RESPONSE:
- 1. As part of the design process for pipe supports on steam filled lines, a structural check is made to determine if the support i
can accomodate the hydro loads. If it cannot, a note is put on the drawing to the effect that a temporary support is required for hydrostatic testing. Temporary supports areThe " designed" in MS lines have i
accordance with site instruction CP-E!-4.0-30.
been successfully hydro tested indicating that adequate mechanisms do exist to assure system acceptability.
y CYGNA COMMENT:
- 2. In reviewing the frames, springs, sthuts, and snubbers, CYGNA has noted that in most cases, seismic displacements are not .1" 4
^
chec ked.'
While these displacements are typically small ( (
w/o SAM), (4, is" with SAM), has TUSI considered these in allowing for frame gaps or spring travel?
NOTE:
See attached sumary of displacements for MS inside containment and the CC line.
TUGC0 RESPONSE:
- 2. TUSI, and the pipe support design organizations, have not consistantly considered seismic displacements in their support '
designs. However, spring supports are designed within their
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working range (generally near mid-travel); a minimum k" travel exists beyond working range limits to reach a fully For most springs, more than extended or retracted position.This is sufficient to account for the small k" is available. For box frames, the seismic movements seismic displacements.
for the supports listed were checked against the designs.
In all cases, adequate clearance existed to allow combined '
thermal and seismic displacements.
i CYGNA COMMENT: \
- 3. In reviewing certain MS supports, CYGNA has noted instances ,
where beams with small gaps are used to provide stability, l instead of tightening U-bolts (supports MS-1-004-003-572R, l for example). In these cases, no analysis is done on the
" stability bumpers." CYGNA has performed calculations which show that the load on these " supports" could be quite high, assuming one accepts the instability of this structure during dynamic loading. Has TUS! used Also, this design for any supports where is the documentation with static compressive loads?
for the integrity of this support arrangement in general?
TUGC0 RESPONSE:
- 3. The " bumpers" supplied on MS 1-004 003 572R (in lieu of a snug U-bolt) for stability are designed to take an oscillating, momentary load (for a system at 20Hz, the applied loadthe Hence, onto the bumpers will act less than 0.05 seconds).
nature of the cyclic load assures stability in that there is j not sufficient time for a constant applied force to push the The calculations i bumpers back and allow the pipe to lift up.
which consider a static upward load are therefore erroneous.
The stress in the bumper steel stays within its elastic limit under the impact load and hence will return to itsThis original design l position when the load reverses and pushes down.
has not been used on any supports which would experience a static compressive load. Structural acceptability of the bumpers is based on the momentary load of less than 0.05 second duration. Size of the members, welds, were judged adequate by inspection.
March 21, 1984_
CYGNA COMMENT:
- 1. In reviewing MS 1-004-001-C725, CYGNA had the following questions:
a)
There appears to be a 7/16" flare bevel weld between itemsDoes !
15 and 22. This does not seem possible due to Item 34.
TUSI haveL,ikewise, of this weld? documentation conforming the weld 5/16") between 26 (the andsize 157 and co r
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The model uses a fixed point at the embed plates (3. 6.12 b) 15 joints). Spec. 2323-55-30, Rev.1, requires these to be treated as pin joints, unless the embedment is stiffened.
Where is the stiffener in this calc, and has structural accepted this configuration?
c) Per ASME Appendix XVII, Para. 2442, shear loads on connections with both welds and bolts must be taken by -
the welds alone. Item 16 is attached to team #21 with both welds and Hilti's. The weld sizing calculations What is done use the bolts to share the shear load.
TU51's standard practice in this type of connection? Is this weld acceptable?
d)
The weight of the constant support itself is not included in the support design load for the frame. A #53 constant weighs - 600 lb, or 5% of the design load.
- What is TU5!'s standard practice for spring anchorage design?
TUGC0 RESPONSE:
- 1. (a) In the NPS! original design,is" well tube steel was used and the 7/16" flere bevel weld was possible. Modifications made The at the site changed most of the steel members to 3/8" wall tube.
weld between items 15 and 22 is a flare bevel weld such that the groove is filled and ground flush to facilitate installation of tem 34 CYGNA is correct in their observation that a 7/16" flare bevel weld does not exist, the size was inadvertantly not removed durinf) the revision process. The stiffeninti effect The of Item 34 on th's joint assures structural acceptabil'ty.
5/16" flare bevel weld between items 26 and 15 is an acceptable weld since the tube steel thickness is 3/8" (greater than 5/16").
Documentation confirming the size of these weids is on file with (b) See comments dated 3/22, QC in their inspection package. Items 15 and 19 are connected to response 1. (c) beam 21,notitem16.) (EditorialThe connection to the beam via embe plate (f.e., by welding) and As via baseplate such, each is (i.e., by capable of bolting)ing resist is at separate locations. using shear. It should be noted that Hilti joints are designed bolt shear allowables based on ultimate test loads divided by 5.
This is not the standard engineering approach to design a bearing or friction joint using code allowables for the bearing or friction condition. Using our design approa'ch, the Hilti joints, since they are pre torqued, would perfom as a friction joint within their working loads. At ultimate loads all joints (bearing or friction) would act as bearing joints (i.e., slip would occur in the friction connection). (Following comments, in response to CVGNA's comment on TU$1's standard practice are provided here for infomation only).
Connections of the type shown below have been used to some extent where space is limited, py"
- Fillet Weld Base plata --
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- "Hilti" Bolt )
Embedded plates gN#
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page 10 Generally, the weld on the embedded plate is modelled as a pinned connection such that prying action in the baseplate is *naximized. Since the Hiltis have a lower capacity than the welds, it is assumed for qualification purposes that the Hiltis resist some shear. This is conservativeApplying in that it maximizes stresses in the weak link of the system.
the total shear in the connection to (d)the CVGNA weldrequesteddoes n6t cause an overloaded condition in the weld. '
information on supports where the weight of the support assembly could be a significant part of the design This load and question could effect the adequacy of the pipe support.
is limited to supports that were not analyzed using "$TRUDL" (i.e.,determinantstructures)sinceSTRUDLanalysisincludes all dead weight loads. The worst case condition would occur in supports having a relatively small design load and a heavy assembly, for example, a constant or spring support as indicated by CYGNA.
We have examined 20 as-built supports of various types and found that in no cases did the assembly weight exceed 6% of the design load used in the design calculations.
(CYGNA indicates dead load as approximately 5% of the design load.) In addition, the weight of the hardwareTherefore, is propor- the tional to the load it is designed to support.
variance in the design load due to the support assembly dead weight will remain within the 6% limit.
A 6 % variance in the design load is negligible when compared to the inherent design conservatisms of the variousTherefore, support components and construction techniques employed.
the design support is considered adequate.
CYGNA COMMENT:
2.
In the spring design loads for the main steam system. CVGNA cannot match the loads in the design calc to the loads in the data transmitted by G&H. How has the design load for a spring been calculated?
TUGC0 RESPONSE:
- 2. Design load for a spring is based on the latest information that the responsible pipe stress organization (Gibbs Piping & Hill or Westinghouse) Supplied to the support The designer.
or an insignificent load increase on a spring support.
piping analyst, using his discretion, may not transmit these load changes to the field support designer due to their in-The load differences in the examples consequential effect.
provided by CVGNA are indi:stive of this practice (i.e., the differences are negligible).
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f Page 11 t
March 22,1984 CYGNA COMMENT: '
- 1. In CC-1-O31-008-S33R, CYGNA has noted another instance of a
" fixed" joint at an embed plate, rather than a " pin"ijoint (see comments on MS-1-004-001-C725, dated 3/21). In this case, a " fixed" assumption is needed, since self-weight was, considered. The civil Spec. (S5-30) requires stiffeners be provided..
a) Is piece 7 considered the stiffener?
b) Has the civil group provided guidelines for stiffeners?
c) What direction has TUSI given the support designers in using embed plates as " fixed" connections?
d) The designer appears to use conservative cales in determinir.o olate loads. Then, he uses the highest plate allowables. What is TUSI's direction for
- determing embed plate allowables?
TUGC0 RESPONSE:
- 1. a) For support CC-1-031-008-533R, Item 7 is considered as the stiffener. (b) The site Civil Group has not provided formal guidelines for stiffeners. (c) Any attachment to an embedded plate (whether it's a rear bracket, flat plate, tube steel member, etc.) will effectively stiffen the embedded Thus, the transfer plate in the local area where it attaches.
of moments into the embed through a stiffened area is a good assumption. (d) Embedded plate allowables are extracted from Specification 2323-55-30. Loads applied at stud locations permit use of a higher plate allowable while a lower allowable is used for loads acting at mid-span between studs. Field ~
verification of Nelson Stud location with respect to the applied load may be used in determing allowable limits.
CYGNA COMMENT:
- 2. In reviewing CC-1-028-022-533K, CYGNA has not found any checks of the hardware, other than references to previous design cales. CYGNA has checked piece 3Using (24" special riser the " max clamp) against the Grinnell 0 load sheets.
operating temp" of 200 F from the line list, the emergency allowable for the clamp is (94' c-c):
E=1.25(16,800)
= 21,000 lb Since E act = 21,964 lb, this support may fail, assuming the above calc. is OK.
Since the cale states the original design loads were higher, a) what is the correct procedure for calculating clamp allowables?
b)
Has TUSI considered that one snubber may be more highly loaded than the other, due to pipe rotation?
+
s
. Page 12 TUGC0 RESPONSE:
2, a)Reviewoftheogig(inaldesfcncalculationsshowsadesign temperature of 128 F not 200 which puts the clamp within its L.CD allowables, even with the larger design loadiconsidered.
The original calculations indicate there was a conscious effort made to determine the actual temperature in order to correct,1y design the clamp. b) Later.
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