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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
[Table view] |
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TXX-43775 -
(A 'CPPA-42175 (,s . .
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-!rEXAS UTILITIES GENERATING COMi%NY P. o. Box 1002 + C1.EN nose. TEXAS 76043 e
b December- 17, 1984
'Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission
- Washington, D.C. 20555
Subject:
Comanche Peak Steam Electric Stacion Unit No.1 Docket No. 50-445 Texas Utilities Evaluation of the Design / Review Quality Revalidation (DR/QR) Report on the TDI L
Diesel Generators at CPSES Unit 1
References:
- 1. . Letter OGTP-246-0-132 to J. B. George from C.L. Ray, Jr., dated September 7, 1984;
- 2. Letter OGTP-582-0-360 to J.B. George from C.L. Ray, Jr., dated November 21, 1984;
- 3. Letter TXX-4326 (CPPA-41258) to H.R. Denton from J.B. George dated October 5, 1984;
- 4. Letter TXX-4329 (CPPA-41272) to Dr. David
_ Dingee from J.B. George dated October 8, 1984;
- 5. Letter to M.D. Spence from B.J Youngblood dated October 1, 1984;
- 6. Letter 0GTP-176-0-92 to J.B. George frem C.L.
Ray, Jr., dated August 9, 1984.
- 7. Letter OGTP-591-N-48 to H.R. Denton from C.L. Ray, Jr., dated November 27, 1984.
- 8. Letter OGTP-627-N-51 to H.R. Denton from C.L. Ray, Jr. dated December- 11, 1984.
Dear Mr. Denton:
Texas Utilities has recently completed a detailed evaluation of the DR/QR report (Reference 1) prepared by the TDI Diesel Generator Owners' Group for the CPSES Unit i diesel generators, including the revisions proposed in Reference 2. For all practical purposes, the CPSES DR/QR report represents the final results of Phases I and II of the
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TXX-4377' CPPA-42175, .
Owners' Group. program to assess the adequacy of the CPSES Unit 1
' diesel generators to perform their intended safety function. Advance copies of the report were forwarded-to NRC Staff at.d to consultants
'from Pacific Northwest Laboratories (PNL) via References 3 and 4, prior to review by Texas Utilities. Revisions proposed in Reference 2 have been reviewed by Texas Utilities'and comments provided to the
-Owners' Group. Publication of the final DR/Q Owners'Groupiserpectedby_ January 1,1985,peportrevisionbythe and Texas Utilities presumes that.there will be no substantial technical differences from the. proposed revisions. Copies.of the final revision will be forwarded to NRC upon receipt.
The purpose of this letter, therefore, is to provide for NRC and PNL review the results of Texas Utilities' evaluation of the revised,DR/QR
, report, particularly the recommendations made therein to assure reliable diesel generator performance over the life of CPSES Unit 1.
As established in Reference 5, actions taken and commitments made to date.by-Texas Utilities have been sufficient for NRC Staff reviewers of-TDI diesel generator issues to conclude that the Unit i engines are adequate for first cycle operation. A report on Texas Utilities' progress in meeting the. commitments identified in Reference 5 is currently under preparation and will be issued by December 20, 1984.
The DR/QR report recommendations are categorized and discussed as follows:
Recommended modifications to equipment. These are discusaed in Enclosure 1 to this letter;
- Recommended maintenance and surveillance activities. These are discussed in Enclosure 2 to this letter;
, -Recommended baseline vibration testing for the engine, piping, tubing and components (one engine only). Baseline vibration testing has recently been performed per.0wners' Group procedures (Reference 6) as recommended, subject to a restriction to load the engines no higher than 5740 KW (approximately 82 percent of rated capacity) as directed in Reference 5. Baseline data are to be used to identify engine components with unusually high vibration levels and to determine initial vibration characteristics of the engine, thus providing a basis for subsequent trend analysis and comparison with similar engines.
Baseline data will be reduced and evaluated against acceptance criteria established by TD1 and Owners' Group personnel. The Owners' Group will issue a formal report in mid-January, 1985, on engine vibration testing.
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CPPA-42175 ,
Should:there_be any questions or concerns on this matter, please feel free to contact us at any time.
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Vice President / Project General Manager JBG/SMW/1jh Enclosure.
CC: ARMS M.D. Spence-J.T. Merritt J.W. Beck D.H. Wade R.A. Jones
.R.E.-Camp-C.K. Moehlman.
N.S._Reynolds V. Noonan - NRC C~. Berlinger - NRC S. Burwell - NRC D. Persinko - NRC
.C.L.'~ Ray;- Duke /TDI Owners' Group A.P. Cobb.- Duke /TDI Owners' Group B.R. Clements L.F. Fikar-J. ' Stefano ' - NRC K..Trickett - Doe i W. Laity - PNL B.J. Youngblood - NRC
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- 5 Enclosure 1;
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" , .L Results of Texas Utilities- Evaluation of'the CPSES DR/QR Report
'RecommendationsforDgcalGeneratorEquipmentModifications 4
. Texas Utilities concurs with all Owners' Group ~ recommended
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modifications to piping and tubing supports,: couplings and electrical
.controlscas" stated.in the revised CPSES DR/QR; report with the'
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following clarifications: .
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3 -1)l Component CP-102, Generator Controls
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, ..Several options were identifieti in-the report for this
- component.- Texas Utilities (. currently intends to implement.
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. I 'g the y' maintenance: and modification" recommendations
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identified in-Attachment'l to the referenced. component report.: -:However, the -ir.terval for monitoring of the pertinent'sub-components-.has been modified by Texas
(, , .-ytilities as stated in Enclosure 2 to this letter.-
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~ 2) D diimponent-02-455B,' Fuel Oil Strainers-A recommendation was.made for this component to change the size of the fuel. oil. strainers to a coarser design should i
the currently installed strainers require excessive
~ h cleaning.' Based on a-l'ack of problem experience with the installed . strainers during engine operation, Texas Utilities.
74-
/d idoes not intend to replace the strainers, however..this .
. position may be reevaluated if the need arises in the' future.
'ThA.DR/QR equipmEn,t modification recommendations as clarified above will be implmented,: as . applicable, for both CPSES Unit I diesel
. generators. /Except for~ generator ~ control panel modifications, the recommended modifications-will be implemented prior to the restart
'from the.first refueling. outage at CPSES Unit 1. -Generator control ipanels will'be modified prior to exceeding 5% power to enable
' subsequent monitoring of specif,ied sub-components.
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Enclosure 2 Results of Texas Utilities' Evaluation of the CPSES DR/QR
- Recommendations Regarding Maintenance and Surveillance Activities Texas Utilities concurs with all Owners' Group recommended maintenance Kand surveillance activities:as stated in the revised CPSES DR/QR component reports and revised maintenance' matrix, with the following proposed modifications and/or clarifications:
'1) Component F-068,-Intercoolers Item-2 in the revised maintenance matrix recommends-cleaning 1 and inspection of.intercooler shell and tube sides after every refueling outage. Texas Utilities concurs with the
, inspection interval for the tube side, however, it is proposed that the shell side-be comparably inspected at a five (5) year interval, based on a lack of identified problem experience for the shell side.
-2) : Component MP-022/23 Turbochargers Item 2 in the revised maintenance matrix recommends cleaning of the' turbocharger impeller and diffuser'at every refueling outage.- Texas Utilities proposes as a more practical maintenance approach that the impellers and diffusers be inspected every refueling outage and cleaned if necessary.
A supplementary Phase I report on turbocharger nozzle ring assemblies has also been issued by the Owners' Group (Reference 7) which contains the following additional
-Utility recommendations:
a.. At any turbocharger disassembly there should be a visual inspection of nozzle ring components for any apparent damage, failure or apparent mispositioning of vanes. Replace all affected nozzle ring components. During reassembly ensure that capscrews are properly installed with recommended pretorque.
- b. Monitor engine operation to ensure exhaust gas temperatures do not exceed those specified.
Texas Utilities will comply with the utility recommendation a) above during all turbocharger disassemblies and'will perform pre-turbine exhaust temperature monitoring on a monthly basis.
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3)1 : Component 00-420, Lube Oil Pres'sure Regulating Valve-
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Itemil ih the. revised maintenance matrix ~ recommends. valve
, l disassembly and cleaning at every-outage.; Texas Utilities-concurs;-but proposes that the interval be changed to lalternate refueling outages' based-on satisfactoryEindustry experience with this valve.
- 34) Component 02-307B, Lube 011 Fittings,' Internal-
. Texas Utilities' concurs with the recommendation in Item 1 to
, 1 check tubing for dents or crimps at every refueling outage, however.fthis_will-be performed on accessible tubing only.
- 5) ' Component 02-310A,~ Crankshaft
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' Item 2 in the~ revised' maintenance matrix. recommends that all crank journal! diameters be measured at alternate outages.
. Texas Utilities proposes _that a sample'of. main journals be
- . measured at, alternates refueling outages in order to be compatible with the established sampling' frequency for the-main bearing shells (see component 02-310B).
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6 ' Component 02-310B, Main Bearing Shells
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. Item 1 in the. revised maintenance matrix recommends visual-and' dimensional inspection of all main _ bearing shells for:
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evidence-of. wear or misalignment-at the first refueling outage and at-alternate outages thereafter. Texas Utilities-believes .that the minimal problems encountered with the
- CPSES Unit 1 DG main bearing shells do not warrant
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Jinspection to.the degree recommended by the Owners' Group.
n . This position'is in agreement with the assessment by NRC and
'PNL of CPSES main bearingushell experience,was stated on
, pages 5.12 and 5.13 of'PNL-5234 (enclosure to Reference 5).
- 3Y 's , As recommended by NRC andsPNL, Texas Utilities will perform a , a sample inspection of two (2) highly loaded bearings per v engine (bearings 5 and 6) at alternate refueling outages.
Associated caps and saddles will also be checked. The need
, for additional' inspection will be determined by the results of the initial sample inspection. Due to accessibility
, restrictions, inspection of bearings 1, 9, and 10 are to be
_ performed only during an engine teardown (every 5 years).
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.-7) Component 02-310C, Thrust Bearing Ring
~ Item 2'in the revised. maintenance matrix recommends a visual inspection of the thrust bearing for signs of wear-or-degradation concurrently with visual and dimensional main
-bearing shell inspections'as recommended above. However,
- the-main bearing shell inspection frequency has been modified as stated.-above. Texas Utilities proposes that the recommended. visual inspection would be adequate if performed at a five (5) year interval (i.e. at overhauls) since a
" bump check"' for thrust bearing clearance will be performed atrevery refueling outage.
' 8). Component 02-315A, Cylinder Blocks
. Item 1 in the revised maintenance matrix recommends a visual inspection of the cylinder block and eddy-current inspection for stud-to-stud cracks between cylinder heads and for cracks between the block edge and studs at the block ends.
The recommended frequency for the inspection is prior to
-returning the engine to standby service after any period of operation above 50% load.
Texas Utilities agrees that surveillance of the block top g
surfaces to ensure the absence of stud-to-stud cracks and stud-to-edge cracks is appropriate for the first cycle of operation at CPSES Unit 1, until such time as the indications found on Train A, cylinders 4R and SR and on Train B, Cylinder 1R and 4R are reinspected at the first refueling outage. Future inspection requirements should be based on the results of the above inspections and on any additional information provided by the Owners' Group. This position is in agreement with PNL's position in PNL-5234.
Texas Utilities proposes at this time, however, that a visual and boroscopic examination be substituted for the eddy-current technique at the same frequency of performance.
Texas Utilities believes that the use of visual /boroscopic examination will result in greater engine availability and is -justifiable based on the stated conservatism in the Owners' Group assessment of the CPSES block indications as
" ligament cracks" and on the absence of Widmanstaetten graphite in the CPSES cylinder blocks.
The indications in the Train A right bank cylinder block are the largest found at CPSES, but the Owners' Group has concluded that they were casting induced not service induced. The smaller indications in the Train B right bank cylinder block were also determined to be casting defects (by TUGCO) and are-less than 0.050 inches in depth. All of these indications are in lower stress regions of the block top than ligament cracks and are all smaller than ligament cracks.
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- Widmanstaetten graphite is a degenerate microstructure.that'
- reduces the' strength andl fatigue' resistance of: grey cast; -
iron.-:The Owners' Group has~ determined that there is no-
$Widmanstaetten graphite present in-the CPSES Unit I cylinder
? _
O, Jblocks.'
, lThe Ownersf Group'has.' stated in the latest._ Phase I report-
- (reference-8) that blocks which have or are assumed to have
. , ligament! cracks and wnich~.have no Widmanstaetten graphite
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fare capable of. withstanding.a LOOP /LOCA event.with,
- sufficient margin, provided no: stud-to-stud _ or stud-to-edge :
(cracks exist.- Furthermore, engines with.such cracks 'an' c
'still be returned'to standby service provided these cracks are less'than;l -inchesLin depth'from the block top. .
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Because.initiationLof stud-to-stud or' stud-to-end cracks m -
- -occurs at_.the' block top: surface and because they propagate
' - downward,' visual surface- inspection of the block top prior
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sto; returning an engine to service will be adequate to assure
,f :the absence of -such cracks.
LAs required in Reference 5, Texas Utilities will also A ; perform routine: daily visual anspections of the block and-external. surfaces ~during operating' periods, with a more f thorough monthly-inspection under strong lighting (also with
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the engine. operating). As stated above, block indications-are to.be reinspected for propagation at the first refueling
, outage. The cylinder block camshaft; gallery will also be visually inspected at-each' refueling outage.
'9) Component 02-340A, Connecting Rods m
Item 2-in the revised'maintenece matrix recommends inspection and' measurement of connecting rods at 5 year intervals. NRC. requirements in Refersuca 5, however,
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specify a visual inspection of._all rod box etternal surfaces and a bolt preload check at each 200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br /> of ope ation or
'_at 9 months, whichever comes first.
+
Texas Utilities will comply with the requirements specified by NRC in ReferenceL5*for the connecting rods. It is hereby
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.. requested,'however, that the inspection interval be changed N T, .to each 200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br /> of operation or each refueling outage,
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whichever; comes first. Texas Utilities believes that hours
- of operation would have more of an affect on the= likelihood
-of bolt pre-load relaxation than would the passage of time, and'should be the parameter of concern.
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- 9 L10)~ Component-02-34'0B, Connecting Rod Bearing Shells
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(Iten 1:in the= revised maintenance matrix recommends'that I"
-visual endidimensional; inspection of all bearingEshells be
- performed. at the' outage which: precedes 500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> of--
c 1* " ; operation by:st 1 east,the sum of. hours of operation in a
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,- LOOP /LOCA plus the expected hours of operation between
- outages.1 f" , _
- I'nplaceofltheabove. scheme,TexasUtilitieswillperforma
! visual:and. radiographic-examination of-connecting rod bearing shells;for 2 sets of pistonstper engine, as
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fspecified:byiNRC in
Reference:
5,'at;the first. refueling-outaget Lube ~o111 analysis for' contamination will be' fe ; performed'on-a monthly basis, and bearing clearance will be measured .byl" bump ~ check" at every refueling outage. -
- 11)' Component 02-341A, Pistons- =
. Items.I and'2.in the original maintenance matrix recommended visual'and liquid penetrant inspections respectively, for apistons at 5 year intervals. .NRC has specified in Reference
,5 that these inspections also lue performed on 2 sets of epistons at-the first' refueling. outage.
-Texas Utilities has learned-informally through the Owners' Group that substantial positive' operating and inspection data have been gained on Type AE. pistons as a result of a 750 hour0.00868 days <br />0.208 hours <br />0.00124 weeks <br />2.85375e-4 months <br />'run on.an AE-equipped engine at Shoreham Nuclear Power Station. The Owners' Group has also proposed deleting
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.the' liquid penetrant-inspection in a revision to the maintenance matrix.: Based on this information, it is
_ ,possible that concerns with regard to AE pistons may be eliminated in theLnear future. Therefore, Texas' Utilities s -hereby; defers commitment to an inspection of AE pistons and
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' requests that NRC reevaluate the-need for such inspections-
, in lightaof this information.
12)- Component 02-350A, Cam Shaft Assembly D
J Item 1 in the original maintenance matrix recommended visual
-inspection of all cam lobe surfaces at 5 year intervals. -
-while the component report specifies inspection at each p?t' ~ _ outage. The Owners' Group has revised the frequency in the
.% maintenance matrix to agree with the component report
- frequency.. This is in conformance with NRC requirements 1" '
specified'in Reference 5 and the inspection will be performed by Texas Utilities at each refueling outage.
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9-13). Component 02-380A, Exhaust Manifold Item 1_in the revised' maintenance matrix recommends magnetic particle examination of_a sample'of circumferential pipe -
welds and' corresponding heat affected zones at the first-refueling outage and at. alternate refueling outages thereafter.
Texas Utilities proposes to visually examine all accessible
- welds at'the frequency given above,-instead of a sample of magnetic particle tests. It is felt that this procedure would provide a more practical approach with broader weld inspection coverage.
14)' Component 02-387A, Crankcase Vacuum Fan Item 1 in the revised maintenance matrix recommends cleaning and inspection of the fan at alternate outages. Texas Utilities proposes, as a more practical-approach, that the
, fan be inspected at alternate refueling outages with cleaning as necessary.
- 15) Component 02-390E, Rocker Arm Bushings Item 1 in the revised maintenance matrix recommends visual and dimensional inspection of intake rocker arm bushings at the outage which precedes 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br /> of operation by at least the sum of expected hours of operation in a LOOP /LOCA plus the expected hours of operation between outages.-
However, NRC has concurred in Reference 5 with Texas Utilities earlier proposal to visually inspect rocker arms at each refueling outage.
Based on the above, Texas Utilities will perform a visual inspection of the intake rocker arms at every refueling outage, and will measure them every 5 years during overhauls.
- 16) Component 02-410A, Overspeed Trip Covernor Recommended settings will be reviewed to ensure compatibility with the Texas Utilities' grid system requirements and may be adjusted accordingly.
- 17) Component 02-410C, Overspeed Trip Drive Couplings
. Item 3 in the maintenance matrix recommends that the present L-110 Lovejoy couplings be replaced with new units at the next outage, per TDI Service Information Memo (SIM) 363.
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Texas Utilities does not intend to replace these couplings at the first refueling outage because they were already replaced per SIM 363 instructions.
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(18)- Chaponent 02 1413A,1 Governor Linkage-
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- Itemil in_the original maintenance matrix recommends that-
. bolt; heads and; roll pins be -lockwired. - , The10wners ' ' Group -
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Jhas revised this-item-to read: " Install positive locking-
- hardware to the lever arm? clamp-bolt heads and shaft rolli pins."'
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(Texa's' Utilities will-install;1ockwire on all fasteners
- designedifor use with lockwire.. Other_ locking hardware will be installed'where specified.
" - 19) ' Component 02-415A, Woodward Governor i
.1 . Recommended settings will be revi+wed to ensure
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. compatibility with the Texas Utilities grid system
, requirements : and may be adjusted accordingly.
20)j : Component 02-5000, Breakers & Contact Blocks Item 3-in=the revised maintenance matrix recommends that
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- circuit breakers be- trip'-checked at each outage. Texas Utilities: believes that breakers'of the molded' case type 7 -<7 lshould-not.be-tested =at frequent intervals and proposes to'
- perform this test every 5 years for-this type.of breaker.
Other.. types of breakers would be tested at each refueling outage as recommended.
~221)_ Components 02-525B, C, Barring Device Controls & Filter R Because~the barring device is not required during engine.
_ operation, the Owners' Group recommendations for the
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. associated components may.not'necessarily be incorporated by.
Texas Utilities,1but will.be taken into consideration.
- 22) . Component 02-717C, Jacket Water Piping, Couplings, Fittings, Orifices & Y-Strainers-The DR/QR component report recommends that flanges be torqued per the general' torque tables in the TDI Instruction Manual. Texas Utilities flange torquing procedure provides for greater torque than the general torque tables and will provide adequate load transfer to
. attaching-supports.
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23).LComponent 02-717G,'K, Lube 011' Valves and Fuel 011 Valves
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, :1ubeloi1 valve: component report" specifies a 5; year interval fforfchecking lift pressure and the: fuel: oil valve component freport does not address:liftipressure at all...lk revision.to the; maintenance. matrix has been proposed by the.0wners'
, 7 roup, G however,'.which sets ~the interval for. checking-lift Jpressure on lube oil?and fuel' oil relief valves at 5 year
? intervals.7 Texas; Utilities will comply with theLrevised
-recommendation.
'24) L Component 02-810E,' Jacket Water' Heaters
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'The Owner' Group recommends in the revised ~ maintenance
- matrix that'the:following.be performed at each outage: 1)
. measure heater: insulation, resistance, 2) inspect and clean e v _ heater elements, and'3); check calibration and inspect 1
' thermostat. However, this recommendation appears to be earbitrary in thatuit is not based on either~a design review orfon adverse component experience according to the
. component report. Texas Utilities believes that the
' activities recommended above would be adequate if performed Lat' alternate refueling outages and intends to implement that interval.
l 25) . . component 02-820A, Lube Oil Sump Tank Heaters -
- The Owners' Group recommends that heater insulation resistance be measured and that thermostats be checked and-calibratediat ev'ery outage. Based on satisfactory
" experience with these heaters, however, Texas Utilities proposes that these activities be performed at alternate
. refueling outages. The heater elements will be inspected at
. every refueling outage in conjunction with the tank inspection, as recommended.
j . ,26) Component CP-102, Generator Controls
, Items 6, 7 and 8 in the revised maintenance matrix recommend monthly inspection of temperature sensitive tape and Glyptol lacquer that are to be applied to several control panel
- components. The tape is also'specified to be' examined before and after each running of the engine.
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- Texas Utilities believes-that. operating experience with the ,
subject components at CPSES Unit 1-has been extremely-
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nc positive and does not warrant inspection at.the recommended, frequency.- No overheating or vibration problems, which the recommended measures are, designed to' detect -have-been Jencountered-with'these components even during extended full.
. f load runs of. the . ' engines. : On this basis, Texas Utilities
, proposes:that'the inspection be; performed at each refueling outage.
The DR/QR' maintenance an'd surveillance activities recommended by
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-the'0wners' Group are to be incorporated into the CPSES Unit 1
. diesel generator. preventive maintenance and surveillance program,
'as: modified and/or' clarified above,as follows:
Monthly and; daily surveillance and maintenance items are to be' incorporated into the surveillance or~ maintenance programs prior to. exceeding 5% power at CPSES Unit 1. Items based on number'of' engine starts or hours of operation, as w211 as 18 month surveillance items, are included in this
' category.
-Surveillance-and maintenance items which are to be l accomplished on a refueling outage or longer ~ basis will be incorporated into the appropriate programs prior to the first. refueling outage.
.It should be noted, however, that evolution of the maintenance and: surveillance program can be expected to occur based on c cimplementation feedback. inspection results and on additional
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input from NRC, the'0wners' Group,'TDI or othe applicable
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sources.- Also,' variations in the methods of achieving the intent-of the recommendations may be necessary'upon implementation in L
order to provide a practical approach to maintenance. NRC is
'hereby requested to provide guidance on the' subject of possible future changes (both major and minor) to the programs for the reasons stated above, particularly regarding NRC notification of prospective changes.
Finally, the TDI inspection and maintenance forms referenced in the " Comments" section-of the maintenance matrix may or may not be used in the performance of the recommended activities.
-Maintenance instructions and procedures will specify which forms are to be used, if any, for a specified activity.
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