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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] |
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o
- Log # TXX-6145 File # 10010 TEXAS UTILITIES GENERATING COMPANY M KYWAY TE DWEN
- 4470 NHHTil E SLIVE MTHEE T, L.fl. Mt
- IDALLAM, TEXAM 73201 April 6, 1984
+
Mr. B. J. Youngblood Chief Licensing Branch No. 1 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D.C. 20555
SUBJECT:
TUGC0 COMMENTS ON CY2..\'s INDEPENDENT ASSESSMENT PROGRAM
Reference:
Schmidt (TtGCO) to foungblood (NRC) letter TXX-4134, dated April 2, 1984
Dear Mr. Youngblood:
Atta_hed are TUGCO's comments on CYGNA's Independent Assessment Program as requested by you. Some comments that were made directly relate to concerns previously addressed in the above referenced letter.
If there are any further questions of clarifications requested regarding the CYGNA report or these comments, please contact us.
Very truly yours, d
f H. C. Schmidt o
HCS:kp Attachment (s)-
c - Ms. Nancy Williams, CYGNA Mr. Nicholas.S. Reynolds h-
@N.5 W6 8404160060 840406 3
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- x. . A .. & , . . _ - ..PDR . , ;
L A CEV10 EON 09* TEEA8 UTELETIER E1 ECTRIC COA *E*ANY
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Page 1
~
LTUGC0 REVIEW.0F CYGNA'S INDEPENDENT ASSESSMENT PROGRAM
. u.' 1 Volume /Section/
Item Page Cygna Statement TUGC0 Comments
,.- :10 LVolume 1J End~ connections consisting of angles anchored to End connections of angles anchored to f HCTS-00-031 . concrete by either one or <two bolts were modeled concrete by one or two bolts is modeled as Page 8 af 13: as hinges'in the cableitray support frame a hinge connection in the cable tray support
- (b). analysis. The assumption of a fixed joint is frame analysis. Cygna suggests that a fixed more appropriate considering the rigidity of the joint is more appropriate considering the base angle connection. rigidity of the base angle connection.
s Texas Utilities suggests that this '
difference of opinion is a matter of engineering judgement, that the modeling
' technique used is justifiable and that the des"gn compensates for the differences in
' the boundary conditions of the connections (i.e., tension, shear, prying action, etc.)
- 2. 'Section!1' f0f the six conduits checked, one instance was Editorial, C-03015123-2 should be read
.Page 13/13 found where the Cable and Raceway Schedule C-03015123.
. identified the conduit :between Spent Fuel
. Cooling Panel XLV-06 and T130FCZ33 as
'C-03015123-2. The installation and. routing drawing identified this as Conduit No.
-C-13015123.
3.- Page~3-10 Check electrical isolation between safety and Editorial, currer.ts should read circuits, non-safety currents.
- 4.1 . Exhibit 3.1. This is'a reportable finding to CG&E under Editorial, CG&E should read CPSES.
requirements of 10CFR Part 21. ~
- 15. : Vol ume' I t. Cygna does suggest that the anchor bolt Embedment depth question was discussed in Page 4-10 enbedment. lengths be removed from the support letter to NRC, TXX-4134 (Homer Schmidt to
. drawings during the next revision. B. J. Youngblood.
Page 2
.TUGC0 P: VIEW 0F CYGNA'S INDEPENDENT ASSESSMENT PROGRAM Volume /Section/
Item ^ Page Cygna Statement TUGC0 Comments 6.- Page 4-12 .There was no clear assurance, however, that Cygna states "there was no clear assurance, sufficient margins existed for all the other however that sufficient margins existed for support design within the plant. all other support designs within the plant."
Although the topic of the above discus; ion is the cable tray supports, it is not clear that this sentence is referring to other cable tray supports in the plant or other types of supports. A clarification is required.
- 17. Page.4-15 ... routing of the 3-1/C-753 MCM w2s verified Cable denoted 3-1/C-750 MCM should read up... "(3) 1/C 750 MCM Cable."
- 8. Page 4-16 Editorial T120/FBU12 should read T120FBU12 T120/FBU11 should read T120FBUll 3-1/C-750MCM should read (3) J/C 750 MCM C130FCZ33 should read C-13015123 C-030/15123-Z should read C-13015123 C-130/15123 should read C-13015123
- 9. -Page 4-17 It was further noted that cable E0/018815 is (1) Editorial E0/018815 should read E0018815 listed as being deleted in the Unit 1 cable schedule issue 308. .The cable is terminated (2) Motor Control Center designated as at the Unit 2 B0P Auxiliary Relay Rack 4 in EPS-EPMD B-3 is not a correct number, accordance with connection drawing E2-0158. It should be CP::-EPMCEB-03. This can bc The. termination of the cable at Motor verified by reviewing the terininal block
< Center EPS-EPMDEB-3 was verified. diaaram E-2-0158 and drawing El-0071 sheets 14 and 24.
(3) Editorial, C-13015123 should read C-03015123.
f, , ,.
, Page 3'
~
iTUGC0 REVIEW 0F.CYGNA'S INDEPENDENT. ASSESSMENT FROGRAM
' Volume /Section/:
~ Item.
2
- Page' '
- Cygna Statement 'TUGC0 Comments
- 10. . :- Vol ume' 11 List of drawings reviewed for-Spent Fuel Pool "Page" used in this reference is actually a Section C .. LCooling System -(Train A)' sheet number and'sume page numbers do not PageJ7 of.;11 apply for some electrical drawings.
11.'- ' Appendix E- ' When compared to the pipe support as-built The tolerances provided by Design
- s. -Page 8 . configuration, these. locations should be within Specification 2323-MS-46A, Revision 3,
- DC-l' ' the' tolerances of Project Design Specification Section 3.6.2.1.1 are for original support 3323-MS-46A. Section 3.6.2.1.1., i.e., design. The tolerances provided in Revision 3 of. the specification are co.npatible with
, the tolerances provided in construction 1 procedures CP-CPM-9.10. The' tolerances provided in MS-46A and CP-CPM-9.10 are
+
bounded by the tolerances provided in the
'As-Built' verification program procedure CP-EI-4.5-1.
- 12. Page 11-14' Editorial 1/2 SSE should read OBE.
DC ! 13.- -Page 4-11= ASME Boiler and Pressure Vessel Code Section III, ASME B&P Vessel Code Section III, Subsection DC -Sub-section NF,:1977 edition.
NF, 1977 Edition is not the code that was committed to for CPSES. The code is the 74 The-stiffness 'of a pipe support in the pipe's Edition through and including the Winter restrained-direction must meet the required Addenda, 74.
, stiffness'shown in'Exhioit 4.1-l'according to i- the nominal . size of restrained pipe. Cygna states that the " stiffness of a pipe
, support must meet the required stiffness P shown..." It is Texas Utilities practice that the actual 'as built' stiffness for Class 1 piping system supports are P
.r v
Pags 4.
~
TUGC0 REVIEW OF CYGNA'S INDEPENDENT ASSESSMENT PROGRAM Volume /Section/-
Item- Page Cygna Statement TUGC0 Comments calculated and provided for the 'as built' analysis. Other non-Class 1 systems do not require this stiffness to conform to the the indicated stiffness values. These values are used by the piping analyst as generic stiffness input into the pipe stress analysis model. Deflection calculations are used as the design guideline for pipe supports. It is requested that Cygna either clarify this statement or identify the industry standard, specification, or guideline on which it is based.
- 14. Page 5-11 The maximum total gap allowed in the restrained Gaps provided for restraints are installed DC-2 direction is 1/8". In unrestrained directions, with the tolerances provided in the (4.1.2) the support design shall allow clearance for construction procedure CP-CPM 9.10, Section the most severe thermal plus seismic movements 3.3.1.2. The maximum total diametrical gap of the pipe.- normally allo.ied is 3/16", not 1/8" as indicated.
- 15. Page.5-ll Deviations See Item 11 above.
.DC-2 (4.1.3)
- 16. Page 6-11 The spring's available travel will be checked Spring supports are not checked against both DC-2 against all the thermal and seismic movements. thennal and seismic movement, aq1y thermal.
All piping supports are designed to be essentially rigid. Seismic motion is considered neglible.
Paga.5-TUGC0 REVIEW 0F CYGNA'S INDEPENDENT. ASSESSMENT PROGRAM Volume /Section/ TUGC0 Comments Item Page- Cygna Statement The midpoint of thermal travel for snubber The' snubber cold and hot normal operating 17.- -Page 6-11 setting is provided on drawings. However, DC . strokes shall be set at the midpoint of the (4.1.6) total travel with . hot and cold settings some snubbers are set near their limits due established accordingly.- to space limitations. A snubber is set with at least a 1/4" margin provided within the snubber stroke after worst case thermal conditions are considered.
- 18. Page 7-11. All seismic supports shall be plus and minus Cygna states that seismic restraints shall restraints. Regardless of other imposed loads, be in each direction along the restraining DC-2 (4.1.10)
.the pipe must be physically restrained in each axis. However, uni-directional supports can direction along the. restraining axis. be used if the dead weight of the unrestrained load is considered as its own restraint.
Friction loads (FL) are to be applied in the The friction load is considered the product
- 19. Page 8-11.
DC-2 direction of thermal movement. Its magnitude of a friction factor and the sum of the dead shall-be the friction coefficient times the and thermal loads. The friction load can, (4.2) at times, be less than the pipe's dead load, algebraic sum of the pipe's dead load and the normal thermal load but shall not be less than A clarification or basis of Cygna's comments should be provided. PSE and ITTG only the pipe's dead load.
consider friction loads if thermal movement is greater than 1/16".
Page 9-11 Editorial Type, E705 should read E70S.
20.
DC-2 (4.4)
- 21. Page 9-11' Concrete expansion anchors should not be used Expansion anchors are not used indiscrim-indiscriminately. inately. The preferred methods are embedded DC-2 plates, bolts or Richmond inserts. However, (4.5.1)
i Page 6
' TUGC0 REVIEW 0F CYGNA'S . INDEPENDENT ASSESSMENT PROGRAM Volume /Section/
Item Page- Cygna Statement TUGC0 Comments many of the pipe supports use expansion anchor bolts in their design. This is due to construction and design requirements.
- 22. . Page 5-8. Editorial 1/2 SSE should read OBE.
DC-3
'(4.2).
'23. Appendix F' Centralization of existing document distribution (2.0a) Six satellites are being fonned, not Obs.~ Record Rev. points (file custodians) into eight remote the eight indicated.
DC-01-01. - Document Control Center (DCC) Satellite" stations.
24.. PI-02 The. tolerance for support design location is + 1 Specification 2323-MS-46A, Rev. 3, Paragraph Page 1 of 1 pipe. diameter per Gibbs & Hill Specification 3.6.2.1.1 is not applicable to the 2323-MS-46A, Rev. 3, Paragraph 3.6.2.1.1. 'as built' analy?.is. Tolerances for as-built conditions are provided in procedure CP-CPM 4.5.1.
- 25. WC 03 Of the six conduits checked, one instance was C-03015123-2 should read C-03015123 Page-1 of-2 -found where the Cable and Raceway Schedule C-13015123 should read C-13015123 identified the conduit between Spent Fuel The first (3) number indicate unit, voltage Cooling Panel XLV-06 and T130FCZ33 as and function only.
C-13015123. The installation and routing drawing identified this as conduit number C-13015123.
The conduit identification number consists of the last five digits (i.e., 15123). This
. number is consistent with the reference documents and the installation. The first
s
- Page 7 TUGC0 REVIEW 0F CYGNA'S INDEPENDENT ASSESSMENT PROGRAM Volume /Section/.
Item- Page Cygna Statement TUGC0 Comments three numbers indicate unit, function, and voltage only. Since. the only discrepancy is the unit. number,'there is no safety impact.
26 . PS-02/03 - See Item 5 above. Embedment length concern addressed in NRC Att. A letter. Embedment lengths on drawing are used during installation and QC inspection.
.e
- 27. F5-09 - The working range for spring hanger SI-1-042- Incorrect support number is provided, the 002-S22K (i.e., top up or bottom out) was number may be SI-1-079-001-S22. Displace-not checked to ensure that the travel due to ment due to seismic motion is not included seismic movement was within the working range in any site specific guidelines due to the of the hanger, rigidity of the piping systems. In addition, the spring is designed within its working range and springs have enough travel outside the working range to account for any seismic motion.
- 28. PS-10 The design input data for support RH-1-064- The design input data for support RH-1-064-010-522R contained an. error in the X 010-S22S contains no values for an X displacement sign (+ .395" vs. 395"). This displacement of + or - 0.395". This seers error appears on the form transmitted from seems to be an incorrect support drawing
- the pipe stress group to the pipe support drawing number.
_ group for the use in the design.
- 29. Volume 2 Does FSEG maintain a log for each drawing that The scope of procedure CP-El-4.04 is limited Appendix H shows any deviations for that drawing? to conduit support design drawings, DC-01-01 Comments: 2323-S-910 Series. Prior to January, 1984, Page_6 of 8 FSEG kept logs of deviations for conduit
.(Item 25) 1. Per procedure for internal documents. support drawings (S-910). Subsequently this responsibility has been transferred to DCC
p r~
Page 8 TUGC0 REVIEW 0F?CYGNA'S INDEPENDENT ASSESSMENT PROGRAM
. Volume /Section/
Item Page- Cygna' Statenent TUGC0 Comments
- 2. ' Logs for older drawings received from DCC as indicated in Section 2.2.2 of procedure
. are not completely up-to-date when compared CP-EI-4.0.4. .Cygna suggests that older logs
-with DCC. received from DCC are not up-to-date. For conduit supports, older logs were not kept
- 3. See Attachment 7 for the change matrix. by DCC. In addition, the attachment does not refer to S-910 drawings. Further clari-fication is required by Cygna to determine if they are only considering conduit supports or have included cable tray supports in this review. The cable tray support documents including logs of deviations have always been maintained and controlled by DCC.
'3).- 0C-01-01L ;Is a ..los maintained indicating all outstanding Procedure CP-El-4.0-22 is the procedure used Page 6 o6'8 design changes against BRPs?_ by the Technical Services Mechanical Item 36- Drafting (TSMD) for design and drawing Per procedure for sample reviewed. control. Specifically, Section 3.3 requires TSMD to maintain a log of outstanding design changes against drawings they issue. The TSMD group maintains this log. DCC maintains a similar log that does not specifically implement this procedure, but is used as their control of document changes and drawings. Item 36 implies that the logging system .or procedure CP-El-4.0-22 is unsatisfactory, but the comments sections does not not clarify any reasons. In fact, the comments state "per procedure for sample received." Texas Utilities feels that there is an inconsistency in Cygna's remarks, and
, ' ' t ';
p- ~
Paga'9 .
TUGCO. REVIEW OFLCYGNA'S INDEPENDENT ASSESSMENT PROGRAM.
- l. ..
- Volume /Section'/'
Cygna Statement
!. Item Page TUGC0 Comments i I t
' 1
'furthermore, we feel that the TSMD group correctly implements their procedure and !
logging system.
- 31. :DC-01 ' Change Distribution Matrix Some of the observations by Cygna regarding
- AttachmentL7 the DCTG log are incorrect due to updating.
However, due to the periodic revising and- .t
,4 updating of the DCTG log specific comments
- s. .
will not be provided in this report. ;
321 - DC-01-03 .The Design' Change Tracking Group (DCTG) is Item I st;stes that DCTG is established to i-
- : Page 1-7 . established to approve design changes, approve design changes is incarrect. The ;
DCTG is solely an admiristrative group Item 1
~
responsible to control the design change
- cycle. The appropriate engineering department (originating engineer) actually approves and reviews design changes.
- 33.- PS-01 No check on stiffness was provided in the Stiffness is required to be checked for
-IDRL 1 support. calculation.- See Note 2 on attachment pipe supports on Class 1 stress problems i Page 3-4 to this checklist.. only. Cygna should provide a basis for
- Item II their comments.
l 34. PS Comments,1 through.4 regarding embedment See letter to the NRC, TXX-4134.
- Page 1-4 : lengths-for Hilti bolts.
Item 1
'35. PS-07 :.The base plate'. input torsional load (Mx) should This is considerea an isolated error and '
should be indicated as such in the comments.
~
l Page 3-4 be 52824-in-lb but.28848.in-1b was used in -
Item 10- . design calculation. -Since this load only ;
2 E
I ~
Page 10 ,.
i l
'TUGC0 REVIEW OF'CYGNA'S INDEPENDENT ASSESSMENT PROGRAM l Volume /Section/
. . Item Page Cygna Statement TUGC0 Comments i . induces shear in the anchor bolt, the .effect of this error is minor because a doubling of the
. bolt shear stress does not impact the bolt qualification.
.36. 'PS-09 Seismic movement not considered in the spring . Seismic movement is not considered in spring
'Page 2-4' . design calculation. design calculations because of its Item 6 negligible design impact.
37.. PS-10 See Item 28 above. Itsn requires transmittal number or correct
-Page 1-4 hanger drawing number.
Item I
- 38. PS Bill of materials Item No. 6 is the base plate. FUB II locates attachments with respect to Page 3-4. It was analyzed using the Grinnell program. the bolt holes not with respect to the plate Item 10 FUB II centers-the attachment on the plate. In edges. This is illustrated by the FUB II
- the actual design it is offset 1" towards bolts Data Input Preparation Form. 3 and 4. This
.will not af fect- the design since the bolt allowable . interaction ratios are sufficiently low.
- 39. PS-30 SA-193-87 rods were used to replace normal Hilti SA-193-B7 rods were used. They were not Page.3-4 bolts, and are acceptable. " replacements" for Hilti bolts. By design, Item 10 thru-bolts of SA-193-87 material were used due to an anticipated high load.
40 .IDR- Editorial 6.0KV should read 6.9KV.
Checklist
- EE-01 t Page 11-13.-
i
fl p- 'Paga 11 TUGC0 REVIEN OF CYGNA'S INDEPENDENT ASSESSMENT PROGRAM P .
- Volume /Section/ .
Item Page Cygna Statement TUGC0 Comments
- 41. IDR Defines requirement that valve 1-88118 be See letter to the NRC, TXX-4134.
Checklist --interlocked to prevent opening until pressure EE-02.(#1) .to 425-psig.
- 42. P1-02 Editorial 1/2 SSE Spectra should read OBE.
Page 2-10 Item 5 T43 - WD-07' Editorial C-020/11928 should read C-02011928
Page 4-6
- 'As-Built' l
i
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t ,