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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:INCOMING CORRESPONDENCE
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 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 ML20216J5571999-10-0101 October 1999 Provides Final Response to GL 98-01,suppl 1, Y2K Readiness of Computer Sys at Npps TXX-9922, Forwards Revised COLR, for Cycle 5 for Unit 21999-10-0101 October 1999 Forwards Revised COLR, for Cycle 5 for Unit 2 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 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 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 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 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 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 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 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 ML20210S6411999-08-12012 August 1999 Informs That Wg Guldemond,License SOP-43780,is No Longer Performing Licensed Duties.Discontinuation of License Is Requested 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 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 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 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, 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 ML20210D3211999-07-21021 July 1999 Provides List of Estimates of Licensing Actions,In Response to Administrative Ltr 99-02,dtd 990603 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 ML20209H0111999-07-16016 July 1999 Forwards Relief Request C-4 to CPSES Unit 2 ISI Program for Approval ML20209G0721999-07-13013 July 1999 Forwards Monthly Operating Repts for June 1999 for CPSES, Units 1 & 2,per TS 6.9.1.5.No Failures or Challenges to PORVs of SV Occurred During Reporting Period ML20209F0681999-07-0909 July 1999 Informs That Effective 990514,TU Electric Formally Changed Name to Txu Electric.Change All Refs of TU Electric to Txu Electric on Correspondence Distribution Lists ML20209E0421999-07-0909 July 1999 Forwards Response to NRC Request for Addl Info on LAR 98-010.Attachment 1 Is Affidavit for Info Supporting LAR 98-010 ML20209B6021999-06-30030 June 1999 Submits Second Response to NRC GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Npps. Readiness Disclosure for Reporting Status of Facility Y2K Readiness Encl ML20195J6981999-06-15015 June 1999 Provides Addl Info Related to Open Issue,Discussed in 990610 Conference Call with D Jaffe Re ISI Program Relief Request L-1 Submitted by Util on 980220 ML20196A4921999-06-15015 June 1999 Forwards Rev 30 to Physical Security Plan.Rev Withheld,Per 10CFR73.21 ML20195J0491999-06-14014 June 1999 Submits Response to RAI Re Implementation of 1.0 Volt Repair Criteria ML20195J0651999-06-14014 June 1999 Submits Response to RAI Re GL 95-07, Pressure Locking & Thermal Binding of Safety Related Power Operated Gate Valves 05000445/LER-1999-001, Forwards LER 99-001-00, Some Electrical Contacts for RCS Pressure Relief Valves Were Not Included in Surveillance Testing Procedures. New Licensing Commitments Identified in Attachment 11999-06-0808 June 1999 Forwards LER 99-001-00, Some Electrical Contacts for RCS Pressure Relief Valves Were Not Included in Surveillance Testing Procedures. New Licensing Commitments Identified in Attachment 1 ML20195F0091999-06-0808 June 1999 Forwards Response to RAI Re Units 1 & 2 ISI Program for Relief Requests E-1 & L-1.Communication Contains No New Licensing Basis Commitments Re Cpses,Units 1 & 2 ML20207E1921999-05-28028 May 1999 Submits Updated Request for NRC Staff to Review & Approve Certain Changes to CPSES Emergency Plan Submitted in 981015 & s Prior to Changes Being Implemented at CPSES ML20207E1711999-05-28028 May 1999 Supplements 990526 LAR 99-004 as TU Electric Believes Extingency Exists in That Proposed Amend Was Result of NOED Granted to Prevent Shudown of CPSES Unit 1 ML20207D9841999-05-26026 May 1999 Requests That NRC Exercise Enforcement Discretion to Allow Cpses,Unit 1 to Remain in Mode 1,power Operation,Without Having Performed Svc Test,Per SR 4.8.2.1d on Unit 1 Battery BT1ED2 ML20195B6351999-05-25025 May 1999 Submits Response to RAI Re GL 95-07, Pressure Locking & Thermal Binding of Safety Related Power Operated Gate Valves TXX-9912, Forwards Txu Electric (Formerly TU Electric) CPSES Emergency Preparedness Exercise Scenario Manual for 990721-22,Graded Exercise1999-05-21021 May 1999 Forwards Txu Electric (Formerly TU Electric) CPSES Emergency Preparedness Exercise Scenario Manual for 990721-22,Graded Exercise ML20206U1981999-05-20020 May 1999 Forwards Form 10K Annual Rept,Per 10CFR50.71(b). Communication Contains No New Licensing Basis Commitments Re Cpses,Units 1 & 2 ML20196L1931999-05-20020 May 1999 Forwards MOR for Apr 1999 for Cpses,Units 1 & 2.During Reporting Period There Have Been No Failures or Challenges to Power Operated Relief Valves or Safety Valves TXX-9911, Forwards non-proprietary & Proprietary Responses to RAI Re LAR 98-010 by Incorporating Attached Changes Into CPSES Unit 2 OL NPF-89 & CPSES Units 1,OL NPF-87 & 2 TS to Increase Licensed Power.W & Caldon Proprietary Responses Withheld1999-05-14014 May 1999 Forwards non-proprietary & Proprietary Responses to RAI Re LAR 98-010 by Incorporating Attached Changes Into CPSES Unit 2 OL NPF-89 & CPSES Units 1,OL NPF-87 & 2 TS to Increase Licensed Power.W & Caldon Proprietary Responses Withheld 1999-09-03
[Table view] Category:UTILITY TO NRC
MONTHYEARML20059K6141990-09-17017 September 1990 Submits Documentation of 900906 Telcon Re Addl Util Candidate for Licensed Operator Generic Fundamentals Exam Section ML20059G8761990-09-10010 September 1990 Forwards Rev 8 to Physical Security Plan.Rev Withheld (Ref 10CFR73.21) ML20059F8461990-09-0404 September 1990 Responds to NRC Re Violations Noted in Insp Repts 50-445/90-22 & 50-446/90-22 on 900606-0705.Corrective action:OPT-467A Changed to Provide Addl Prerequisite Info Re Solid State Protection Sys Switch Lineup During Testing ML20059E4981990-08-31031 August 1990 Forwards Revised Radial Peaking Factor Limit Rept for Cycle 1 Per Tech Specs Through Amend 1 & ML20059E4201990-08-30030 August 1990 Forwards Objectives & Guidelines for 1990 Emergency Preparedness Exercise Scheduled for 901113 ML20028G8281990-08-29029 August 1990 Forwards Comanche Peak Unit 1 Semiannual Radioactive Effluent Release Rept,900403-0630 & ODCM TXX-9030, Forwards Endorsements 40 & 4 to Nelia Policy NF-274 & Maelu Policy M-90,respectively & Endorsements 10,11,12,13,14 & 15 to Maelu Policy MF-1311990-08-27027 August 1990 Forwards Endorsements 40 & 4 to Nelia Policy NF-274 & Maelu Policy M-90,respectively & Endorsements 10,11,12,13,14 & 15 to Maelu Policy MF-131 ML20059F4381990-08-23023 August 1990 Forwards Public Version of Revised Emergency Plan & Corporate Emergency Response Procedures,Consisting of Rev 1 to EPP-313,Rev 7 to CERP-101,Rev 7 to CERP-102 & Revised Forms.W/Dh Grimsley 900906 Release Memo TXX-9029, Responds to NRC Re Violations Noted in Insp Repts 50-445/89-57 & 50-446/89-57.Corrective Actions:Storage Facilities for Instrumentation & Control Work Packages Improved to Provide Acceptable Protection for Documents1990-08-20020 August 1990 Responds to NRC Re Violations Noted in Insp Repts 50-445/89-57 & 50-446/89-57.Corrective Actions:Storage Facilities for Instrumentation & Control Work Packages Improved to Provide Acceptable Protection for Documents ML20058P0571990-08-13013 August 1990 Forwards, Comanche Peak Steam Electric Station Unit 1 Control Room Simulator 10CFR55 Certification Initial Rept TXX-9026, Forwards Addendum to Unit 1 Preservice Insp (PSI) Summary Rept, Providing Remaining Info & Editorial Corrections Re PSI & Addressing Exams & Tests of Code Class 1 & 2 Sys as Stipulated in PSI Plan1990-08-13013 August 1990 Forwards Addendum to Unit 1 Preservice Insp (PSI) Summary Rept, Providing Remaining Info & Editorial Corrections Re PSI & Addressing Exams & Tests of Code Class 1 & 2 Sys as Stipulated in PSI Plan ML20058N2311990-08-0909 August 1990 Forwards First Half 1990 fitness-for-duty Program Performance Data,Per 10CFR26.71(d).Point of Contact for Personnel,Random Testing Program Results & Confirmed Positive Tests Summary & Mgt Summary Included in Data ML20059A5831990-08-0404 August 1990 Responds to Info Request Made During 900802 Meeting Re Inadvertent Safety Injections on 900726 & 30 & Results of 100% Power Plateau Testing TXX-9024, Provides Status of Exam Activity & Revised Completion Schedule for Portion of Exam.Util Deferred Preoperational Testing of Facility Spent Fuel Pool Cooling & Cleanup Sys Until Prior to First Off Loading of Spent Fuel1990-08-0303 August 1990 Provides Status of Exam Activity & Revised Completion Schedule for Portion of Exam.Util Deferred Preoperational Testing of Facility Spent Fuel Pool Cooling & Cleanup Sys Until Prior to First Off Loading of Spent Fuel TXX-9022, Forwards Detailed Descriptions of Changes in Amend 79 to FSAR for Comanche Peak Steam Electric Station1990-07-31031 July 1990 Forwards Detailed Descriptions of Changes in Amend 79 to FSAR for Comanche Peak Steam Electric Station TXX-9027, Responds to NRC Re Violations Noted in Insp Repts 50-445/90-19 & 50-446/90-19.Corrective Action:Specific Activity within Tech Spec Limits.No Further Corrective Action Required1990-07-30030 July 1990 Responds to NRC Re Violations Noted in Insp Repts 50-445/90-19 & 50-446/90-19.Corrective Action:Specific Activity within Tech Spec Limits.No Further Corrective Action Required ML20055J1571990-07-27027 July 1990 Submits Info Re Replacement of Borg-Warner/Intl Pump,Inc Check Valve Swing Arms,Per .Swing Arms in ASME Code Class 2 Check Valves Will Be Replaced During First Refueling Outage ML20056A0461990-07-24024 July 1990 Requests Regional Waiver of Compliance for Containment Pressure Transmitter 1-PT-934 During Coming Outage TXX-9023, Responds to NRC Bulletin 90-001, Loss of Fill-Oil in Transmitters Mfg by Rosemount. No Subj Transmitters in Existence at Facility1990-07-18018 July 1990 Responds to NRC Bulletin 90-001, Loss of Fill-Oil in Transmitters Mfg by Rosemount. No Subj Transmitters in Existence at Facility ML20055G6351990-07-17017 July 1990 Submits Results of Remote Shutdown Panel Environ Survey ML20055F9371990-07-13013 July 1990 Submits Info Re Revised Acceptance Criteria for THERMO-LAG Fire Barrier,Per 900705 Telcon.On Exposure to Heat Flux at Surface of Barrier,Listed Mechanisms Activated.Fire Testing Demonstrates That Panels Qualified W/Variation in Thickness ML20055F9391990-07-13013 July 1990 Advises That Operators Have Gained Significant Experience in Operating Plant Under Wide Range of Conditions & Have Demonstrated Necessary Proficiency to Safely Operate Unit ML20044A7001990-06-26026 June 1990 Responds to Generic Ltr 90-04, Request for Info on Status of Licensee Implementation of Generic Safety Issues Resolved W/Imposition of Requirements or Corrective Actions. Util Will Implement for Unit 2 Activities Performed for Unit 1 ML20044A1411990-06-20020 June 1990 Forwards Endorsements 4 & 5 to Nelia Certificate N-90, Endorsements 5 & 6 to Maelu Certificate M-90 & Endorsements 34,35,36,37,38 & 39 to Nelia Policy NF-274 ML20043H7031990-06-18018 June 1990 Discusses Mod/Rework to Auxiliary Feedwater Sys Check Valves Mfg by Bw/Ip Intl,Inc.All But One Affected Check Valve modified.Motor-driven Auxiliary Feedwater Pump Discharge Valve Check Valve Body Replaced ML20043G3131990-06-15015 June 1990 Forwards Addl Info Re Pressurizer Surge Line Thermal Stratification & leak-before-break Evaluation & Nonproprietary Suppl 3 to WCAP-12247, Supplementary Assessment... & Proprietary Suppl 3 to WCAP-12248 ML20043H2181990-06-15015 June 1990 Forwards Response to 900515 Request for Addl Info on Emergency Preparedness.Ongoing Emergency Preparedness Programs Address Concerns Raised by Citizens for Fair Util Regulation ML20043C5671990-06-0101 June 1990 Discusses Identification of Slave Relays Tested Using Alternative Methodology,Per 900402 Commitment.Encl Tabulation Identifies Test Type,Applicable Procedures & Equipment & Impact of Improper Documentation ML20043E7131990-06-0101 June 1990 Responds to NRC 900517 Notice of Violation & Imposition of Civil Penalty in Amount of $25,000.Corrective Action:Qc Mgt Counseled Level III Inspector & QC Supervisor on Importance of Good Communications W/Receipt Inspectors ML20043C4501990-05-31031 May 1990 Advises That Util Revised FSAR Section 15.1.2 & Question/ Response 32.108,per 10CFR50.59 ML20043B5471990-05-25025 May 1990 Provides Status of Facility Design & Const Activities,Per Request.Detailed Design Work Will Resume in June 1990.Const Activities Expected to Increase Signficantly by Jan 1991 ML20043B5481990-05-23023 May 1990 Provides Clarification of 890710 Commitment Re Power Ascension Program.Cooldown Portion of Remote Shutdown Test Performed During Preoperational Testing,Per FSAR & Reg Guide 1.68.2 TXX-9018, Advises of Completion of Implementation of Requirements of Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety- Related Equipment1990-05-21021 May 1990 Advises of Completion of Implementation of Requirements of Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety- Related Equipment ML20043D1711990-05-21021 May 1990 Forwards Public Version of Revised Emergency Plan Procedures,Including Rev 8 to EPP-109,Rev 7 to EPP-112,Rev 4 to EPP-116 & Rev 6 to EPP-121.W/DH Grimsley 900604 Release Memo ML20043B0981990-05-15015 May 1990 Forwards Radial Peaking Factor Limit Rept for Cycle 1, Containing F(Xy) Limits for All Core Planes Containing Bank D Control Rods & All Unrodded Core Planes ML20042F2851990-05-0303 May 1990 Supplemental Response to Generic Ltr 90-01, Request for Voluntary Participation in NRC Regulatory Impact Survey. ML20042F3861990-05-0303 May 1990 Responds to NRC 900410 Ltr Re Violations Noted in Insp Repts 50-445/90-10 & 50-446/90-10 on 900206-07 & 0226-0302. Corrective Action:Memo Issued Emphasizing That Discrepancies Should Be Brought to Attention of Site Organizations ML20042F3051990-05-0202 May 1990 Provides Revised Response to Generic Ltr 88-17 Re Loss of DHR ML20042F3021990-05-0202 May 1990 Responds to NRC 900402 Ltr Re Violations Noted in Insp Repts 50-445/89-23 & 50-446/89-23.Util Does Not Believe That Circumstances Described in 900402 Ltr Constitutes Violation of 10CFR50.9(a) ML20042E4581990-04-12012 April 1990 Responds to Inconsistencies in Terminology & Labelling Identified During NRC 890118 & 19 Audit of Facility Dcrdr. Util Believes Control Room Inventory Requirement of Suppl 1 to NUREG-0737,satisfied ML20042E0701990-04-10010 April 1990 Discusses 900305 Meeting W/Nrc in Rockville,Md Re Offsite Power Availability for Automatic Switch Co Solenoids for MSIV in Event of Nonmechanistic Main Steam Line Crack in Superpipe Region ML20012F5011990-04-0303 April 1990 Forwards Corrections to 891016 Response to Emergency Diesel Generator Engine Requirements.Lengths of Two Pairs of Bolts Above Crankpin Shall Be Measured Ultrasonically Before Detensioning & Disassembly of Bolts ML20012F3221990-04-0202 April 1990 Discusses ESF Sys Slave Relay Alternate Test Methodology. Implementation Schedule for Design Mods to Relay Will Be Submitted by 900601 ML20042D8081990-03-29029 March 1990 Forwards Proposed Change to FSAR Section 13.4 Re Station Operations Review Committee.Similar Change Submitted in 900328 Ltr for Chapter 6 of Facility Tech Specs ML20012F0411990-03-28028 March 1990 Forwards marked-up Pages of Facility Draft Tech Specs & Bases (NUREG-1381) Provided W/Low Power OL ML20012E6051990-03-27027 March 1990 Forwards Endorsements 1-4 to Maelu Certificate M-90, Endorsements 1-9 to Maelu Policy MF-131,Endorsements 29-33 to Nelia Policy NF-274 & Endorsements 1-3 to Nelia Certificate N-90 ML20012E6531990-03-27027 March 1990 Provides Final Response to Reporting Requirement 2 of NRC Bulletin 88-008, Thermal Stresses in Piping Connected to RCS, for Unit.Nde Requirements of Action 2 Not Considered Applicable to Unit ML20012E1911990-03-23023 March 1990 Forwards Comanche Peak Steam Electric Station Unit 1 Cycle 1 Startup Physics Tests Control Rod Worth Predictions Utilizing TU Electric Control Rod Swap Methodology. ML20012E1581990-03-23023 March 1990 Clarifies 880624 Response to NRC Generic Ltr 88-05, Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR Plants. ML20012D0151990-03-19019 March 1990 Responds to NRC 900216 Ltr Re Violation a Noted in Insp Repts 50-445/90-03 & 50-446/90-03.Corrective Actions: Groundwater Calculations Completed & Engineering Personnel Reminded of Procedural Requirements 1990-09-04
[Table view] |
Text
a Log # TXX-6398 H
File # 10010 Ref #10CFR50.30(a)
WELECTRIC April 15, 1987 wm c. co-ma mwae N hr.asent U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKETS NOS. 50-445 AND 50-446 REQUEST FOR ADDITIONAL INFORMATION - NUREG-0737, ITEM II.D.1 i PERFORMANCE TESTING OF RELIEF AND SAFETY VALVES l Gentlemen:
By letter dated March 27, 1987, the NRC staff requested additional information f regarding the TV Electric submittal of June 13, 1986, "NVREG-0737, Item II.D.1 -
Performance Testing of Relief and Safety Valves". ,
i j Attached is the information requested.
] Very truly yours, R/Al W. G. Counsil By: N, 6[
G. S. Keeley '-
Manager, Nuclear k ensing BSD/amb Attachment
, c - Mr. E. II. Johnson, Region IV ;
Mr. D. L. Kelley, RI - Region IV !
Mr.11. S. Phillips, RI - Region IV
\
i B704210075 870415 .
l PDR ADOCK 05000445 <
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n North Olne $ttret LR RI (Wlas. Teens 1.1.'01 l
Attachment to TXX-6398
, April 15, 1987 Page 1 of 23 QUESTION 1: Load Combination Ecuation l
In the load combination equation for the emergency service condition given on Page A-12 of Appendix A of Reference 1
[TU Electric letter TXX-4849 dated June 13,1986), the summation of the moment, MWt, due to deadweight, and the moment, MsoIE , due to safety valve discharge, is expressed as MSOTE + lMWtl.
Explain why the absolute value of the deadweight moment is used in this equation. This summation will produce unconservative results when both Ms0T Eand MWt have negative values.
4 RESPONSE 1: The computer program used for the stress evaluations automatically considers the absolute value of the respective moment from the thrust events including SOTE . Consequently, MsoIE is actually the absolute value of MsoIE and has been combined with the absolute value of MWt-
I Attachment to TXX-6398 April 15, 1987 Page 2 of 23 00ESTION 2: Pioina Stress Comnarison A. The piping stress comparison presented in Appendix A of Reference 1 (TV Electric letter TXX-4849 dated June 13, 1986] included the design, fatigue, and faulted condition stresses for the Class 1 (upstream) portion of the safety valve and PORV piping. The upset and emergency condition stresses were not provided. Table A-5 in the above reference showed that the faulted condition stresses were low enough to fall below the emergency condition stress limits. However, it is difficult to draw the same conclusion for the upset condition, since not all of the i stresses listed in Table A-5 are below the upset condition stress limit. The Licensee should provide a stress comparison for the upset condition to demonstrate that the PORY piping stresses are within allowable limits.
B. Reference 1 did not include a stress comparison for the downstream piping. Provide a comparison of the normal, upset, emergency, and faulted condition stresses and the applicable stress limits for the downstream piping in a similar manner as those for Class 1 piping.
C. Provide sketches of the upstream and downstream piping indicating the locations of the structural nodes used in the !
stress comparisons. ,
RESPONSE 2:
The loadings for the design condition listed in Table A 4 are for the combination P + DWT + SRSS (OBE, 50TV ). Therefore, the normal and upset conditions are automatically covered by the design data in Table A 4 and the emergency and faulted conditions are automatically covered by the faulted data in Table A 5 of the reference.
Attachment to TXX-6398 April 15, 1987 Page 3 of 23 RESPONSE 2: Since the transmittal and review of the reference data, the line (cont'd) has been reanalyzed to reflect pipe support changes. A comparison of the normal, upset, emergency and faulted condition stresses and the applicable stress limits for both the upstream and downstream piping is presented in the attached Tables 2-1 through 2-9 for the revised analysis. Figures A-1 and A 2 illustrate the structural node points and support locations.
. Attachment to TXX-6398 April 15, 1987 Page 4 of 23 OVESTION 3: Pipino Supoort Loads A. The piping support evaluation was performed in accordance with the ASME Boiler and Pressure Vessel Code, Section Ill, Subsection NF. The stress limits listed in Tables A-1 and A-2 (Reference 1) [TU Electric letter TXX-4849 dated June 13,1986) for load combinations for normal, upset, emergency, and faulted conditions appear to be oriented toward pipe stresses only, and not pipo support stresses.
The allowables for the supports would be expected to be multiples of Subsection NF stress limits. Therefore, clarify the stress limits used for the supports for all load combinations. Also, identify the stress limits used for standard components such as snubbers.
B. Present a table comparing the worst caso load (or stress) in several representativo supports with the applicablo allowable load (or stress) and identify the associated load combination equation. Also indicato in the table the support number and support type. If the support numbrr':
l usedinthetablearenotshowninthepipingsketche,lin Figures A 8 through A-13 in Reference 1, provido addstional sketches to identify the support locations.
RI.SPONSE 3: Regarding item 3A, the load combinations and stress allowables for the ASME Code Class 1, 2, and 3 pipo supports are in conformance with Subsection NF of the ASME Section !!! Codo.
This includes standard component supports. Those allowables are tabulated in FSAR Tables 3.90 10, 3.9B 10, and 3.90 lE.
For Item 30, the worst case load / stress versus the allowables for representative pipo supports in Figures A 8 through A 13 are tabulated in Tables 3 1 through 3 6, respectively. Tablo 3 7 contains a similar comparison for small bore pipo supports within the stress problem boundary but not shown in the piping :
sketches in figures A 8 through A 13 of Referenco 1.
l
Attachment to TXX-6398 April 15, 1987 Page 5 of 23 OVESTI0ff 4: Provide a description of the pipe material for the Class 1
, piping upstream of the valves.
1 RESPONSE 4: The Class 1 piping, por the as built data, is either ASME SA 376 TP304 or TP316 stainless steel. Ilowever, the lower allowable stress values for TP304 are used in the stress analysis.
l I
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Attachment to TXX-6398
. April 15, 1987 Page 6 of 23 Table 2-1 CLASS 1 (UPSTREAM) PRIMARY STRESS
SUMMARY
NORMAL CONDITION COMBINATION: P + DWT Maximum Allowable Stross Node Piping Equation #9 1.5 Sm Point Comoonent Stress (ksi) (ksi) 3 3020 Butt Wold 10.064 24.225 3041 Long Radius Elbow 12.123 24.225 5000 Branch Connection 15.844 24.225 3030 CRUN 9.905 24.225 4332 5 0 Bond 5.384 24.225 4170 Roducer 12.867 24.225 4
i 1
D
, Attachment to TXX-6398 April 15, 1987 Pago 7 of 23 Table 2-2 CLASS 1 (UPSTREAM) PRIMARY STRESS
SUMMARY
UPSET CONDITION COMBINATION: P + DWT + SRSS (OBE. 50TV1 Maximum Allowable Stross Node Piping Equation #9 o y Point Comoonent Stress (ksi) (1.8 Smksi) (r 1.5 S )*
4480 Butt Wold 15.704 26.850 1031 Long Radius Elbow 17.089 26.850 5000 Branch Connection 26.466 26.850 4481 CRUN 15.704 26.850 4332 5 0 Bond 13.625 26.850 4170 Roducer 19.561 26.850
- The smaller of the given allowablo is to be used.
, Attachment to TXX-6398 April 15, 1987 Page 8 of 23 Table 2-3 CLASS 1 (UPSTREAM) PRIMARY STRESS
SUMMARY
EMERGENCY CONDITION COMBINATION: P + DWT + S0TE Maximum Allowable Stress Nodo Piping Equation #9 o y Point Comoonent Stress (ksi) (2.25Sm(r1.8S)*
ksi) 3161 Butt Wold 16.846 32.220 3152 Long Radius Elbow 23.471 32.220 3160 Branch Connection 31.104 32.220 3152 CRUN 16.846 32.220 4332 5 0 Bond 7.885 32.220 4170 Roducer 13.730 32.220
- The smaller of the glvon allowable is to be used.
. Attachment to TXX 6398
+
April 15, 1987 Pag] 9 of 23 Table 2 4 CLASS 1 (UPSTREAM) PRIMARY STRESS
SUMMARY
FAULTED CONDITION COMBINATION: P + DWT + SRSS (SSE. 50TF 1 Maximum Allowable Stress Node Piping Equation #9 3.0 Sm Point Comoonent Stress (ksi) (ksil i
5170 Butt Wold 21.021 48.450 1031 Long Radius Elbow 26.075 48.450 5000 Branch Connection 40.223 48.450 5171 CRUN 21.016 48.450 4332 5 0 Dend 17,868 48.450 4170 Reducer 22.982 48.450 1
4 4
1
. Attachment to TXX-6398 April 15, 1987 Page 10 of 23 Table 2-5 CLASS NNS (DOWNSTREAM) PRIMARY STRESS
SUMMARY
NORMAL CONDITION COMBINATION: P + DWT Maximum Allowable Stress Node Piping Equation #9 1.0 S Point Component Stress iksi) (ksi)h 3302 Butt Wold 6.794 15.900 3311 Long Radius Elbow 7.641 15.900 2440 Branch Connection 5.206 15.9tJO 2430 CRUN 6.081 15.900 l
l l
r
. Attachment to TXX-6398 April 15, 1987 Pag] 11 of 23 Table 2-6 CLASS NNS (DOWNSTREAM) PRIMARY STRESS
SUMMARY
UPSET CONDITION COMBINATION: P + DWT + SOTu Maximum Allowable Stress Node Piping Equation #9 1.2 Sh Point Comoonent Stress (ksi) (ksil 3302 Outt Wold 6.989 19.080 3311 Long Radius Elbow 7.888 19.080 2440 Dranch Connection 5.703 19.080 2430 CRUN 7.099 19.080
. Attachment to TXX-6398 April 15, 1987 Page 12 cf 23 Table 2-7 CLASS NNS (DOWNSTREAM) PRIMARY STRESS
SUMMARY
UPSET CONDITION COMBINATION: P + DWT + SRSS (0BE. S0T U I Haximum Allowable Stress Node Piping Equation #9 1.8 Sh Point Component Stress (ksi) (ksil 4531 Butt Wold 14.070 28.620 3311 Long Radius Elbow 11.965 28.620 3450 Branch Connection 10.871 28.620 2430 CRUN 13.414 28.620 l
l l
l
Attachment to TXX-6398 April 15, 1987 Page 13 of 23 Table 2-8 CLASS NNS (DOWNSTREAM) PRIMARY STRESS
SUMMARY
EMERGENCY CONDITION COMBINATION: P + DWT + S0TE Maximum Allowable Stress Node Piping Equation #9 1.8 Sh Point Comoonent Stress (ksi) (ksil 3360 Butt Weld 17.421 28.620 3322 Long Radius Elbow 18.386 28.620 1430 Branch Connection 10.860 28.620 1420 CRUN 18.629 22 620 l
l l
l
-Attachment to TXX-6398
.- April 15, 1987 Page 14 of 23 Table 2-9 CLASS NNS (DOWNSTREAM) PRIMARY STRESS
SUMMARY
FAULTED CONDITION COMBINATION: P + DWT + SRSS (SSE. SOTF 1 Maximum Allowable Stress Node Piping Equation #9 2.4 S Point Component Stress (ksi) (ksi)h 4531 Butt Weld 19.288 38.160 1311 Long Radius Elbow 20.838 38.160 3450 Branch Connection 14.571 38.160 1420 CRUN 22.400 38.160
Attachment to TXX-6398 -
April 15, 1987 Page 15 of 23 TABLE 3-1 Tabulation of Worst-Case Stress vs. Allowable Stress Representative Supports from Figure A-8 Worst Standard Component Worst Stressed (Strut or Snubber) Structural Component Support No. Support Tvoe Actual Load Allowable load L.C.** Tvoe* Actual Allowable L.C.**
RC-1-Il5-015-C76R Parallel struts 52475 lbs 75900 lbs (clamp) F 2 18,189 psi 19,600 psi F attached to frame 3 Interaction 1.0 F 0.76 1 Interaction 1.0 F 0.565 RC-1-ll5-008-C76K Snubber attached 2346 lbs 22100 lbs F 5 0.5" 0.39" F (1) to frame Thick plate Thick plate 4 Interaction 1.0 F 0.57 OStructural Component Tvoes: ** Load Combination Case: (1) Analysis based on allowable stress requires plate thick-1 - Support Member F - Faulted ness of 0.39"; actual plate 2 - Weld E - Emergency thickness is 0.50".
3 - Base Plate / Anchor Bolt U - Upset 4 - Richmond Insert / Threaded Rod 5 - Other: Load-Carrying End Plate
Attachment to TXX-6398 April 15, 1987 Page 16 of 23
~
TABLE 3-2 Tabulation of Worst-Case Stress vs. Allowable Stress' ,
Representative Supports from Figure A-9 Worst Standard Component Worst Stressed (Strut or Snubber) Structural Component Sucoort No. Support Tvoe Actual Load Allowable load L.C.** Tvoe* Actual Allowable L.C.**
RC-1-Il5-019-C66K Snubber attached 20121 lbs 67200 lbs E 3 Interaction 1.0 F to frame 0.89 20466 lbs 72450 lbs F 1 Interaction 1.0 F 0.77 RC-1-Il5-020-C66R Rigid frame --- --- --
2 14,899 psi 17,864 psi F 3 Interaction 1.0 F 0.84 RC-1-ll5-023-C66R Rigid frame --- --- --
2 Interaction 1.0 F 0.76 1 Interaction 1.0 F 0.56 RC-1-ll5-029-C56K Snubber attached 8226 lbs 72450 lbs F 2 0.25" 0.221" F (1) l to frame l 4 Interaction 1.0 F l 0.66 OStructural Component Types: ** Load Combination Case:
1 - Support Member F - Faulted (1) Analysis based on allowable 2 - Weld E - Emergency stress requires weld size of 3 - Base Plate / Anchor Bolt U - Upset 0.221"; actual weld size is 4 - Richmond Insert / Threaded Rod 0.25".
5 - Other:
Attachment to TXX-6398
- April 15, 1987 Page 17 of 23 TABLE 3-3 Tabulation of Worst-Case Stress vs. Allowable Stress Representative Sampling for Supports on Figure A-10 Worst Standard _ Component Worst Stressed (Strut or Snubber) Structural Component Support No. Support Tvoe Kctual Load Allowable load L.C.** Tvoe* Actual Allowable L.C.**
RC-1-097-002-C86K Snubber attached 8488 lbs # s 72450 lbs F 3 Interaction 1.0 F j to frame -
, O.54
- 3 12485 psi 26250 psi F i
i OStructural Component Tvoes: ** Load Combination Case:
1 - Support Member F - Faulted 2 - Weld E - Emergency 3 - Base Plate / Anchor Bolt U - Upset 4 - Richmond Insert / Threaded Rod 5 - Other:
Attachment to TXX-6398 April 15, 1987 Page 18 of 23 TABLE 3-4 Tabulation of Worst-Case Stress vs. Allowable Stress Representative Supports from Figure A-11 Worst Standard Component Worst Stressed (Strut or Snubber) Structural Component Support No. Support Tvoe Actual Load Allowable Load L.C.** Type
RC-1-099-002-C86K Snubber attached 7915 lbs 22100 lbs F 4 Interaction 1.0 F to frame 0.83 2 14,005 psi 17,864 psi F OStructural Component Tvoes: ** Load Combination Case:
1 - Support Member F - Faulted 2 - Weld E - Emergency 3 - Base Plate / Anchor Bolt U - Upset 4 - Richmond Insert / Threaded Rod 5 - Other:
. Attachment to TXX-6398
- 2 April 15, 1987 Page 19 of 23
, TABLE 3-5 Tabulativa of Worst-Case Stress vs. Allowable Stress Representative Supports from. Figure A-12 Worst Standard Component Worst Stressed
- (Strut or Snubber) Structural Component
- Support No. Support Tvoe Actual Load Allowable Load L.C.** Tvoe* Actual Allowable L.C.**
RC-1-101-002-C86K Snubber attached 3452 lbs 10640 lbs F 5 13,125 psi 26,250 psi F to base plate 3 Interaction 1.0 F 0.12 1
i i
OStructural Component Tvoes: ** Load Combination Case:
1 - Support Member F - Faulted 4 2 - Weld E - Emergency 3 - Base Plate / Anchor Bolt U - Upset 4 - Richmond Insert / Threaded Rod 5 - Other:
Attachment to TXX-6398 April 15, 1987 Page 20 of 23 TABLE 3-6 Tabulation of Worst-Case Stress vs. Allowable Stress Representative Sampling for Supports on Figure A-13 Worst Standard Component Worst Stressed (Strut or Snubber) Structural Comoonent Support No. Support Tvoe Actual Load Allowable load L.C.** Tvoe* Actual Allowable L.C.**
RC-1-110-001-C86K Snubber attached 3226 lbs 6000 lbs U 3 Interaction 1.0 F to base plate 0.43 4612 lbs 9400 lbs F 3 9,769 psi 23,925 psi F RC-1-ll2-003-C86K Snubber attached 2147 lbs 6000 lbs U 3 Interaction 1. 0 . F to base plate 0.25 3339 lbs 9400 lbs F 2 1,371 psi 20,365 psi F oStructural ComDonent Tvoes: ** Load Combination Case:
1 - Support Member F - Faulted 2 - Weld E - Emergency 3 - Base Plate / Anchor Bolt U - Upset 4 - Richmond Insert / Threaded Rod 5 - Other:
Attachment to TXX-6398 April 15, 1987 Page 21 of 23 TABLE 3-7 Tabulation of Worst-Case Stress vs. Allowable Stress Representative Sampling for Supports on Small Bore Iso RC-1-RB-019 Worst Standard Component Worst Stressed (Strut or Snubber) Structural Component Support No. Support TYDe Actual Load Allowable load L.C.** TVDe* Actual Allowable L.C.**
RC-1-103-700-C75K Snubber attached 39 lbs 267 lbs F --- --- --- ---
to frame RC-1-103-702-C75R Rigid frame --- --- ---
3 1,528 psi 27,000 psi F 2 2,763 psi 17,864 psi F RC-1-103-705-C75R Snubber attached 84 lbs 510 lbs F 3 1,514 psi 27,000 psi F to base plate OStructural Component Tvoes: ** Load Combination Case:
1 - Support Member F - Faulted 2 - Weld E - Emergency 3 - Base Plate / Anchor Bolt U - Upset 4 - Richmond Insert / Threaded Rod 5 - Other:
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