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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-4694 File # 10130 IR 85-13 TEXAS UTILITIES GENERATING COMPANY IR 85-09
&KYWAY TOWER
- 400 NORTH OLIVE EFFREET. L.B. St
- DAILAS. TEXAS 78308 February 21, 1986 WILLIAM G. COUNSIL Mr. Eric H. Johnson, Acting Director l Division of Reactor Safety and Projects E2'E i U. S. Nuclear Regulatory Commission f Region IV U a; V, 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76012
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 RESPONSE TO NRC NOTICE OF VIOLATION INSPECTION REPORT NOS.: 50-445/85-13 AND 50-446/85-09
Dear Mr. Johnson:
We have reviewed your letter dated December 24, 1985, concerning the inspection conducted by Mr. T. F. Westerman and other members of the Region IV Comanche Peak Group during the period August 23, through September 30, 1985. This inspection covered activities authorized by NRC Construction Permits CPPR-126 and CPPR-127 for Comanche Peak Steam Electric Station Units 1 and 2.
We requested and received two extensions of two weeks each in providing our response during telephone discussions on January 23, 1986, and February 7, 1986, between yourself and Mr. John Marshall of TUGCO. These extensions were necessary because of holiday delays and the number of issues to be addressed.
We have responded to the Notice of Violation and have provided a partial response to the Notice of Deviation in the attachments to this letter. To aid in understanding our response, we have attached the Notice of Violation and Notice of Deviation. We consider the enclosed information to be responsive to the inspector's findings.
Very truly yours, W 6Ls:l W. G. Counsil JWA/gj /
Attachments By:_ [ '
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LC-O30 & a ouvussou or r xas uruzzrues #1xcrsuc coursur v
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Director, Inspection and Enforcement (15 copies)
U.S. Nuclear Regulatory Commission i
Washington, D.C. 20555 Mr. V. S. Noonan Mr. D. L. Kelley I
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A_PPENDIX A NOTICE OF VIOLATION Texas Utilities Electric Company Comanche Peak Steam, Units Electric1 and 2Station Dockets: 50-445/85-1 Permits: CPPR-126 50-445/85-0 CPPR-127 five violations of NRC ugust requirementsDuring 23 throu an provisions for control of e deleteriousinspection pipe support dimension, inade 30, 1985, installed components, incomplete and materials unauthorized breaking of an accepted fl
" General Statement of Policy missing and angePr joint.con,duit identification, 10 CFR Part 2, Appendix C (1985)
A. ocedure for NRC EnforcementIn a Criterion V of Appendix B , the violations are listed below: Actions,"
Quality 1981, Assurance requires Program QAP) that activities (to 10 CFR Part 50, a,ffecti as documented instructions, procedures Section 5.0, Revision 2, dated C0 May instructions, procedures, omplished
- s. in or drawingthe accordance with thesee cap Site Procedure shall assign a QI-QAP-11.1-28 number to each states th the Q dimensionalat specific dimension inspection report and shall record the attribute identified as a actual measurements on this was recorded on the QC inspection reContra assigned and no measurement result dimension shown on pipe support dr dimension was independently port for awing checked the wall-to b
AF-2-006-412-533A. pipe centerline when the drawing showed it ytoNRC, be 11h i When this it was found to be 13 -inches nches.
This is a Severity 1.evel V violati B.
TUGC0 QAP, Section 13.0, Revision 1 Cri
, dated JulyPart 50, as implemented by measuresand cleaning, be established preservation toofcontrol 31, 1984,the h material andandling, s work and inspection instructions to p revent damage or deterioration Revision 8, dated July 5, 1984Section 2.17 of Gibbs .
contamination of reactor defines the actions to mit be taken coolant equipment low melting point metals and their csurfaces; e.g.
ompounds, prohibition,of use ofprohibition of l
C of 4 mi, i o W7h T%.*hDM 1 e l
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instruments containing mercury, and restriction of halide content of products such as machining coolants, seals, and plug materials.
Contrary to the above, implementing site procedures do not address prohibition of use of instruments containing mercury, do not provide necessary craft guidance for contamination control, or include provisions to assure that procured consumables are in compliance with specification requirements.
This is a Severity Level IV violation (Supplement II) (446/8509-V-02).
C. Criterion V of Appendix B to 10 CFR Part 50, as implemented by the TUGC0 QAP, Section 5.0, Revision 2, dated May 21, 1981, requires that activities affecting quality shall be prescribed by documented instructions, procedures, or drawings of a type appropriate to the circumstances and shall be accomplished in accordance with these instructions, procedures, or drawings.
Brown & Root Procedure MCP-10, paragraph 3.6, Revision 9, dated July 2, 1985, requires that items stored in place shall merit additional protection if construction work threatens the integrity of equipment and includes a prohibition in regard to placing work platforms or scaffolds on permanent plant installations, such as a pipe, tray hangers, etc., without written engineering authorization. '
Contrary to the above:
- 1. On September 25, 1985, the NRC inspector observed in Room 16 (854 feet elevation) a wooden two by four which was laid across .
3/4-inch pipe RC-2-095-501R-2 to serve as a work platform, but there was no evidence to indicate that engineering had authorized this temporary platform.
- 2. On September 24, 1985, the NRC inspector observed at the 905 feet elevation that welding had taken place above the reactor pressurizer and associated piping without adequately protecting the equipment, as evidenced by the presence of weld spatter on weld no. 42 in 6-inch line RC-2-096-2501R-1.
This is a Severity Level IV violation (Supplement II)
(446/8509-V-03).
D. Criterion V of Appendix B to 10 CFR Part 50, as implemented by the TUGC0 QAP, 5,ection 5.0, Revision 2, dated May 21, 1981, requires that activities affecting quality shall be prescribed by documented instructions, procedures, or drawings of a type appropriate to the circumstances and
3 shall be accomplished in accordance with these instructicns, procedures, or drawings.
Paragraph 3.1.1, subparagraphs b and c, of TUGC0 Procedure QI-QP-11.3-8, Revision 0, issue date July 7,1978, " Identification and Color-Coding Inspections," require that conduit designation shall be applied with black ink or paint and that identification of conduit be verified at both sides of all walls and slabs through which conduit passes.
Paragraph 3.1.1, subparagraph b, of TUGC0 Procedure QI-QP-11.2-23.7, Revision 1, issue date January 5, 1980, " Verify Conduit Identifications,"
similarly requires that conduit be identified on both sides of all walls and slabs through which conduit passes. Subparagraph c. of this paragraph states, in part, " Groups of embedded conduits which are flush with the surface of walls, floors and manholes shall be identified on the surface or the wall, floor, or manhole by attaching an identification template near the conduit bank. . . ."
Contrary to the above, the following examples of incomplete and missing conduit identifications were noted in the Unit 1 lower cable spread room, auxiliary building, and safeguards building:
1.
Two conduits attached to embedded conduit wall sleeve TSW-A-020 were not identified on the identification template and one conduit which was identified on the template as being present did not, in fact, exist.
2.
Two banks of embedded conduit wall sleeves below sleeve TSW-A-023 had no form of identification.
- 3. At tray section T14GCDH27, there were four floor sleeves which were not identified by either identification template or conduit marking.
- 4. At tray section T24WAEF, there were two floor sleavas with an incomplete identification template; i.e., the template contained only the letters TFS.
- 5. Below battery pack CPI-ELBPSG-187 (Circuit ESB7-11), there were two floor sleeves which were not identified.
- 6. At a tray section above junction box JBIA-1332, the embedded conduit wall sleeves were not identified by either identification template or marking.
- 7. Ihree of five floor sleeves at tray section T220ABA41 were unmarked.
- 8. Four floor sleeves at tray section T120ABB23 were unmarked.
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Conduits attached to embedded conduit wall sleeve TSW-A-030 were not l identified on tha identification template which was present.
This is a Severity Level IV violation (Supplement II) (445/8513-V-01).
E.
Criterion V of Appendix B to 10 CFR Part 50, as implemented by TUGC0 QAP, Section 5.0, Revision 2, dated May 21, 1981, requires that activities affecting quality shall be prescribed by documented instructions, procedures or drawings of a type appropriate to the circumstances and shall be accomplished in accordance with these instructions, procedures, or drawings.
Paragraph 3.5.2.1 in Revision 7 of Brown & Root Procedure CP-CPM 6.9E states, in part, "When it becomes necessary to break an inspected flanged joint for any reason, the responsible craft QA/QC foreman.Building Superintendent shall be notified by This notification will be by the foreman completing an IRN (Item Removal Notice) in accordance with CPM 6.10. . . ."
Paragraph 3.11 states, in part, " Flanged pipe joints shall be tightened sufficiently to prevent leakage."
Contrary to the above, flange no. 6 in Unit 2 piping system BRP-SW-2-018, which was installed, inspected and accepted using Construction Operation Traveler No. MP-82-4117-0400 dated April 20, 1982, was observed in a broken condition as evidenced by loose nuts on 4 of the 12 studs, thus impairing its ability-to sufficiently prevent leakage. Further, there were no available IRNs authorizing any activity which would require the breaking of this flanged joint.
This is a Severity Level IV violation. (Supplement II) (446/850'9'V-04).
Pursuant to the provisions of 10 CFR 2.201, Texas Utilities Electric Company is hereby required to submit to this office within 30 days of the date of the letter transmitting including this Notice, a written statement or explanation in reply, for each violation:
(1) the reason for the violations if 1dmitted; l (2) the corrective steps which have been taken and the results achieved; (3) corrective steps which will be taken to avoid further violations; and (4) the date when full compliance will be achieved.
consideration will be given to extending the response time.Where good cause is shown, l
i Dated in Arlington, Texas, this 24th day of December,1985
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_ APPENDIX B l
NOTICE OF DEVIATION l
1 Texas Utilities Electric Company (TVEC) Docket: 50-445/85-13 Comanche Peak Steam Electric Station, Unit 1 Permit: CPPR-126 Based on the results of an NRC inspection conducted on September 1-30, 1985, of Comanche Peak Response Team (CPRT) activities, three deviations from ;
conrnitments to the NRC were identified. The deviations involved inclusion of non-ASME pipe supports and base plates in the Issue-Specific Action Plan (ISAP)
No. V.d ASME population; issue of reinspection verification packages containing missing, incomplete, and/or incorrect documents; and failure of ERC inspectors to note conditions which violated drawing requirements. In accordance with the
" General Statemect of Policy and Procedure for NRC Enforcement Actions,"
10 CFR Part 2, Appendix C (1985), the deviations are listed below:
A. Paragraph 4.1 in CPRT ISAP No. V.d states, in part, ". . .the absence or presence of unauthorized or undocumented plug welds in ASME pipe supports and base plates will be verified. . . ." Paragraph 4.1.1 states, in part, "Two random samples of ASME pipe supports and base plates will be selected for inspection. One sample will be drawn from the population representing Unit 1 and common and the second sample from the population representing Unit 2. The Sample Plan will be based on identifying, with a 95%
confidence, a rate of detectable plug welds of 5% or greater. The smallest random sample which will achieve this confidence level and rate
... is 60 ...."
Contrary to the above, a review of the 2 selected random samples which were inspected revealed that the 2 random samples contained just 39 and 35 ASME pipe supports and base plates, respectively (445/8513-D-01).
B. Paragraph 5.1 of Procedure CPP-007, Revision 1 entitled " Preparation of checklists and Data Base Reports," states, in part, " Responsible QA/QC Discipline Engineers review the latest Gibbs and Hill, Brown and Root, and subcontractor design documents relating to the population. As applicable, the latest installation procedures, construction drawings (including as-builts) and manufacturer's prints and manuals are also reviewed."
Paragraph 5.2.1 of the above procedure states, in part, "On receipt of the memorandum with attachments, the QA/QC Lead Discipline Engineer reviews the documents for accuracy, completeness, and conformance with this procedure. . . ."
Contrary to the above requirements, verification packages have been issued by the discipline engineers to inspectors with missing, incomplete, and/cr incorrect documents. Examples identified by NRC inspectors include the following:
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- 1. Verification Package No. I-S-LBSR-047 for large bore pipe supports had an incorrect checklist. The responsible QA/QC discipline engineer wrote "NA" for not applicable on the checklist for Richmond inserts, when in fact, Richmond inserts were present as listed on the bill of materials and shown on the design drawing.
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- 2. Verification Packages Nos. I-S-LINR-6 and I-S-LINR-51 for the containment liner and tank stainless steel liner had incorrect checklists. The responsible QA/QC discipline engir.eer wrote "NA" for not applicable on the checklists for two base naterial local centour attributes. The attributes were found during the physical inspection to be inspectable. New checklists were requested by the ERC inspector.
- 3. Verification Packages Nos. I-E-EEIN-029 I-E-EEIN-042 and I-E-ININ-005 were missing documents required for physical inspections. For the first two packages, generic design change authorizations had been issued but were not specifically identified <
or included in the verifict. tion packag's. e For the third package. l l three documents required to determine tubing size were not included in the verification package.
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- 4. Verification Package No. I-S-PS7N-187 contained two rather than tha required number of four forms to document inspection of snubber brackets. The inspection package also contained a form for pipe clamp inspection although a pipe clamp did not exist (445/8513-D-02).
C. Paragraph 5.0 of ERC Project Procedure No. QI-027 Revision 0, identifies the applicable inspection notes to be used, and requires that the reinspection checklist is to be used by the inspector to document the inspection results.
Note 30, an identified inspection note states, "In the course of inspection the inspector shall note any item not covered by reinspection / verification which appears out of the ordinary as related to the construction of the inspected item cr sucrounding area. Note such in the remarks column of inspection checklist."
I Contrary to the above, the ERC inspectors failed to identify and note an cut-of-the-ordinary condition in the remarks column of the inspection checklist for ASME pipe support MK No. CT-1-053-436-C52R; i.e., the existence of four 9/16" diameter holes in item 2 of the pipe support that were not shown on the applicable drawing.
Texas Utilities Electric Company is hereby requested to submit to this office, within 30 days of the date of this Notice of Deviation, a written statement or explanation in reply, including for each deviation: (1) the reason for the deviations if admitted, (2) the corrective steps which have been taken and the I . . . . .
3 results achieved, (3) corrective steps which will be taken to avoid further deviation from commitments made to the Comission, and (4) the date when full compliance will be achieved.
Consideration may be given to extending your response time for good cause shown.
Dated in Arlington, Texas, this 24th day of December, 1985 i
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Response to Notice of Violation Item A (446/8509-V-01)
We do not feel that this item on. is a violati At the time the apparent deficiency was id response that provided the dimension by the Brown in question was not &anager Root Site QA Mentified to this item was was a location Checklist. dimension However, after discussin as identified in itan attribute verifie em A.2. of th
".....e attached QC the QC QI-QAP-11.1-28.
inspector to measure this dimen,siattrib he incorrectly agree.each dimens on appeared to violate the words of Subsequent to this discussion, he verified it and all the QC program.
QC personnel were inspector to measure this dimensi cognizant of t
- n. e requirements of A.I.
on did not violate the inspectio BRH AF-2-006-412-S33A inspector on 4/27/85. in completing the Component Rev.0S used ev.2, were and CMC 86747 by the QC j Field Engineering and CMC-86747 Rev dimension. .
a 0 iAt that time, t inspector did not contain the CMC's isFor unknown rea was notthe within aware that the dimension QI-QAP-ll.1-28 revised. had be Therefore, en requirement ofsuedhe again dimension fcr pipe location. and well withinplus/minus the 23231 MS inch 100of the revise tolerance of plus/minus 2 inches The complete support package a is avail bl e for review by your inspector.
w- w " _.
Response to Notice of Violation Item 8 (446/8509-V-02) 1.
Reason for the Violation control of chemical substances need to orbe stren The current and existing procedures may be used in acc requirements val. and may not be used elsewhere without o- Engin 2.
Corrective Steps Which Have Been Taken and Results Achieved In order to strengthen the project control program,.,CP-CPM-9 2 the application of approved substances." Control oeof Che for the identification of noncompliances by nonconformance ports.
rePro Upon issuance of the revised procedure, an in-depthe made survey will of applicable directions. plant structures to ensure compliance with presc issuance of the procedure in accordance program.
raining with the 3.
Corrective Steps Which Will Be Taken to Avoid Further Viola:f by the implementation of construction recurrence es. This surveilla program will be further supported by the training specified abov trending activities for related nonconformance reports e and
- 4. Date When Full Compliance Construction Procedure than March 7,1986.
completed by March 21,The survey 1986.
CP-CPM-9.2 oislater for compliance and training scheduled will be I
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Response to Notice of Violation i
Item C (446/8509-V-03) 1.
Reason for the Violation The two findings noted were confirmed followin the NRC.
group responsible for these items.Further investigation could n e individual or permanent installed equipment.a lack of awareness by cra ance of protecting 2.
! Corrective Steps Which Have Bcen Taken and Result
! s Achieved.
1 of October, 1985.Both of the conditions e identified were correct d These staff findings meeting were on Cctober 1 discussed with all Supe i tNo damage . { w 1985. r n endents at the weekly the integrity of permanent installationsvision to prec for discussion at the weekly safety meeting These findings were a topicc encies January 27, 1986.
with the craft personnel on 3.
Corrective Steps Which Will Be Taken to Avoid F urther Violations.
through supervision. Craft awareness of these concerns will conti nue to be emphasized supervision will continue in orderr to prevent fu thMonitoring er violations.y 1986, to assess the effectiveness g.
of28,traininQuality ormed by March 4
Date When Full Compliance Will Be Achieved .
The full compliance date was January , 1986. 27 l
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i Responsg to Notice of Violation Item D (445/8513-V-01)
- 1. Reason for the Violation l
We have reviewed each of these findings and concludad that a lack of i understanding of the requirements for sleeve identifications was the cause of those findings. Many of the sleeves noted are unused and do not require identifications until they are utilized. T'iose sleeves which were found to have incorrect / incomplete identification are being corrected.
- 2. Corrective Steps Winich Have Been Taken and Results Achieved To ensure compliance within the ES-100 Specification regtfrements for sleeve identification, we will be oerforming walkdowns of all power and non-power through-wall and thruagh-floor sleeves. In addition, we have initiated a comparison review of ES-100, Drawing 2323-El-1701, DCA 21464 and Installation and Inscection procedures to ensure that design requirements are consistently implemented.
- 3. Corrective Steps Which Will be Taken to Avrid Further Violations Following the documentation review we will train personnel to ensure proper ur.derstanding of ?hese requirements. It is anticipated that the above actions will be completed by June 1, 1986.
Quality Surveillance of the activity will be performed by July 2, 1986, to ass 6ss the effectiveness of training.
- 4. Date When Full Compliance Will 8e Achieved The date of full compliance will be June 1, 1986.
Response to Notice of Violation Item E (446/8509-V'-04)
- 1. Reason for the Violations We have confirmed that an Item Removal Notice did not exist for this broken flange joint. Futher investigation did not reveal the reason or the individuals responsible for breaking open this flange joint.
- 2. Corrective Steps Which Have Been Taken and the Results Achieved.
A Non-conformance Report (NCR-M-18697) was written and the flange was repaired. No damage to any equipment resulted from this item.
- 3. Corrective Steps Which Will Be Taken to Avoid Further Violations.
Additional training was prescribed for construction personnel to provide additional emphasis regarding the proper documentation required for work on previously inspected components. This training was completed on February 5, 1986. -
Quality Surveillance of this activity will be performed by March 28, 1986, to assess the effectiveness of training.
- 4. Date When Full Compliance Will Be Achieved.
The date of full compliance was February 5, 1986.
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- I Response to Notica of Deviation Item A (445/8513 D-01) l
- 1. Reason for the Deviation Due.to a misunderstanding of the action plan by the personnel respon-sible for selecting the sample, the intent of the V.d action plan to inspect ASME supports was interpreted as being supports where ASME welding procedures were used during fabrication and erection rather than ASME,NF supports. At the time of the NRC inspection, the third-party overview had focused on the random sampling methodology, the inspection procedure and inspector training, and the initial field inspections.
A project report, which included the list of all pipe supports inspected, w'as in preparation .at the time of the NRC Inspection but had not yet undergone final review, It is quite likely that the devistign identified by the NRC inspection would have been detected by efther the project or the third-party during this final review.
- 2. Corrective Steps Which Have Been Taken and Results Achieved To correct the ide0tif f.ed discrepancy, additional NF pipe supports have been selected and inspected to achieve a sample of 60 ASME-NF supports in each unit.
- 3. Corrective Steps Which Wii. Be Taken to Avoid Further Violations The necessity of completing project checks and third-party overviews of key aspects earlier in the process has been reemphasiged to all affected parties.
- 4. Date When Full Compliance Will be Achieved The full compliance date was February 1, 1984.
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Rerponse to Notice of Deviation Item B (445/8513-D-02) and Item C Based on recent findings by the NRC as exemplified by these items and by Evaluation Research Corporation (ERC), while conducting internal sur-veillance activities, the Senior Review Team (SRT) suspended Quality of Construction (QOC) ISAP VII.c reinspection activities on January 8, 1986. '
The purpose of the suspension of activities was to evaluate the specifics of these two Notices of Deviation items and to assess, specify and imple-ment any necessary corrective actions. Until the ERC evaluation is complete and the SRT has concurred with the results, the specifics of these items cannot be addressed. It is anticipated that the ERC response will be finalized and approved ry the SRT in late February. A response to the spe-cifics of those deviations will be provided to NRC by mid-March 1986.
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