ML20235J165
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Initiation
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Other: 0CAN048804, Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Informs That No Instances of Circuit Breakers Being Installed in safety-related Applications Identified at Plant, 3F0288-18, Responds to NRC Bulletin 88-001 Re Defects in Westinghouse Circuit Breakers.Plant Does Not Use Westinghouse Circuit Breaker Models DS-206,DSL-206,DS-416,DSL-416 & DS-420, A07039, Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Pole Shafts for All Four Breakers Replaced During Recently Completed Refueling Outage, BECO-88-050, Notifies That Westinghouse Circuit Breakers Not in Use or Planned to Be Used in safety-related Applications at Util, in Response to NRC Bulletin 88-001, ML20147F998, ML20147G854, ML20148A890, ML20148B666, ML20148K225, ML20148Q724, ML20149M198, ML20150A899, ML20150B182, ML20150B526, ML20150C407, ML20150D397, ML20151A945, ML20151B202, ML20151E018, ML20151E419, ML20151E868, ML20151G115, ML20151G791, ML20151H779, ML20151H965, ML20151Q920, ML20154D233, ML20154E154, ML20155A456, ML20155E392, ML20196H353, ML20205P688, ML20235J165, ML20235J168, ML20236A614, ML20236A849, ML20236D105, ML20236F547, ML20236S018, ML20247K075, NRC-88-0072, Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Util Does Not Utilize Subj Circuit Breakers, RBG-27645, Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Util Does Not Utilize Any Circuit Breakers Subj to Bulletin in Class 1E Svc at Plant, W3P88-0051, Responds to NRC Bulletin 88-001 Re Defects in Westinghouse Circuit Breakers.Util Does Not Use Westinghouse Series Ds Circuit Breakers & Not Subj to Insps Requested in Bulletin | |
MONTHYEARML20235S2971987-10-0202 October 1987
[Table View]Summary of 870923 Meeting W/Westinghouse Re Technical Basis for Westinghouse Recommended Actions,Criteria & Conclusions in to Utils That Use Models DS-416,DSL-416, DS-420,DS-206 & DSL-206 Switchgear in Class 1E Svc Project stage: Meeting ML20236A6141987-10-16016 October 1987 Advises That Util Insp of Reactor Trip Breakers Revealed Catawba Pole Shaft Which Had Welds W/Indications of Cracking.Forwards Informal Technical Communication from Franklin Research Ctr Re Initial Observation Project stage: Other ML20236A8491987-10-16016 October 1987 Forwards I.6177-5-1, Interim Rept on McGuire Reactor Trip Breaker 2B Failure Evaluation & Rcommended Corrective Actions from Westingtonhouse. Rept Explains Mechanical Binding Which Kept Breaker from Opening on 870702 Project stage: Other ML20236D1051987-10-21021 October 1987 Provides Record of 871020 Telcon Between D Hood,D Sellers & V Hodge of NRC & J Mcvicker & Cowne of Bg&E Re Unit 1 480 Volt Circuit Breaker W/Broken Weldment Connecting Ctr Pole Lever to Pole Shaft.Util Exam Results in 860918 Memo Project stage: Other ML20236F5471987-10-23023 October 1987 Documents 871020 Telcon W/Util Re Unit 2 Circuit Breaker Pole Shaft Weld Failure Project stage: Other ML20236F9651987-10-27027 October 1987 Notification of 871103 Meeting W/Util & Westinghouse in Philadelphia,Pa to Discuss Results of Franklin Research Ctr Exam of Cracks in Pole Shaft Welds of Reactor Trip Breaker Project stage: Meeting ML20236S0181987-11-18018 November 1987 Summarizes 871020 Telcon Between NRC & Util Re Two Broken Fillet Welds on Pole Shaft Assembly of Circuit Breaker That Energizes Emergency Fire Protection Pumps for Facility. Photographs Attached to 870710 Memo to NRC Encl Project stage: Other ML20149M1981988-02-16016 February 1988 Advises That Since Util No Longer Operating Reactor Licensee Due to 870430 Shutdown & 870804 Amend,Modifying License DPR-45 to Possess But Not Operate Status,Generic Ltr 88-01 Determined Inapplicable to Facility Project stage: Other 3F0288-18, Responds to NRC Bulletin 88-001 Re Defects in Westinghouse Circuit Breakers.Plant Does Not Use Westinghouse Circuit Breaker Models DS-206,DSL-206,DS-416,DSL-416 & DS-4201988-02-23023 February 1988 Responds to NRC Bulletin 88-001 Re Defects in Westinghouse Circuit Breakers.Plant Does Not Use Westinghouse Circuit Breaker Models DS-206,DSL-206,DS-416,DSL-416 & DS-420 Project stage: Other ML20196H3531988-02-25025 February 1988 Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. No Westinghouse Ds Series Circuit Breakers Installed at Facility Project stage: Other ML20147G8541988-03-0101 March 1988 Responds to NRC Bulletin 88-001 Re Westinghouse Ds Series Circuit Breakers Used in safety-related Applications.Plant Does Not Have Any Westinghouse Ds Series Circuit Breakers Project stage: Other ML20147F9981988-03-0404 March 1988 Submits Response to NRC Bulletin 88-001 Re Defects in Westinghouse Circuit Breakers.Author Does Not Utilize Any Westinghouse Circuit Breakers,As Identified in Subj Bulletin,In Class 1E Applications at Facility Project stage: Other ML20150B1821988-03-0707 March 1988 Responds to NRC Bulletin 88-001 Re Defects in Westinghouse Circuit Breakers.Plant Does Not Use Westinghouse Circuit Breakers in Class 1E Applications So Bulletin 88-001 Does Not Apply to Plant Project stage: Other ML20148A8901988-03-0707 March 1988 Responds to NRC Bulletin 88-001 Re Defects in Westinghouse Circuit Breakers.Unit 1 Has No Westinghouse Ds Circuit Breakers Used in Class 1E Application.Unit 2 Reactor Trip & Bypass Breakers Insp Initiated Per Info Notice 87-035 Project stage: Other ML20150A8991988-03-0909 March 1988 Provides Response to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Util Determined That Westinghouse Series Ds Circuit Breakers Not Employed at Plant.Insp Required by Bulletin Not Applicable to Plant Project stage: Other ML20150C4071988-03-11011 March 1988 Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Util Determined That Westinghouse Type Ds Circuit Breakers Not Used at Plant Project stage: Other BECO-88-050, Notifies That Westinghouse Circuit Breakers Not in Use or Planned to Be Used in safety-related Applications at Util, in Response to NRC Bulletin 88-0011988-03-15015 March 1988 Notifies That Westinghouse Circuit Breakers Not in Use or Planned to Be Used in safety-related Applications at Util, in Response to NRC Bulletin 88-001 Project stage: Other ML20148B6661988-03-16016 March 1988 Responds to 880205 NRC Compliance Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Westinghouse Ds Series Circuit Breakers Not Used in Class IE Svc at Plant Project stage: Other NRC-88-0072, Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Util Does Not Utilize Subj Circuit Breakers1988-03-24024 March 1988 Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Util Does Not Utilize Subj Circuit Breakers Project stage: Other ML20148K2251988-03-25025 March 1988 Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Two Reactor Trip Breakers & Two Reactor Trip Bypass Breakers Subj to Bulletin Used at Millstone Unit 3.Main Pole Shaft Weld Insps Completed by 880225 Project stage: Other ML20151G7911988-03-28028 March 1988 Confirms That Westinghouse Ds Breakers Not Used at Facility, Per IE Bulletin 88-001, Defects in Westinghouse Circuit Breakers Project stage: Other W3P88-0051, Responds to NRC Bulletin 88-001 Re Defects in Westinghouse Circuit Breakers.Util Does Not Use Westinghouse Series Ds Circuit Breakers & Not Subj to Insps Requested in Bulletin1988-03-29029 March 1988 Responds to NRC Bulletin 88-001 Re Defects in Westinghouse Circuit Breakers.Util Does Not Use Westinghouse Series Ds Circuit Breakers & Not Subj to Insps Requested in Bulletin Project stage: Other ML20151A9451988-03-30030 March 1988 Responds to IE Bulletin 88-001 Re Westinghouse Ds/Dsl Circuit Breakers.Ref Components Not Utilized at Facility Project stage: Other 0CAN048804, Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Informs That No Instances of Circuit Breakers Being Installed in safety-related Applications Identified at Plant1988-04-0101 April 1988 Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Informs That No Instances of Circuit Breakers Being Installed in safety-related Applications Identified at Plant Project stage: Other ML20151B2021988-04-0404 April 1988 Responds to NRC Bulletin 88-001 Re Defects in Westinghouse Circuit Breakers.Insp of All Westinghouse DS-415 Reactor Trip & Bypass Breakers Completed on 880308 & Results Encl Project stage: Other RBG-27645, Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Util Does Not Utilize Any Circuit Breakers Subj to Bulletin in Class 1E Svc at Plant1988-04-0404 April 1988 Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Util Does Not Utilize Any Circuit Breakers Subj to Bulletin in Class 1E Svc at Plant Project stage: Other ML20148Q7241988-04-0707 April 1988 Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. No Westinghouse Models DS-206,DSL-206, DS-416,DSL-416 or DS-420 Breakers in Class 1E Circuits at Hatch Project stage: Other ML20151H7791988-04-0707 April 1988 Informs That Westinghouse Ds Circuit Breakers Not Utilized in Any 1E Application at Plant But Used in non-1E Applications & Will Be Included in Util Preventive Maint Program Project stage: Other ML20151E4191988-04-0808 April 1988 Responds to 880205 NRC Bulletin 88-01 Re Defects in Westinghouse Circuit Breakers for Facilities.Westinghouse Ds Series Circuit Breakers Not Used at Plants.Other Provisions of Bulletin Do Not Apply to Plants Project stage: Other ML20151E8681988-04-11011 April 1988 Forwards Response to NRC Bulletin 88-001 Re Defects in Westinghouse Circuit Breakers in Class 1E Svc.All Required long-term & short-term Insps Completed Project stage: Other ML20151H9651988-04-13013 April 1988 Responds to NRC Bulletin 88-001, Deficiencies in Westinghouse Circuit Breakers. Bulletin Addresses Deficiencies Exclusive to Westinghouse Ds/Dsl Type Circuit Breakers & Outlines Specific Insps to Be Performed Project stage: Other ML20151G1151988-04-13013 April 1988 Ack Receipt of in Response to NRC Bulletin 88-001 Re Westinghouse Circuit Breakers.Plant Does Not Use or Plan Use of Circuit Breakers,Therefore Matter Closed Project stage: Other ML20205P6881988-04-20020 April 1988 Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. No Circuit Breakers Subj to Bulletin Installed in Plant Project stage: Other ML20155E3921988-06-0909 June 1988 Responds to NRC Bulletin 88-001 Re Defects in Westinghouse Circuit breakers.Sixty-six of sixty-seven Breakers Required New Pole Shafts Due to Failure of Welds to Meet Bulletin Requirements Resulting from Insp Project stage: Other ML20150B5261988-06-30030 June 1988 Informs That All Class 1E DS-416 Breakers Now in Use Comply W/Nrc Bulletin 88-001 Re Defects in Westinghouse Circuit Breakers Project stage: Other ML20150D3971988-07-0505 July 1988 Advises That Response to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers, Satisfactory Project stage: Other ML20151E0181988-07-14014 July 1988 Advises That Util 880407 Response to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers, Satisfactory Project stage: Other ML20151Q9201988-08-0202 August 1988 Informs That Response to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers, Satisfactory Project stage: Other ML20154D2331988-09-0909 September 1988 Informs That Response to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers, Satisfactory & No Further Reply Necessary Project stage: Other ML20154E1541988-09-0909 September 1988 Advises That 880408 Response to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers, Satisfactory Project stage: Other ML20155A4561988-09-29029 September 1988 Requests Addl Info Re Util 880908 Response to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Response Requested within 70 Days of Ltr Date Project stage: Other ML20235J1681989-02-17017 February 1989 Advises That 880314 Response to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers Satisfactory. Westinghouse Ds Series Circuit Breakers Not Used in safety-related Applications at Plant Project stage: Other ML20235J1651989-02-17017 February 1989 Provides Final Response to NRC Bulletin 88-001, Defects in Westinhouse Circuit Breakers. Alignment Check Specified in 871201 Submittal Satisfactorily Performed During Installation of Replacement Pole Shaft in Breakers Project stage: Other ML20247C7191989-05-15015 May 1989 Forwards Supplemental Response to NRC Bulletin 88-001 Re Westinghouse Series Ds Circuit Breakers.Insp Info Corrected Project stage: Supplement ML20247K0751989-05-24024 May 1989 Responds to NRC Bulletin 88-001 Re Defects of Westinghouse Circuit Breakers.All forty-seven Westinghouse Type Ds Breakers Inspected Were Found to Have Acceptable Breaker Mechanism Alignment Project stage: Other A07039, Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Pole Shafts for All Four Breakers Replaced During Recently Completed Refueling Outage1989-07-24024 July 1989 Responds to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers. Pole Shafts for All Four Breakers Replaced During Recently Completed Refueling Outage Project stage: Other 1988-03-07 |
| ML20235J165 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 02/17/1989 |
| From: | William Cahill TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| IEB-88-001, IEB-88-1, TAC-65955, TAC-65956, TXX-89080, NUDOCS 8902240196 | |
| Download: ML20235J165 (3) | |
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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 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
[Table view]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 Category:UTILITY TO NRC MONTHYEARML20059K6141990-09-17017 September 1990
[Table view]Submits Documentation of 900906 Telcon Re Addl Util Candidate for Licensed Operator Generic Fundamentals Exam Section ML20059G8761990-09-10010 September 1990 Forwards Rev 8 to Physical Security Plan.Rev Withheld (Ref 10CFR73.21) ML20059F8461990-09-0404 September 1990 Responds to NRC Re Violations Noted in Insp Repts 50-445/90-22 & 50-446/90-22 on 900606-0705.Corrective action:OPT-467A Changed to Provide Addl Prerequisite Info Re Solid State Protection Sys Switch Lineup During Testing ML20059E4981990-08-31031 August 1990 Forwards Revised Radial Peaking Factor Limit Rept for Cycle 1 Per Tech Specs Through Amend 1 & ML20059E4201990-08-30030 August 1990 Forwards Objectives & Guidelines for 1990 Emergency Preparedness Exercise Scheduled for 901113 ML20028G8281990-08-29029 August 1990 Forwards Comanche Peak Unit 1 Semiannual Radioactive Effluent Release Rept,900403-0630 & ODCM TXX-9030, Forwards Endorsements 40 & 4 to Nelia Policy NF-274 & Maelu Policy M-90,respectively & Endorsements 10,11,12,13,14 & 15 to Maelu Policy MF-1311990-08-27027 August 1990 Forwards Endorsements 40 & 4 to Nelia Policy NF-274 & Maelu Policy M-90,respectively & Endorsements 10,11,12,13,14 & 15 to Maelu Policy MF-131 ML20059F4381990-08-23023 August 1990 Forwards Public Version of Revised Emergency Plan & Corporate Emergency Response Procedures,Consisting of Rev 1 to EPP-313,Rev 7 to CERP-101,Rev 7 to CERP-102 & Revised Forms.W/Dh Grimsley 900906 Release Memo TXX-9029, Responds to NRC Re Violations Noted in Insp Repts 50-445/89-57 & 50-446/89-57.Corrective Actions:Storage Facilities for Instrumentation & Control Work Packages Improved to Provide Acceptable Protection for Documents1990-08-20020 August 1990 Responds to NRC Re Violations Noted in Insp Repts 50-445/89-57 & 50-446/89-57.Corrective Actions:Storage Facilities for Instrumentation & Control Work Packages Improved to Provide Acceptable Protection for Documents ML20058P0571990-08-13013 August 1990 Forwards, Comanche Peak Steam Electric Station Unit 1 Control Room Simulator 10CFR55 Certification Initial Rept ML20058N2311990-08-0909 August 1990 Forwards First Half 1990 fitness-for-duty Program Performance Data,Per 10CFR26.71(d).Point of Contact for Personnel,Random Testing Program Results & Confirmed Positive Tests Summary & Mgt Summary Included in Data ML20059A5831990-08-0404 August 1990 Responds to Info Request Made During 900802 Meeting Re Inadvertent Safety Injections on 900726 & 30 & Results of 100% Power Plateau Testing TXX-9024, Provides Status of Exam Activity & Revised Completion Schedule for Portion of Exam.Util Deferred Preoperational Testing of Facility Spent Fuel Pool Cooling & Cleanup Sys Until Prior to First Off Loading of Spent Fuel1990-08-0303 August 1990 Provides Status of Exam Activity & Revised Completion Schedule for Portion of Exam.Util Deferred Preoperational Testing of Facility Spent Fuel Pool Cooling & Cleanup Sys Until Prior to First Off Loading of Spent Fuel TXX-9022, Forwards Detailed Descriptions of Changes in Amend 79 to FSAR for Comanche Peak Steam Electric Station1990-07-31031 July 1990 Forwards Detailed Descriptions of Changes in Amend 79 to FSAR for Comanche Peak Steam Electric Station TXX-9027, Responds to NRC Re Violations Noted in Insp Repts 50-445/90-19 & 50-446/90-19.Corrective Action:Specific Activity within Tech Spec Limits.No Further Corrective Action Required1990-07-30030 July 1990 Responds to NRC Re Violations Noted in Insp Repts 50-445/90-19 & 50-446/90-19.Corrective Action:Specific Activity within Tech Spec Limits.No Further Corrective Action Required ML20055J1571990-07-27027 July 1990 Submits Info Re Replacement of Borg-Warner/Intl Pump,Inc Check Valve Swing Arms,Per .Swing Arms in ASME Code Class 2 Check Valves Will Be Replaced During First Refueling Outage ML20056A0461990-07-24024 July 1990 Requests Regional Waiver of Compliance for Containment Pressure Transmitter 1-PT-934 During Coming Outage TXX-9023, Responds to NRC Bulletin 90-001, Loss of Fill-Oil in Transmitters Mfg by Rosemount. No Subj Transmitters in Existence at Facility1990-07-18018 July 1990 Responds to NRC Bulletin 90-001, Loss of Fill-Oil in Transmitters Mfg by Rosemount. No Subj Transmitters in Existence at Facility ML20055G6351990-07-17017 July 1990 Submits Results of Remote Shutdown Panel Environ Survey ML20055F9391990-07-13013 July 1990 Advises That Operators Have Gained Significant Experience in Operating Plant Under Wide Range of Conditions & Have Demonstrated Necessary Proficiency to Safely Operate Unit ML20055F9371990-07-13013 July 1990 Submits Info Re Revised Acceptance Criteria for THERMO-LAG Fire Barrier,Per 900705 Telcon.On Exposure to Heat Flux at Surface of Barrier,Listed Mechanisms Activated.Fire Testing Demonstrates That Panels Qualified W/Variation in Thickness ML20044A7001990-06-26026 June 1990 Responds to Generic Ltr 90-04, Request for Info on Status of Licensee Implementation of Generic Safety Issues Resolved W/Imposition of Requirements or Corrective Actions. Util Will Implement for Unit 2 Activities Performed for Unit 1 ML20044A1411990-06-20020 June 1990 Forwards Endorsements 4 & 5 to Nelia Certificate N-90, Endorsements 5 & 6 to Maelu Certificate M-90 & Endorsements 34,35,36,37,38 & 39 to Nelia Policy NF-274 ML20043H7031990-06-18018 June 1990 Discusses Mod/Rework to Auxiliary Feedwater Sys Check Valves Mfg by Bw/Ip Intl,Inc.All But One Affected Check Valve modified.Motor-driven Auxiliary Feedwater Pump Discharge Valve Check Valve Body Replaced ML20043H2181990-06-15015 June 1990 Forwards Response to 900515 Request for Addl Info on Emergency Preparedness.Ongoing Emergency Preparedness Programs Address Concerns Raised by Citizens for Fair Util Regulation ML20043G3131990-06-15015 June 1990 Forwards Addl Info Re Pressurizer Surge Line Thermal Stratification & leak-before-break Evaluation & Nonproprietary Suppl 3 to WCAP-12247, Supplementary Assessment... & Proprietary Suppl 3 to WCAP-12248 ML20043C5671990-06-0101 June 1990 Discusses Identification of Slave Relays Tested Using Alternative Methodology,Per 900402 Commitment.Encl Tabulation Identifies Test Type,Applicable Procedures & Equipment & Impact of Improper Documentation ML20043E7131990-06-0101 June 1990 Responds to NRC 900517 Notice of Violation & Imposition of Civil Penalty in Amount of $25,000.Corrective Action:Qc Mgt Counseled Level III Inspector & QC Supervisor on Importance of Good Communications W/Receipt Inspectors ML20043C4501990-05-31031 May 1990 Advises That Util Revised FSAR Section 15.1.2 & Question/ Response 32.108,per 10CFR50.59 ML20043B5471990-05-25025 May 1990 Provides Status of Facility Design & Const Activities,Per Request.Detailed Design Work Will Resume in June 1990.Const Activities Expected to Increase Signficantly by Jan 1991 ML20043B5481990-05-23023 May 1990 Provides Clarification of 890710 Commitment Re Power Ascension Program.Cooldown Portion of Remote Shutdown Test Performed During Preoperational Testing,Per FSAR & Reg Guide 1.68.2 ML20043D1711990-05-21021 May 1990 Forwards Public Version of Revised Emergency Plan Procedures,Including Rev 8 to EPP-109,Rev 7 to EPP-112,Rev 4 to EPP-116 & Rev 6 to EPP-121.W/DH Grimsley 900604 Release Memo TXX-9018, Advises of Completion of Implementation of Requirements of Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety- Related Equipment1990-05-21021 May 1990 Advises of Completion of Implementation of Requirements of Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety- Related Equipment ML20043B0981990-05-15015 May 1990 Forwards Radial Peaking Factor Limit Rept for Cycle 1, Containing F(Xy) Limits for All Core Planes Containing Bank D Control Rods & All Unrodded Core Planes ML20042F2851990-05-0303 May 1990 Supplemental Response to Generic Ltr 90-01, Request for Voluntary Participation in NRC Regulatory Impact Survey. ML20042F3861990-05-0303 May 1990 Responds to NRC 900410 Ltr Re Violations Noted in Insp Repts 50-445/90-10 & 50-446/90-10 on 900206-07 & 0226-0302. Corrective Action:Memo Issued Emphasizing That Discrepancies Should Be Brought to Attention of Site Organizations ML20042F3021990-05-0202 May 1990 Responds to NRC 900402 Ltr Re Violations Noted in Insp Repts 50-445/89-23 & 50-446/89-23.Util Does Not Believe That Circumstances Described in 900402 Ltr Constitutes Violation of 10CFR50.9(a) ML20042F3051990-05-0202 May 1990 Provides Revised Response to Generic Ltr 88-17 Re Loss of DHR ML20042E4581990-04-12012 April 1990 Responds to Inconsistencies in Terminology & Labelling Identified During NRC 890118 & 19 Audit of Facility Dcrdr. Util Believes Control Room Inventory Requirement of Suppl 1 to NUREG-0737,satisfied ML20042E0701990-04-10010 April 1990 Discusses 900305 Meeting W/Nrc in Rockville,Md Re Offsite Power Availability for Automatic Switch Co Solenoids for MSIV in Event of Nonmechanistic Main Steam Line Crack in Superpipe Region ML20012F5011990-04-0303 April 1990 Forwards Corrections to 891016 Response to Emergency Diesel Generator Engine Requirements.Lengths of Two Pairs of Bolts Above Crankpin Shall Be Measured Ultrasonically Before Detensioning & Disassembly of Bolts ML20012F3221990-04-0202 April 1990 Discusses ESF Sys Slave Relay Alternate Test Methodology. Implementation Schedule for Design Mods to Relay Will Be Submitted by 900601 ML20042D8081990-03-29029 March 1990 Forwards Proposed Change to FSAR Section 13.4 Re Station Operations Review Committee.Similar Change Submitted in 900328 Ltr for Chapter 6 of Facility Tech Specs ML20012F0411990-03-28028 March 1990 Forwards marked-up Pages of Facility Draft Tech Specs & Bases (NUREG-1381) Provided W/Low Power OL ML20012E6051990-03-27027 March 1990 Forwards Endorsements 1-4 to Maelu Certificate M-90, Endorsements 1-9 to Maelu Policy MF-131,Endorsements 29-33 to Nelia Policy NF-274 & Endorsements 1-3 to Nelia Certificate N-90 ML20012E6531990-03-27027 March 1990 Provides Final Response to Reporting Requirement 2 of NRC Bulletin 88-008, Thermal Stresses in Piping Connected to RCS, for Unit.Nde Requirements of Action 2 Not Considered Applicable to Unit ML20012E1911990-03-23023 March 1990 Forwards Comanche Peak Steam Electric Station Unit 1 Cycle 1 Startup Physics Tests Control Rod Worth Predictions Utilizing TU Electric Control Rod Swap Methodology. ML20012E1581990-03-23023 March 1990 Clarifies 880624 Response to NRC Generic Ltr 88-05, Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR Plants. ML20012D0201990-03-19019 March 1990 Advises That Allegations Provided to NRC by Former Util Employee Unsubstantiated,Based on Investigation by Util Safeteam Organization ML20012E2181990-03-19019 March 1990 Responds to Generic Ltr 89-19 Re USI A-47, Safety Implication of Control Sys in LWR Nuclear Power Plants. Util Determined That Loss of safety-related Inverters 1 or 2 Would Involve Coincidental Opening of Main Feedwater Valves 1990-09-04 |
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. Log. # TXX-89080 File # 10119 980.3 7t# ELECTRIC -Ref. #.10CFR50.71 Feb ruary '17, 1989 '
- W.J.Cahul Executive Vice President .
U. S. Nuclear Regulatory Commission Attn: Docunent Control Desk Washington, D.C. '20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION'(CPSES)
DOCKET NOS. 50-445 AND 50-446 NRC BULLETIN 88-01 (TACS 65955/65956)
DEFECTS IN WESTINGHOUSE CIRCUIT BREAKERS REF: 1) NRC Bul_letin 88-01; Defects in Westinghouse Circuit Breakers, dated February 5,1988
- 2) Westinghouse Technical Bulletin NSID-TB-87-11, Westinghouse Circuit' Breakers Type DS/DSL: Welds on Pole Sheft, dated December 1, 1987 3)' .TU Electric Letter TXX-88377 from W. G. Counsil to U.S.N.R.C. dated April 8, 1988
- 4) NRC Letter from C.1. Grimes to W. G. Counsil dated June 1,.1988 Gentlemen:
Reference 1) requested addressees to perform certain inspections of 4
Westinghouse DS series circuit breakers used in Class 1E applications.
Reference.3) provided TV Electric's interim response. Reference 4) provided the results of the NRC review of TV Electric's interim response. Provided below.is TV Electric's final response to NRC Bulletin 88-01 for Unit 1. Our final response for Unit 2 will be provided prior to Unit 2 fuel load.
We have determined that there are a total o; 48 Westinghouse type DS-416 breakers installed in Unit 1 Class 1E applications. No other type DS or DSL breakers identified in reference 1 are used in Unit 1 Class 1E applications The pole shafts on all 48 Unit 1 05-416 Class IE breakers have been replaced with new pole shafts from the vendor. The replacement pole shafts were receipt inspected and accepted per the short term and long term inspection requirements contained in reference 2 as modified by reference 1. The alignment check specified by reference 2 was satisfactorily performed during the installation of the replacement pole shafts in the breakers.
8902240196 890217 [
PDR ADOCK 05000445 ,.
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400 North Olive Street LB81 Dallas, Texas 75201
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4 TXX-89080 February 17, 1989 Page 2 of 2 The removed pole shafts were examined to the requirements of reference 2. On all 48 removed pole shafts, the welds attaching pieces 2, 3, and 6 (figure 1,,
reference 2) to the shaft did not meet the weld criteria specified in
, reference 2. Pieces.2, 3, and 6 have been rewelded and.the pole shafts r
. retained for possible use in non-Class 1E applications.
Sincerely, William J. ahill, Jr.
WJH:mbk Attachment c - Mr. R. D. Martin, Region IV Resident Inspectors, CPSES (3)
4
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- Attachment to TXX-89080 r February 17, 1989 f
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of Texas Utilities Electric Company ) Docket Nos. 50-445 50-446 (Comanche Peak Steam Electric
- Station, Units .1 F 2)
AFFIDAVIT W. J. Cahill, Jr. being duly sworn, hereby deposes and says that he is '
Executive Vice President, Nuclear of TV Electric, the Applicant herein; that he is duly authorized to sign and file with the Nuclear Regulatory Commission this response to NRC Bulletin 88-01 (TACS 65955/65956) that he is familiar with the content thereof; and that the matters s?+ forth therein are true and correct to the best of his. knowledge, information ant' belief.
W. Jpabill, Jr./ // I '
Executive Vice Preffdent, Nuclear canot.vN s. wiu.iAus STATE OF TEXAS
= i._.._
- N["7s N itary Seal COUNTY OF Somervell Subscribed and sworn to before me on this 16th day of February ,
1989.
Nota (yPublic
) .
My commission expires: 3-22-92 ,
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