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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 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 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 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 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 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 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 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 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 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 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 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) ML20042F3051990-05-0202 May 1990 Provides Revised Response to Generic Ltr 88-17 Re Loss of DHR 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. ML20012D0201990-03-19019 March 1990 Advises That Allegations Provided to NRC by Former Util Employee Unsubstantiated,Based on Investigation by Util Safeteam Organization ML20012E2181990-03-19019 March 1990 Responds to Generic Ltr 89-19 Re USI A-47, Safety Implication of Control Sys in LWR Nuclear Power Plants. Util Determined That Loss of safety-related Inverters 1 or 2 Would Involve Coincidental Opening of Main Feedwater Valves 1990-09-04
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Log # TXX-6306 File #10130
. .-- IR 86-07
= = 86-05 IllELECTRIC
,, g. March 6, 1987 Lnecunw ike hesidmo U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 i
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 SUPPLEMENTAL ~ RESPONSE TO INSPECTION REPORT 50-445/86-07 AND 50-446/86-05 REF: TXX-6222, dated February 18, 1987 Gentlemen:
In the referenced letter we stated that responses to Notice of Violation Items B (445/8607-V-02), C (445/8607-V-21), D (445/8607-V-20), E (445/86-07-V-22),
F (445/8607-V-04), and Notice of Deviation Item I.5 (445/8607-D-13) would be provided by March 6, 1987. The attachment to this letter provides these responses.
Very truly yours, W. G. Counsil JCH/ef i
Attachment c - Mr. E. H. Johnson, Region IV Mr. D. L. Kelley - RI, Region IV Mr. H. S. Phillips - RI, Region IV i
3 p PD G L 400 North Olise Street I..it 81 Dallas. Texas 75201
f Attachment.to TXX-6306 March 6, 1987 Page 1 of 13 NOTICE OF VIOLATION ITEM B (445/8607-V-02)
B. Criterion III of Appendix B to 10 CFR Part 50, as implemented by Section 3.0, Revision 4, dated November 20, 1985, of the TUGCo QAP, states, in part, " Measures shall be established to assure that applicable regulatory requirements and the design basis. . . are correctly translated into specifications, drawings, procedures, and instructions. . . . The design control measures shall provide for verifying or checking the adequacy of design, such as. . . by the use of alternate or simplified calculational methods . . . . The design control measures shall be applied to items such as . . . delineation of acceptance criteria."
Contrary to the above, on September 25, 1985, TUGCo Nuclear Engineering (TNE), in response to Evaluation Research Corporation's Technical Information Request (TIk) No. TIR-017 dated August 26, 1985, provided design information which delineated the acceptance criteria for base material defects on field fabricated tanks. TNE's method for verifying the adequacy of the design information was by the use of calculations.
However, as of May 15, 1986, those calculations were incomplete and unapproved (445/8607-V-02).
RESPONSE TO ITEM B (445/8607-V-02)
We admit the violation and the requested information follows.
- 1. Reason for Violation The violation resulted when Comanche Peak Engineering (CPE) personnel in the mechanical discipline elected to provide the subject defect acceptance criteria on an "at risk" basis prior to formal design verification. The completed but unverified acceptance criteria was issued in response to Technical Information Request (TIR) No. TIR-017 to expedite inspection of field fabricated tanks. CPE-Mechanical recognized that if subsequent formal verification showed that the criteria was invalid, the tanks would require reinspection. The CPE Mechanical personnel had sufficient confidence in the completed but unapproved calculations that the risk was
. considered acceptable. Completion of formal design verification of the
! calculation was entered into an engineering Action Item List and the l
records calculation log to ensure it would be tracked. Procedure TNE-DC-3, " Preparation and Review of Calculations" requires that calculations be checked and approved, but makes no provisions for issuing unverified results in order to expedite field work.
- 2. Corrective Steos Taken and Results Achieved i The calculation was reperformed and verified in accordance with procedure TNE-DC-3 on May 21, 1986. No change from the previously issued acceptance criteria was required. CPE-Mechanical verified that no other unverified calculation results have been issued to Evaluation Research Corporation.
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r Attachment to TXX-6306 March 6, 1987
Page 2 of 13 NOTICE OF VIOLATION RESPONSE TO ITEM B (445/8607-V-02) Cont'd It was determined that issuance of results of unverified calculations on an "at risk" basis is not a typical practice. We have also determined that this practice is not allowed by the Stone & Webster Engineering Corporation procedures or other CPSES Engineering contractors.
- 3. Corrective Steos Which Will be Taken to Avoid Further Violations Appropriate CPE personnel will be instructed that the results of completed but unverified calculations shall not be issued to support field activities.
- 4. Date When Full Comoliance Will be Achieved The instruction of CPE personnel will be completed no later than April 6, 1987.
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Attachment to TXX-6306 March 6,~1987 Page 3 of 13 NOTICE OF VIOLATION ITEM C (445/3607-V-21)
C. Criterion V of Appendix B to 10 CFR Part 50, as implemented by Section 5.0, Revision 3, dated July 31, 1984, of the TUGCo QAP, dated July 31, 1984, requires that activities affecting quality shall be prescribed by and accomplished in.accordance with documented instructions, procedures, or drawings of a type appropriate to the circumstances.
Paragraph 4.0 of Revision 6 to CPSES Startup Administrative Procedure CP-SAP-13, " Temporary System Modifications," dated December 9, 1985, states, in part, " Temporary modification tags shall be filled out and placed on all-modifications required to be logged and tagged. . ., a Log Sheet shall be filled out . . . , and lifted leads shall be suitably insulated."
Paragraph 4.2.4 of CPSES Station Administrative Manual Precedure STA-602,
" Temporary Modifications," Revision 1, dated March 5, 1986, states, in part, "Each temporary modification will be clearly identified with a Temponry Modification Tag. . . , The tag normally will be hung en the lifted lead . . . . or placed as close to the modification as possible."
Contrary to the above:
- 1. The white conductor of cable EG123389 was found lifted in Unit 1 Termination Cabinet 4 without being tagged, logged, or insulated.
- 2. The black conductor of cable EG106004 was found lifted in Unit 1 Control Room Relay Rack No. 2 without being tagged or logged. This conductor was subsequently reconnected without documentation of the nonconforming condition (445/8607-V-21).
RESPONSE TO ITEM C (445/8607-V-21)
We admit to Item No.1 of the violation and the requested information follows.
-Item No.1 - Cable EG123389(W)
- 1. Reason for Violation
(
A search of records was performed to determine the cause of the subject conductor being left unterminated. The last recorded activity on this cable was in December 1983, when the cable was reterminated after the replacement of a bad crimp. (See Startup Work Authorization No. 15423 and i
documented on Construction Quality Control Inspection Report No. ET l 0005416.)
Plant records show that this circuit was verified operable under Startup
- Prerequisite Test EE-12, " Annunciator Operability" on July 26, 1984.
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- Attachment to TXX-6306 March 6, 1987 Page 4 of 13 NOTICE OF VIOLATION RESPONSE TO ITEM C (445/8607-V-21) Cont'd Nuclear Operations personnel found no plant record to indicate why the lead was lifted. However, we believe that this incident is an isolated event. Our position is supported by the significant number of inspection activities performed on electrical wiring during this period that reveal no other similar discrepancies. The lead identified in the Notice of Violation appears to be the only one that cannot be traced to some tracking document.
- 2. Corrective Steos Taken and Results Achieved A Work Order will be issued to reterminate the cable.
The plant Operations Department will be notified of the impact the lifted lead has on valve indication.
- 3. Corrective Steos Which Will Be Taken To Avoid Further Violation The requirement for procedural compliance on temporary modifications will be reiterated to the Nuclear Operations Electrical Maintenance and Instrument and Control Groups. The reasons for properly tagging and logging of lifted leads under the temporary modification program will be stressed.
- 4. Date When Full Comoliance Will Be Achieved The Work Order and the notification to Operations Department will be completed by March 8, 1987.
Action taken to avoid further violations will be complete by March 31, 1987.
We deny that Item No. 2 of the Violation is a deficiency for the reasons that follow:
Item No. 2 - Cable EG106004(B)
A records search (similar to the search performed in Item 1 above) was conducted to determine the root cause of the conductor being found lifted without being tagged or logged. A subsequent evaluation by Nuclear Operations personnel resulted in the determination that this is not a
! violation because work on the conductor did not constitute a temporary modification, in accordance with site procedures.
l Cable EG106004(B) originally provided a shunt trip function for battery charger 1024. This function was deleted by revision 3 to drawing El-0066, sheet 76 dated July 22, 1983. Cable EG106004(B) originates in CP1-ECPRCR-04 and ends in CPI-ECPRTC-27 at TB2-83.
Attachment to TXX-6306 March 6, 1987 Page 5 of 13 NOTICE OF VIOLATION RESPONSE TO ITEM C (445/8607-V-21) Cont'd The results of the records search indicate that this cable was terminated following the installation of a butt splice (PIES), in June 1984, (see DCA 18,968 and Construction Quality Control Inspection Report No. ET 0046966).
In December 1984, the Construction Electrical Deficiency Report No. PCV 0057893, Item 4, documented that the cable was lugged, but not landed.
The deficiency was entered on the Construction Master Data Base (System 5201, Item 10555) for tracking.
In January 1985, the conductor was identified by the CPRT and tracked as an out-of-scope item ISAP I.a.2.
In June 1985, Work Order C85-1221 was issued by Results Engineering to reland EG106004(B) to close out the open item on the Construction Master Data Base. The work order was accomplished and verified complete by Operations QC Inspectors on June 19, 1985.
The lifted status of cable EG106004(B) was logged from point of discovery to closure.
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Attachment to TXX-6306
' March 6, 1987 m~ Page 6 of 13 NOTICE OF VIOLATION ITEM D (445/8607-V-20)
D. Criterion V of Appendix B to 10 CFR Part 50, as -implemented by Section 5.0, Revision 3, of the TUGCo QAP dated July 31, 1984, requires that activities affecting quality shall be prescribed by and accomplished in accordance with documented instructions, procedures, or drawings of a type appropriate to the circumstances.
Drawing 2462-1005, sheet 1, Revision CP-1, requires that identification be provided adjacent to " components."
Contrary to the above, except for TB-53, -54, -55, the terminal blocks in Unit 1 Control Room Panel CPI-ECPRCR-01 were not identified (455/8607-V-20).
RESPONSE TO ITEM D (445/8607-V-20)
We deny the alleged violation for the reason that follows.
The subject terminal blocks were identified in accordance with Drawing 2462-1005. The identification markings are not visible unless the protective terminal block covers are removed. Installation of the covers apparently led the NRC inspector to believe that terminal blocks were not identified.
r tw Attachment to TXX-6306 l - March 6, 1987 l
a' Page 7 of 13 NOTICE OF VIOLATION ITEM E (445/8607-V-22)
E. Criterion V of Appendix B to 10 CFR Part 50, as implemented by Section 5.0, Revision 3 of the TUGCo QAP dated July 31, 1984, requires that activities affecting quality shall be prescribed by and accomplished in accordance with documented instructions, procedures, or drawings of a type appropriate to the circumstances.
l Paragraph 2.1.3 of THE Procedure TNE-DC-7, Revision 16, dated February 14, 1986, " Preparation and Review of Design Drawings," requires that completed drawings shall be checked for accuracy and compliance. Paragraph 2.1.4 also requires an engineering review for technical accuracy upon completion of the drafting / design review.
Contrary to the above, drawings were not appropriately reviewed / checked for accuracy. The following drafting errors were involved with unsatisfactory items identified during inspections related to ISAP I.a.4:
- 1. Drawing 2323-El-0172, sheet 17, identified cable EG120248 AS EG20248.
- 2. The white conductors of cables EG109964, EG109975, EG109963, and EG109764 were not shown on Drawing 2323-El-0156, Revision CP-1.
- 3. Drawing 2323-El-0156, Revision CP-7, shows the green conductor of cable EG118347 landed at terminal TCA-5; the conductor actually installed is white with a black stripe. This drawing also showed the orange conductor of cable EG130012 landed at terminal TCA-7; the conductor physically installed was black from cable EG118347A. There was no " cloud" on the drawing to indicate that this was a design change.
- 4. Drawing 2323-El-0172, sheet 17, Revision CP-4, did not identify the color of the conductor to be landed at TB2-31 (445/8607-V-22).
RESPONSE TO ITEM E (445/8607-V-22)
We admit the violation and the requested information follows.
- 1. Reason for Violation The violation was caused by unrelated oversights by drafting / design and engineering personnel.
For clarity in the following discussions, the drawing errors are numbered in accordance with the numbers used in the Notice of Violation. Errors 3.a and 3.b refer to the two errors stated in item 3 of the Notice of Violation.
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- Page 8 of- 13 : i l
NOTICE OF VIOLATION .
RESPONSE TO ITEM E'(445/8607-V-22) Cont'd ;
Errors 1 and 4 on drawing 2323-El-0172 were a result of transferring information from a poor quality original to a mylar document. In the-reproduction process, some of the alphanumeric characters on the original l did not carry over onto the mylar.
Error 2 on drawing 2323-El-0156 was due to an inadvertent. incomplete incorporation of a~DCA. When DCA-15484, Rev. 3 was incorporated into Revision CP-1 of drawing no. 2323-El-0156 the white conductors of cables EG109964, EG109975, EG109963 and EG109764 were inadvertently omitted.
1 Error 3(a) on drawing 2323-El-0156 was due to a drafting error and error 3(b) to ar. incomplete " clouding" of a drawing revision. " Clouding" is used to distinguish information incorporated during the drawing revision.
- 2. Corrective Steos Taken and Results Achieved Error I The cable EG120248 identification error was corrected by revision CP-3
.. (dated February 4, 1985) to drawing 2323-El-0172.
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Error 2 i The omission of the white conductors of cables EG109964, EG109975,_
EG109963 and EG109764 was corrected by revision CP-5 (dated January 10, 1985) to drawing 2323-El-0156.
Error 3.a TNE Design Deficiency Report (TDDR) EE-86-187 was issued on April 30, j . 1986,to identify the error. DCA 31,277, Rev. O, will be issued to change i the color of the conductor of cable EG118347 landed at terminal block TCA, point 5, from green to white with a- black stripe. This DCA is associated with the design change of Design Modification (DM)85-077 and therefore will be issued in conjunction with the issuance of the DM. The DCA will be incorporated into drawing 2323-E-0156 upon implementation and inspection of DM 85-077.
Error 3.6 TDDR EE-86-186 was issued on April 30, 1986, to identify the cloud omission error. DCA 31,277, Rev. O, will be issued to ensure the field verifies that the orange conductor of cable EG130012 is landed at TCA-7 and that all conductors of cable EG118347A are spared. This DCA is associated with the design change of DM 85-077 and therefore will be issued in conjunction with the issuance of the DM. The DCA will be incorporated into drawing 2323-El-0156 upon implementation and inspection of DM 85-077.
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Attachment to TXX-6306
- March 6, 1987 Page 9 of 13 NOTICE OF VIOLATION RESPONSE TO ITEM E (445/8607-V-22) Cont'd Error 4 DCA 33,523, Rev. O, was issued to identify the color of the conductor to be landed at terminal block TB-2, point 31. This DCA will be incorporated into the next revision of drawing 2323-El-0172.
- 3. Corrective Steos Which Will be Taken to Avoid Further Violations The drawing errors resulted from oversights by individuals involved in the preparation of drawings and revisions, and are not considered indicative.
of a generic problem. Since the organization preparing drawings and revisions at the time the errors were made is no longer engaged in the activity, counsaling or reinstruction of personnel is not appropriate.
Electrical drawng reviews are specified by Stone & Webster Engineering Corporation (SWEL) procedure PP-032, " Preparation, Review, and Approval of SWEC Project Drawings," and TV Electric procedure ECE-DC-7, " Preparation and Review of Design Drawings." TU Electric believes that the reviews required by these procedures will provide the necessary degree of confidence in.the accuracy of electrical drawings. In addition, there are several mechanisms whereby drawing errors are detected. These mechanisms consist of field installation activities, post installation inspections, construction testing, pre-operational testing and Comanche Peak Response Team inspections. These additional mechanisms provide further assurance that significant drawing errors will be detected and corrected.
Correction of drawing errors is normally accomplished via design change Nonconformance Reports (NCRs) and Design Change Authorizations (DCAs).
Comanche Peak Engineering has recently initiated a program for trending of design change NCRs and DCAs. This program, as specified in procedure ECE 2.11, " Design Change Trending", identifies adverse trends involving drawing errors and requires corrective actions as appropriate. TU Electric believes this program is adequate to identify and correct programatic or generic design drawing deficiencies.
- 4. Date When Full Comoliance Will be Achieved DCA 33,523, Rev. 0 will be incorporated into drawing 2323-El-0172 no later than April 30, 1987.
DCA 31,277, Rev. O will be incorporated into drawing 2323-El-0156 no later than June 30, 1987.
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. Attachment to TXX-6306 1 March 6, 1987 i Page 10 of 13 NOTICE OF VIOLATION ITEM F (445/8607-V-04)
F. Criterion III of Appendix B to 10 CFR Part 50, as implemented by Section 3.0, Revision 4, dated November 20, 1985, of the TUGCo QAP, states, in part, ". . . Design changes, including field changes, shall be subject to design control measures commensurate with those applied to the original design and approved by the organization that performed the original design. . . . "
Contrary to the above, field design changes, pertaining to the installation of stainless steel shims between the reactor coolant system crossover leg piping and saddle blocks, were not submitted to the organization that performed the original design for review and approval.
In addition, the traveler which was used to implement the design change did not document all of the changes that occurred (445/8607-V-04).
RESPONSE TO ITEM F (445/8607-V-04)
We deny the first part of the alleged violation for the reasons that follow:
At the time that DCA 21,116, Revision 0, was issued (September 27,1984),
Comanche Peak Engineering (CPE) possessed an approved design document which allowed the installation of the subject stainless steel shims. This design document, titled, " Reactor Coolant System Equipment Supports Shim / Gap Acceptance Criteria," had been transmitted to CPE via letter (WPT-7517, dated September 18,1984) from the Westinghouse Comanche Peak Project Manager in Pittsburgh. The use of shim stock / capture plates for supports and restraints, except RCP tie rods, was approved on page 7 of the criteria. Although CPE failed to provide the transmittal letter to the NRC inspector during the inspection, the letter indicates prior design approval by Westinghouse.
We admit the second part of the violation and the requested information follows: ,
- 1. Reason for Violation The violation was caused by a lack of clarity in the documentation of I completed work on the Reactor Coolant System (RCS) loop 2 crossover leg, I
steam generator (SG) side, saddle block shim installations. The traveler which directed installation of the shim stock was worked in combination with another traveler which addressed installation of the saddle block on the piping. In implementing steps required by the second traveler l measurements documented in the first traveler were superceded by i
repositioning the saddle block. Through discussions with the personnel involved, it was determined that the shims were installed as required and the final configuration was in accordance with design requirements.
However, conformance with design requirements cannot be clearly verified by reviewing the completed travelers.
T l
' Attachment to TXX-6306 l March 6, 1987 '
Page 11 of 13 l RESPONSE TO ITEM F (445/8607-V-04) Cont'd l
- 2. Corrective Steos Taken and Results Achieved The installation will be inspected to verify the acceptability of the shim installations. Copies of the inspection reports will be placed in the packages for the two travelers discussed above. These activities will be performed as documented per Deficiency Report (DR) No. C-87-886 The completed travelers for shim installation on the other RCS loop 1,2,3 and 4 restraints will be reviewed to ensure the documentation clearly describes the final installation and conformance to design requirements.
Additional nonconformance reports will be issued and completed, if necessary, to provide proper documentation.
- 3. Corrective Steos Which Will be Taken to Avoid Further Violations Appropriate CPE personnel will be instructed to ensure that instructions provided in travelers governing field activities adequately and clearly document conformance to design requirements in the final configuration.
- 4. Date When Full Comoliance Will be Achieved Reinspection of the RCS loop 2 crossover leg, SG side, saddle block shim installation per DR C-87-886 will be completed no later than April 20, 1987.
Review of completed travelers for other RCS loop 1,2,3 and 4 restraints and any necessary reinspection will be completed no later than May 20, 1987.
Instruction of CPE personnel will be completed no later than April 6, 1987.
l 1
F Attachment to TXX-6306
- March 6, 1987 Page 12 of 13 NOTICE OF DEVIATION ITEM I.5 (445/8607-D-13)
I. -Section 4 in Revision 4 to CPRT Project Procedure CPP-009 states, in part,
" Qualified QA/QC Review Team personnel perform field reinspections of specific hardware items and reviews of appropriate documents in accordance with approved instructions . . . ."
Section 4 in Revision 2 to ERC Quality Assurance Procedure ERC-QA-28,
" Performance of Overview Inspections," states, in part, " Qualified QA/QC Review Team personnel assigned to the on-site QA Representative perform Overview Inspections of work performed in accordance with Reference 3.1 (CPP-009) . . . ." Section 5.4.2 of ERC-QA-28 states, in part, " Based upon each accept / reject criterion specified in the referenced QI/ effective Change Notice (s), the OI (Overview Inspector) denotes whether the item is (un) acceptable . . . ." Section 5.4.3 of ERC-QA-28 states, in part, "The 01 compares the results of the Overview Inspection with the results of the initial reinspection / documentation review to identify any apparent inconsistencies . . . ."
In deviation from the above, the following error was identified concerning the results of overview inspections:
I.5. The initial ERC inspector and the OI signed off as acceptable Attribute 3 regarding spherical bearing gap for Verification Package I-S-PS7N-146. Independent inspection of this package revealed that the spherical bearing had been painted, precluding an accurate measurement of either the gap or the spacer (445/8607-D-13).
RESPONSE TO ITEM I.5 (445/8607-D-13)
We admit the deviation and the required information follows.
l 1. Reason for Deviation l
l ERC Reinspection and Overview .ispection failed to N/A Attribute 3 regarding spherical bearing gap for Verification Package No.1-S-PS7N-146
- due to the attribute being non-recreatable. The attribute was non-recreatable due to the presence of paint in the gap area and on the spacer masking the performance of an accurate measurement.
- 2. Corrective Steos Taken and Results Achieved l
As a result of the deviating condition identified by the NRC, Verification Package No.1-S-PS7N-146 Attribute 3 will be N/A'd to reflect this observation. Futhermore, on August 1, 1986, an Out-of-Scope Observation l (00S) No. 796 was prepared to identify that paint was observed on the
! surface of the spherical bearing. It was also noted on the 00S that the sway strut had freedom of movement. Additionally, TV Electric initiated Nonconformance Report M-25303N on September 17, 1986, to address this concern.
l
F
. Attachment to TXX-6306 March 6, 1987 e Page 13 of 13 RESPONSE TO ITEM 1.5 (445/8607-D-13) Cont'd
- 3. Corrective Steos Which Will be Taken to Avoid Further Deviation On August 1, 1986, an ERC inspector along with NRC inspector reinspected the total population of pipe support spherical bearings previously inspected by the ERC inspector identified in this deviation. Seven packages were reinspected and four Out-of-Scopes were prepared (including the 00S mentioned above) to identify that paint was observed on the surface of the spherical bearing (s). In all cases, the sway strut had freedom of movement. Additionally, TU Electric has initiated Nonconformance Reports M-25384N, M-25385N, and M-25362N addressing the concern. Although we believe this condition to be an isolated case and plan no further action by Reinspection or Overview Inspection, TU Electric has nevertheless undertaken a Hardware Validation Program (HVP) whereby all pipe supports (100%) will be reinspected including such items as the spherical bearing gap, spacers, etc.
- 4. Date When Full Comoliance Will be Achieved CPRT compliance will be achieved when Verification Package No. 1-S-PS7N-146, Attribute 3 is corrected. This is scheduled for completion by April 30, 1987.
TU Electric Hardware Validation Program is tentatively scheduled to be completed by August 1, 1987.
l l
l l
I v.
?~ File No. 10002 a
COMMITMENT TRACKING OUTG0ING CORRESPONDENCE EVALUATION SHEET DOCUMENT IDENTIFICATION Title /
Subject:
SUPPLEMENTAL RESPONSE TO INSPECTION REPORTS Log No. TXX-6306 50-445/86-07 AND 50-446/86-05 File 10130 Date 03/06/87 ITEM TRACKING Item Tracking Item No. Description Types
001 Appropriate CPE personnel will be instructed that the IA LCR-87-128 results of completed but unverified calculations shall not be issued to support field activities. See response to ItemB (445/8607-V-02) 002 A Work Order will be issued by Operations to reterminate IA LCR-87-129 Cable EG123389 (W) by March 8,1987.
See response to Item C (445/8607-V-21).
003 The Operations Department will be notified of the impact IA LCR-87-130 of lifted leads (specifically Cable EG123389 (W)) on valve indication. See reponse to Item C (445/8607-V-21).
004 The requirement for procedural compliance on temporary IA LCR-87-131 modifications will be reiterated to the Nuclear Operations Electrical Maintenance and Instrument & Controls Groups.
See response to Item C (445/8607-V-21).
l l 005 DCA 33,523, Rev. O, will be incorporated into drawing DB LCR-87-132 l 2323-El-0172 no later than April 30, 1987.
1 See response to Item E (445/8607-V-22).
006 DCA 31,277, Rev. O, will be incorporated into drawing DB LCR-87-133
- 2323-El-0156 no later than June 30, 1987.
i See response to Item E (445/8607-V-22).
1
- Item Types: EA - External Action OB - Operational Basis DB - Design Basis
! IA - Internal Action DO - Description Only AS - (See LCR form)
COMPLETED BY REVIEWED BY Initials Og*
u Date
- m Initials M Date 3/6/57 l
1
m z
3:
. File N3. 10002 s
COMITMENT TRACKING OUTG0ING CORRESPONDENCE EVALUATION SHEET DOCUMENT IDENTIFICATION Title /
Subject:
SUPPLEMENTAL RESPONSE TO INSPECTION REPORTS Log No. TXX-6306 50-445/86-07 AND 50-446/86-05 File 10130 Date 03/06/87 ITEM TRACKING Item Tracking
-Item No. Description Types
007 Reinspection of the RCS loop 2 crossover leg, SG side, IA LCR-87-134 saddle block shim installation per Deficiency Report (DR)
C-87-886 will be completed no later April 20, 1987.
008 Review of completed travelers on the other RCS 1, 2, 3, & 4 IA LCR-87-135 restraints and any necessary reinspection will be completed no later than May 20, 1987.
009 Appropriate CPE personnel will be instructed to ensure that IA LCR-87-136 instructions provided in travelers governing field activity adequately & clearly document conformance to design requirment in the final configuration. See Item F (445/8607-V-04).
010 CPRT compliance will be achieved when Verification Package IA LCR-87-137 No. 1-S-PS7N-146, Attribute 3 is corrected. This is scheduled for completion by April 30, 1987.
See response to Item I.5 (445/8607-D-13).
011 The TU Electric Hardware Validation Program is tentatively IA LCR-87-138
, scheduled to be completed by August 1,1987.
See reponse to Item I.5 (445/8607-D-13).
- Item Types: EA - External Action OB - Operational Basis DB - Design Basis IA - Internal Action DO - Description Only AS - (See LCR form)
COMPLETED BY REVIEWED BY Initials p4- Date N7 Initials Date $[6[k7
Outg31ng Correspondence bec (2):
M. D. Spence R. L. Grubb S. S. Palmer A W. G. Counsil G. M. Hamilton L. E. Powell J. W.-Beck J. L. Hansel R. L. Ramsey R. W. Ackley L. J. Hardie J. D. Redding D. L. Anderson H. A. Harrison D M. Reynerson
- R. E. Ballard R. A. Jones
- N. S. Reynolds J. L. Barker R. T. Jenkins
'* J. H. Buck S. D. Karpyak H. C. Schmidt
- A. Buhl G. S. Keeley/ A. B. Scott
- W. R. Burchette J. S. Marshall C. E. Scott
- E. J. Siskin R. D. Calder J. E. Krechting P. B. Stevens F. Camp J. C. Kuykendall
- D. F. Landers J. F. Streeter R. L. Cloud
- H. A. Levin T. G. Tyler D. E. Deviney 0. W. Lowe
, D. M. McAfee/
- E. L. Wagoner-( J. Ellis P. E. Halstead H. M. Warren (2) l l W. D. Fenoglio
- J. P. McGaughy D. R. Woodlan J. C. Finneran D. D. Mosley R. A. Wooldridge J. L. French
- J. Garibaldi L. D. Nace h L. W. Garner
- W. E. Nyer J. B. George PIMS
- = First Class Mail March 2, 1987