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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:ENGINEERING/CONSTRUCTION/CONSULTING FIRM TO NRC
MONTHYEARML20011E4561989-10-24024 October 1989 Concludes That No Statements or Conclusions of SALP Board in Conflict W/Or Run Counter to Findings Resulting from Insp of Plant Operations Exist ML20247P9411989-05-17017 May 1989 FOIA Request for Final Open Item Transmittal Ltrs Per NRC Insp Procedure 94300B for Listed Plants ML20245A5381989-04-12012 April 1989 Forwards Rev 0 to TR-84056-01, Independent Assessment Program for Comanche Peak Electric Station Final Rept, Vols 1-3 ML20196C4471988-01-21021 January 1988 FOIA Request for Documents Re NRC Review & Evaluation of Comanche Peak Safe Team During 1985 to Present ML20150D3871988-01-21021 January 1988 Update to FOIA Request for Documents Re Plant Sser 5 ML20148H0331988-01-18018 January 1988 FOIA Request for Documents Re Rept on Performance of Region IV in Inspecting Util ML20149J2841988-01-0404 January 1988 Requests Listed Address Change for Comanche Peak Project Correspondence List ML20234D7461987-12-23023 December 1987 FOIA Request for NRC Internal Correspondence Dtd After 861126 Re Ofc of Inspector & Auditor Investigation of Allegations of Misconduct by Region IV Mgt Concerning Plant ML20150D3801987-12-16016 December 1987 FOIA Request for Documents Re Plant Sser 5 ML20235A1251987-12-16016 December 1987 Forwards Info Re Resource Technical Svcs,Inc,Including Summary of NRC Contract Work,Nrc Form 26 for Three Existing Contracts,Audit Info,Work History & Lists of Expertise Available for Special Insps & of Current Resource Svcs ML20147G7251987-12-16016 December 1987 FOIA Request for Documents Re Region IV Status Repts on Plant Readiness for OL & Region IV Yearly Operating Plans & Self Evaluations for 1974-87 ML20196H0191987-09-30030 September 1987 FOIA Request for Documents Listed on Encl App Re Response to Notice of Violation ML20237K0581987-08-12012 August 1987 Advises of Util Agreement to Pay Litigation Costs for Ob Cannon & Son,Inc.Util Will Also Retain Ob Cannon & Son, Inc to Perform Coating Applications to Plant Svc Water Sys ML20235U7051987-07-16016 July 1987 Forwards Technical Rept TR-6710-3, Comanche Peak Response Team Results Rept Rev 1 for Issue Specific Action Plan Isap I.d.2 Guidelines for Administration of QC Inspector Tests ML20235V8351987-07-16016 July 1987 Forwards Technical Rept TR-6710-2, Comanche Peak Response Team Results Rept Rev 1 for Issue Specific Action Plan Isap VII.a.4 Audit Program & Auditor Qualifications ML20237J1791987-07-0606 July 1987 FOIA Request for Insp Rept 50-445/84-14 ML20237J5031987-07-0303 July 1987 FOIA Request for Listed Documents Re Comanche Peak Insp & Related Correspondence ML20237H6781987-06-25025 June 1987 FOIA Request for Insp Repts 50-445/81-94,50-445/82-28, 50-445/83-05,50-445/83-42,50-445/83-45,50-445/87-01, 50-445/87-04 & 50-445/81-05.Last Rept,Requested in FOIA Request 87-119,not Obtained Due to Accession Number Error ML20215M1401987-05-0808 May 1987 Forwards EGG-NTA-7701, TMI Action-NUREG-0737 (II.D.1), Comanche Peak Steam Electric Station Unit 1, Technical Evaluation Rept.Licensee Provided Acceptable Submittals Reconfirming That Listed GDC of App a to 10CFR50 Met ML20214R4221987-03-19019 March 1987 Forwards Conformance to Generic Ltr 83-28,Item 2.2.2- Vendor Interface Programs for All Other Safety-Related Components:Comanche Peak-1 & -2, Final Informal Technical Evaluation Rept.Facility Conforms to Subj Generic Ltr ML20212N8371987-02-20020 February 1987 FOIA Request for Insp Repts 50-445/81-05,73-01,75-02 & 78-06 & 50-446/81-05,73-01,75-02 & 78-06 ML20203D7201986-07-0202 July 1986 Forwards Jj Rivard Internal Memo Re Audit of Facility Train C Conduit Program at Impell Corp Walnut Creek,Ca Ofc ML20203D5381986-07-0202 July 1986 Forwards EA Solla 860702 Memo Re 860609 Audit of Impell Cable Tray Reanalysis Effort ML20203D4121986-07-0101 July 1986 Forwards Trip Rept 2236 Re 860428-0501 Safety Significance Evaluation Audit at Comanche Peak ML20211H0731986-06-18018 June 1986 Forwards Review of safety-significant Evaluations (SSE) of Const Deviations in Civil/Structural Populations.Tentative Schedule for SSE & App P Issues Deemed Inappropriate Based on Current Contractual Requirements ML20210D8801986-05-16016 May 1986 Forwards Addl Comments Re Draft Sser 13 Sent on 860514 ML20210R2111986-05-14014 May 1986 Forwards Preliminary Comments on May 1986 Draft Sser 13, Sections 1 & 3.Sentence on Pages 1-4,1-7,3-1 & 3-5 Most Appropriately Worded on Page 1-7.Last Word in Paragraph on Page 1-6 Re Generic Implications Should Be Deficiencies ML20141M8201986-02-11011 February 1986 Forwards Rev 0 to Audit Plan,Comanche Peak Steam Electric Station,Cable Tray & Conduit Support Reanalysis,Project 6410. Audit Meeting W/Ebasco Svcs,Inc Scheduled for End of Current Wk ML20137U7091986-01-31031 January 1986 Forwards Trip Repts 2201 & 2202 Re Robert L Cloud & Assoc & Impell Corp Audits of Facility Cable Tray & Support Activities ML20210B2071986-01-30030 January 1986 Forwards Early Inputs for Next Rev to Sser on Facility Program Plan.Encls Do Not Fully Reflect Evaluation Due to Late Receipt of Rev 3 to Program Plan.More Input Will Be Provided at 860303 Meeting ML20141G4411986-01-0707 January 1986 Supports Use of ASME Code Cases N-397 & N-411 for Seismic Analysis of Piping at Facility.Comments on Util 851118 Request to Use Codes Listed ML20137G6231985-12-27027 December 1985 Forwards Preliminary Trip Rept 2191 of 851203-06 Site Visit Re Audit of Comanche Peak Review Team Item Vii.C on Const Reinsp/Documentation Review Plan ML20137G7601985-12-27027 December 1985 Forwards Preliminary Trip Repts 2186a of 851113-14 & 20-22 Site Visits & 2190a of 851206 Visit to S&W ML20210A7741985-12-23023 December 1985 Submits List of Portions of Draft SER Transmitted to Date by Teledyne.Portions Focus on Comanche Peak Review Team Program Plan,Design Adequacy Program Plan & Const Adequacy Program Plan.Listed Info Will Be Provided Later ML20138N9371985-12-18018 December 1985 Forwards Draft Trip Rept of 851211 & 12 Visit to Facility to Audit Walkdown of Cable Trays ML20138H4991985-12-12012 December 1985 Forwards Preliminary Trip Rept of 851205 Visit to Plant Re Results of NRC Audit Walkdown on Unit 1 Cable Tray Supports. List of Attendees Also Encl ML20138Q4111985-12-11011 December 1985 Forwards Preliminary Trip Rept of 851126 Visit to Ebasco in New York,Ny Re Audit of Util Presentation, Slenderness Ratio Limitations for Cable Tray Hanger Type Supports. Viewgraphs Encl ML20138D2801985-12-10010 December 1985 Forwards Trip Rept 2182 of 851118-22 Visit to Facility to Review Work Performed by Util & Ebasco to Verify Accuracy of as-built Data Used for Input to Cable Tray Design Verification ML20137G5671985-11-22022 November 1985 Forwards Preliminary Trip Rept 2179 of 851106 Site Visit Re Cable Tray Hanger Program Audit Insp.Viewgraphs Encl ML20137G6161985-11-21021 November 1985 Forwards Draft Trip Rept 2178 of Ja Flaherty & Jj Rivard 851029-31 Visit to Comanche Peak for Audit of Const Reinsp/ Documentation Review Plan ML20137G5361985-11-21021 November 1985 Forwards Preliminary Draft Trip Rept 2172 of 851108 Meeting W/Ebasco Re Cable Tray Hanger & Seismic Design Procedures & Draft Trip Rept 2175 of 851112-14 Meeting W/Corporate Consultating Development Co in Apex,Nc Re Clamp Testing ML20215E9661985-08-12012 August 1985 Forwards QA Mgt Review Board Qamrb Audit 3 Rept,780605-23, Per 850812 Telcon. Critique of Third Annual Mgt Audit Conducted for Brown & Root,Inc... & MAC-79-G021, Critique of Fourth Annual Mgt Audit..., Also Encl ML20215E9321985-08-0606 August 1985 Forwards MAC-77-66, Final Rept,Mgt Audit of Brown & Root QA Program,770509-20, Per 850729 Request ML20133H5901985-07-31031 July 1985 Forwards Comments on Draft Input to SER Re Program Plan & Rev 2 to Issue Specific Action Plans,Per 850731 Request. Balance of Comments Will Be Reserved for Reviewing Checks Which Will Be Submitted at Later Date ML20210C5901985-07-29029 July 1985 Forwards Teledyne Engineering Svcs Technical Rept TR-6410-1, Executive Summary Technical Evaluation Rept on Comanche Peak Response Team Program Plan & Issue-Specific Action Plans,Rev 2, Books 1 & 2 ML20140F6901985-06-27027 June 1985 Forwards Page 20,324,inadvertently Omitted from Original 841121 Transcript ML20128G4261985-05-20020 May 1985 Forwards Resumes for Electrical & Mechanical Sys Project Personnel & Representative Sample of Other Vendor Personnel Available for Technical Support for Independent Assessment Program-Phases 2 & 4,per 850426 Meeting ML20128F3751985-05-0303 May 1985 Forwards Preliminary Rev 0 to App Q, Electrical Walkdown Checklist & Rev 0 to App V, Mechanical Sys Walkdown Checklists, to TR-84056-01, Independent Assessment Program,Phase 4 ML20127P5761985-04-29029 April 1985 Forwards Rev 1 to DC-5, Independent Assessment Program Electrical Sys Review Criteria,Phase IV, Rev 1 to DC-4, ...Mechanical Design Review Criteria & App N to Rev 0 to TR-84056-01, Independent Assessment Program,Phase 4 ML20128K1021985-03-0808 March 1985 Responds to Two Remaining Questions Re NRC Review of Independent Assessment Program,Phases 1 & 2,concerning Cable Tray Const Drawings.Discrepancies Between Design & Fabrication Drawings Encl.Nh Williams Encl 1989-05-17
[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
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.' 'RTELEDYNE ENGNEERING SERVICES 130 SECOND AVENUE WALTHAM, MASSACHUSETTS 02254 (617) 890-3350 TWX (710) 324-7508 December 12, 1985 6410-26 Eb- H S 664 4G ,
Mr. Vince Noonan, Project Director Comanche Peak Project U. S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Division of Licensing Mail Stop P-234 Washington, D. C. 20555
Dear Mr. Noonan:
Attached please find our preliminary Trip Report for our visit to Comanche Peak Steam Electric Station to discuss -the results of the NRC audit walkdown on the Unit 1 Cable Tray Supports.
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! If you have any questions please do not hesitate to contact me.
Very truly yours, TELEDYNE ENGINEERING SERVICES A $
Donald F. Landers Executive Vice President DFL/lh Attachment (TripReportNo.2188) cc: L. Shao (USNRC)
C. Trammell (USNRC)
C. Poslusny (USRNC)
D. Jeng (USNRC) 6410 File (TES)
ADD:
PWR = A/RC's TECH SUPPORT AD - J. Knight titr on13 )
8512170222 851212 PDR \
A ADOCK 05000445 UcN^In"o"Us PDR rsa (cAxxrLt) p' g"gg8 $
g ENGINEEHS AND METALLURGISTS
"#TELEDYNE ENGINEERING SERVCES TRIP REPORT N0. 2188 VIST TO COMANCHE PEAK STEAM ELECTRIC STATION.
DECEMBER 5, 1985 On Thursday December 5,1985 a meeting was held with TUCG0
.to discuss the results of the NRC audit walkdown on the unit I cable tray supports. A list of those in attendance is shown in attachment 1. TUCG0 has stopped the walkdowns and is currently revising the walkdown procedures. The causes of the NRC findings are being investigated and appropriate corrective action will be taken. Previously the walkdown teams consisted of a QC inspector and an engineer. The QC inspector and the engineer will now be split up into two walkdown teams.
TERA was asked if their review included looking at the walkdowns. They responded that they were reviewing the procedures but that implementation was not part of the current scope. They are considering, as a result of these findings, to include the implimentation in their scope.
As a result of the NRC findings TUCG0 has sent level III inspectors out to~ walkdown the supports in which we had findings.
The following is a list of'TUCG0 responses to the findings found during the NRC audit November 18 - 22, 1985.
1.. CTH-1-5817: (a) Bottom two teirs are 1 member size smaller than what is shown on the drawing.
(b) Tray 1 is a 4" x 24" not a 4" x 12" as shown on the drawing.
(c) Tray 2 is a 4" x 24" not IA as shown on the drawing.
(d) Bolts G1 & G2 are given as type " BEVEL".
Actual type is A307 & A449.
(e) Conduit #11 span is too short.
TUCG0 Response:
(a) By measuring the webs the members were found to be the correct size. The differance in the flange widths is due to the mill tolerances on the steel. This item needs further investigation.
(b) Agree with finding.
(c) Accessability is defined as accesable at the tray. Since the tray was wrapped in a thermal blanket at the support it was marked IA.
The thermal blanket ended just after the support at which point the tray size could be measured but since this would involve the use of engineering judgement, which is not allowed in the procedure, the tray size is marked IA.
(d) Agree with finding.
(e) Agree with finding.
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- 2. CTH-1-5787: (a) Angle under tray.was given as 3-1/2" x 2-1/2" x 5/16 with the 2-1/2" marked-IA. Angle is
.actually 3-1/2" x 5" x 7/16". .
(b) Weld of angle to baseplate marked IA but only weld on leg under tray was inaccesable the other leg was accesable.
TUCG0 Response:
(a) Agree with finding.
(b) Agree with finding.
- 3. CTH-1-239: (a) Span lengths incorrect. 4" dimension is 12" & 4'-0" dimension is 4'-10".
(b) Bolt G dimensions given as 2-13/16" &
2-5/8" but-actually measure as 2-1/2 8 2-3/4.
TUCG0 Response:
(a) Agree with f.inding.
(b) Agree with finding.
- 4. CTH-1-42: (a) Bolt #1 G dim given as 2-1/8", actual dimension is 3-1/8".
(b) Welds #4 & 8 are written up as U.S measuring,3/16". Actual measurement is 1/4" which
what was called for.
(c) Tray clamps 3 & 4 marked IA but have beveld washers on them.
TUCG0 Response:
(a) Agree with finding.
(b) Agree with finding.
(c) According to the procedure the clamp and bolt are to be treated as a unit and since the clamp was inaccessable the bolts. and washers were also marked IA.
l S. 'CTH-1-12075: (a) Tray clamp is shown as Type B, 1/2"
~
' plate welded to channel. Actual tray clamp is Type C, botled to channel.
(b) Weld symbol of channel to angle is reversed.
TUCG0 Response:
(a) Agree with finding.
(b) Agree with finding. 1
- 6. CTH-1-5942: (a) Weld #1 arrow side is given as 5/16" but measures 1/4". ,
(b) Channel C4x5.4 is actually a C4x7.25. l (c) 7-5/8" dimension to edge of column is l actually 8-5/8". '
TUCG0 Response:
(a) Agree with finding.
(b) Agree with finding.
(c) Agree with finding.
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SPTFIC0YNE i ENGINEERING SERVCES l
.7. CTP 636: (a) Weld #1 measures 1/4" both sides. ,
Drawing shows 1/4" NS and 3/16" FS.
TUCG0 Response:
(a) TUCG0 inspectors found weld to be undersized for 27% of its length which is greater than 25% therefore the weld is unsat as shown in the
, walkdown.
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- 8. 'CTH 6_07: (a) Support is marked inaccesable but base plate are accesable for-dimensioning.
TUCG0 Response:
(a) TUCG0 did not know about this item.
- 9. CTH-1-1853:_ (a) Weld sizes for top of angle brace are given backwards.
(b) Gap under Richmond Insert is greater '
than 1/16" TUCG0 Response:
(a) Agree with finding.
(b) Copy of inspection report that was used for the walkdown was not the latest inspection report.
~
The latest inspection report contains the gap discrepancy.
- 10. CTH-1-1716: (a) Bolt #2 has 2-3/4" projection given. /
Actual projection 2-3/8".
TUCG0' Response:
(a) Agree with finding. Problems with bolt projections are due to techniques used to measure the projections. Since the procedure does not define the -
method to be used many different methods may have been used. The next revision to the walkdown procedure will clearly outline the method of measuring the bolt
. projection.
- 11. CTH-1-1845: (a) Bolt Projections 3-3/4" & 3-3/8"-given.
Actual projections are 3" & 2-3/4".
(b) Tray clamp G1 contains no bolt and Wdsher as called out in table. G1 is a Type B (welded) clamp.
(c) Tray clamp G2 contains a bevel and flat washer. Table shows only bevel washer.
(d) Angle at wall rotated 90 deg.
(e) Dimension against wall between attachments is wrong.
(f) Dimension of W.P. in det A is wrong.
(g) Weld size in Det B is given as 1/2".
Actual weld size is 3/16".
"RTACTT(NE ENGINEERING SERVICES TUCG0 Response:
(a) Agree with finding.
~ (b) Agree with finding.
(c) Agree with finding.
(d) Agree with finding.
(e) Agree with finding.
(f) Agree with finding.
(g) Agree with finding, but measure 1/4".
- 12. CTH-1-5517: (a) Weld #1 arrowside udersized 5/16" - 1/4".
(b) Tray size marked IA due to thermal blanket.
Just down from support tray was accesable. Tray measures 18" x 4".
(c) Weld #5 & 6 Q.C. marked unsat for undersized were found to be OK.
(d) The end prep on a bevel weld was found to i be undersized. l
- '(e) Plate size on clamp given as 1/2" x 3-3/4" f- x 6" measures 1/2" x'4-1/4" x 6".
i TUCG0 Response:
(a) Agree with findir.g.
l (b) See response 1 (c).
(c) Agree with finding.
,. (d) This attribute was not being checked for L
at'this support.
(e) Agree with finding. The measurement tolerances included in the walkdown procedure did not apply to redlined dimensions but in the next revision
[ they will apply. The discrepancy on the plate tolerance is within these tolerances.
- 13. 'CTH-1-5488: (a) Dimension from B.0.C. to top of vertical channel. Dwg called for 2'-6" (max) dimension was deleted.
(b) Weld #1 far side undersized. 5/16" called out, Q.C. called unsat to 1/4", actually measur'ed
. 3/16".
TUCG0 Response:
(a) Deleted dimension was added on a different section which was uncicar due to copying.
(b) Agree with finding.
- 14. CTH-1-7047: (a)' Bolt projections found to be different.
Walkdown NRC Bolt #1 2-1/2" 2-1/4" Bolt #2 1-7/8" 1-5/8" Bolt #3 2-11/16" 2-1/2"
.TUCG0 Response:
(a) Disagree with finding. See response to item 10 (a).
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- 15. CTH-1-1963: (a) 5'-1" dimension measures 4'-10".
(b) Weld #2 weld length called out as 3/4".
Actual weld lengths are 3-1/4".
(c) Plate size 6-3/4"lg measures 6-1/2".
TUCG0 Response:
(a) Agree with finding.
(b) This problem is due to unclear copies.
Original has 3-1/4" for weld length..
(c) This plate is skewed and tough to get an accurate measurement on. However the discrepancy will be_within the tolerance of the procedure.
- 16. CTH-1-5538: (a) Bevel on penetration weld found to be incorrect.-
TUCG0 Response:
(a) Agree with finding.
- 17. CTH-1-4738: (a) Weld #1 is udersized.
TUCG0 Response:
(a) TUGC0 inspectors disagree however said part of weld was inaccesable. The discrepancy in weld size was found in the area they said was inaccesable.
This ' item needs further investigation.
- 18. CTH-1-6631: (a) Weld undercut.
(b) Std. hex nuts found in lieu of heavy hex nuts.
TUCG0 Response:
(a) This attribute was not looked at for this support. -
(b) This attribute was not checked. Since this is a bearing connection the size of the nut has no
! effect on the strength of the connection.
- 19. CTH-1-5976: (a) 3" dimension from back of channel to edge of plate.was measured at 3-1/4" (b) Projection of bolt #1 given as 3-1/2" was measured as 3".
TUCG0 Response:-
(a) Agree with finding.
(b) See response 10 (a).
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ENGINEERING SERVICES In the afternoon a meeting was held with Region I to find out what procedures they used for there walkdown. Region I used the VWAC procedure for performing the walkdown-on September 9 -
10, 1985. Region IV performed there walkdown as per. TUCG0 procedures that were used by TUCG0 for there walkdowns.
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Eric A Solla EAS Enclosures' cc: DFL-JAF WJC TRIP REPORT FILE 9
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ENGINEERING SERVIOES Attachment 1 Cable Tray Meeting 12/5/85
. Name Organization Terry Langowski NRC/TRT Bob Philleo TRT Tom Brandt- TUGC0 QA Philip Halstead TUGC0 QA J. S. Marshall TUGC0 LIC R. E. Camp IMPELL - PROJ MGR Victor Ferrarini NRC/TRT Jim Dale NRC/RIV David C. Jeng NRC/TRT Howard A. Levin CPRT/RTL Larry Shoa NRC Thomas F. Westerman NRC/RIV Eric Solla NRC/TES C. R..Hooton
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TUCG0 R. M. Kissinger TUCG0 W. F. Rockwell EBASCO Ronald A. Muldoon EBASCO John Vorderbeneggem IMPELL H. A. Harrison TUCG0 9
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