ML20090A070
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| ML20090A070 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 06/14/1984 |
| From: | Rahe E WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| To: | Baer R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| References | |
| NS-EPR-2932, NUDOCS 8407110212 | |
| Download: ML20090A070 (2) | |
Similar Documents at Comanche Peak | |
|---|---|
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
[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 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 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:VENDOR/MANUFACTURER TO NRC MONTHYEARML20043G3231990-06-14014 June 1990
[Table view]Application for Withholding Proprietary Suppl 3 to WCAP-12248, Supplementary Assessment of Leak-Before-Break for Pressurizer Surge Lines of Unit 1, from Public Disclosure,Per 10CFR2.790 ML20012D5391990-03-19019 March 1990 Requests Withholding of Encl Proprietary Info Re Rod Control Cluster Assembly Repositioning from Public Disclosure,In Accordance w/10CFR2.790.Affidavit Supporting Request Also Encl ML19325E7541989-10-23023 October 1989 Requests That Proprietary Rept WCAP-12248,Suppl 2, Addl Info in Support of Evaluation of Thermal Stratification for Comanche Peak Unit 1 Pressurizer Surge Line Be Withheld from Public Disclosure (Ref 10CFR2.790) ML19325E9001989-10-19019 October 1989 Forwards Text of Info Communicated to All Util W/ Westinghouse NSSS Design on Pressurizer Safety Valve Set Pressure Deviation Info Request Response ML20011E4441989-10-17017 October 1989 Responds to 891010 Request for Comments on Plant SALP Process.Words of SALP Rept,Section H,Consistent W/Author Limited Knowledge & Exposure to Plant Current Status ML20247G9771989-09-13013 September 1989 Requests Proprietary Suppl 1 to WCAP-12248, Addl Info in Support of Evaluation of Thermal Stratification for Comanche Peak Unit 1 Pressurizer Surge Line, Be Withheld (Ref 10CFR2.790(b)(4)) ML20245J8591989-08-0303 August 1989 Requests Proprietary Suppl 2 to WCAP-12258, Evaluation of Thermal Stratification for Comanche Peak Unit 1 RHR Lines Be Withheld (Ref 10CFR2.790) ML20248B1381989-07-11011 July 1989 Requests That Proprietary Rept RXE-89-003-P, Steady State Reactor Physics Methodology, Be Withheld from Public Disclosure (Ref 10CFR2.790) ML20246E7941989-05-0404 May 1989 Requests Withholding of Proprietary WCAP-12258, Evaluation of Thermal Stratification for Comanche Peak Unit 1 & 2 RHR Lines, from Public Disclosure (Ref 10CFR2.790) ML20246K1641989-05-0404 May 1989 Requests That Proprietary Rept WCAP-12267, Technical Bases for Eliminating Rupture of Accumulator Injection Nozzles... Comanche Peak Unit 1, Be Withheld from Public Disclosure (Ref 10CFR2.790).Ltr Is Reissuance ML20245G0811989-04-27027 April 1989 Requests That Proprietary WCAP-12248, Evaluation of Thermal Line Stratification for Comanche Peak Unit 1 Pressurizer Surge Line, Be Withheld,Per 10CFR2.790(b)(4) ML20247A4371989-04-24024 April 1989 Requests That Proprietary Rev 2 to WCAP-12123 Westinghouse Setpoint Methodology for Protection Sys,Comanche Peak Unit 1,Rev 1, Be Withheld from Public Disclosure (Ref 10CFR2.790) ML20247L2801989-03-27027 March 1989 Requests Withholding of Proprietary Rev 1 to WCAP-12123, Westinghouse Setpoint Methodology for Protection Sys, from Public Disclosure (Ref 10CFR2.790) ML20247G4011989-03-22022 March 1989 Application for Withholding Proprietary WCAP-12228, Transit Time Flow Meter Calculation (Ref 10CFR2.790) ML20236E2261989-03-0707 March 1989 Requests That Proprietary WCAP-12171, Evaluation of Thermal Stratification of Surge Line & RHR Lines for Comanche Peak Unit 1,Presentation Overheads for 890221 Util/Nrc Meeting, Be Withheld from Public Disclosure (Ref 10CFR2.790) ML20207M6871988-09-26026 September 1988 Requests That Proprietary WCAP-11987, Surge Line Stratification Presentation Overheads - 880907 Texas Util Electric/Nrc Meeting Be Withheld from Public Disclosure (Ref 10CFR2.790) ML20148E6381988-03-14014 March 1988 Requests for Withholding of Rept RXE-88-101-P, Design Basis Analysis of Postulated Steam Generator Tube Rupture Event for Comanche Peak Steam Electric Station Unit 1, from Public Disclosure ML20245B7761987-05-28028 May 1987 Requests That Rept Re Reported Failures of Model 3S-130-300 Class 1E Battery Chargers at Plant Be Sent to Author.Company Has Received Little or No Info Re Reported Failures ML20214K0491986-09-24024 September 1986 Requests Withholding of Proprietary WCAP-11127, Shotpeening Licensing Rept for Comanche Peak Unit 1, Per 10CFR2.790 ML20237L1871986-08-31031 August 1986 Forwards marked-up Corrected Transcript of Cj Haughney 860617 Investigative Interview.Two Comments,Including Evident Transcription Error on Page 20,Line 12 Discussed ML20214K0701986-08-0101 August 1986 Requests Withholding of Proprietary WCAP-11175, Row 1 & Row 2 Heat Treatment for Comanche Peak Unit 1, Per 10CFR2.790 ML20197E2891986-04-0808 April 1986 Discusses Energy Technology Engineering Ctr Review of Rev 3 to Comanche Peak Review Team Issue-Specific Action Plan V.D Re Unauthorized Plug Welds in ASME Pipe Supports & Base Plates & in Cable Tray Supports.Review Encl NRC-85-3061, Submits Internal Review Results Concluding That Safety Deficiencies,Intimidation & Retaliation Alleged by Ja Segletes Did Not Occur,Confirming 850712 Preliminary Assessment.Related Info Encl1985-09-13013 September 1985 Submits Internal Review Results Concluding That Safety Deficiencies,Intimidation & Retaliation Alleged by Ja Segletes Did Not Occur,Confirming 850712 Preliminary Assessment.Related Info Encl ML20135C2641985-08-30030 August 1985 Requests That Proprietary Responses Re Justification of Reduced Flow Meter Measurement Uncertainties Be Withheld (Ref 10CFR2.790) NRC-84-2985, Advises That Addl Info Requested During 841008 Meeting Re WCAP-9172(P)/9264(NP), N-16 Transit Time Flow Measurement Sys (Ttfm) Description & Performance Will Be Provided to NRC by First Refueling Outage1984-12-0505 December 1984 Advises That Addl Info Requested During 841008 Meeting Re WCAP-9172(P)/9264(NP), N-16 Transit Time Flow Measurement Sys (Ttfm) Description & Performance Will Be Provided to NRC by First Refueling Outage ML20098C8591984-08-14014 August 1984 Alleges That Unqualified Suppliers Awarded Contracts from Plants to Provide Flexible Conduits Unqualified Under IEEE Stds 323 & 344 Despite IEEE Bid Requirements.Meeting Re NRC Position on safety-related Installations Requested ML20090A0701984-06-14014 June 1984 Responds to Request for Info Re Westinghouse DS-416 Breaker Moving Secondary Contact Mounting Frame Welds.Separated Bracket Welds Not Indicative of Generic Issue ML20092H4401984-06-0404 June 1984 Requests Withholding of Proprietary Westinghouse Setpoint Methodology for Protection Sys,Comanche Peak Station, (Ref 10CFR2.790) ML20101C4371984-05-18018 May 1984 FOIA Request for Investigation Rept Re Flexible Metal Conduit & Associated Fittings Supplied to Facilities ML20084A6771984-04-15015 April 1984 Application for Withholding Proprietary Rept, Technical Bases for Eliminating Large Primary Loop Pipe Rupture as Structural Design Basis for Comanche Peak,Units 1 & 2 ML20081E8061983-10-28028 October 1983 Application for Withholding Proprietary Version of Technical Bases for Eliminating Large Primary Loop Pipe Ruptures as Structural Design Basis for Comanche Peak Units 1 & 2, Per 10CFR2.790.Affidavit Encl ML20081A4611983-08-26026 August 1983 Forwards Nonproprietary & Proprietary Versions of Counterflow Preheat Steam Generator Tube Expansion Rept & Counterflow Preheat Steam Generator Tube Vibration Summary Rept. Proprietary Version Withheld (Ref 10CFR2.790) ML20081A4691983-08-26026 August 1983 Application for Withholding Proprietary Versions of Counterflow Preheat Steam Generator Tube Expansion Rept & Counterflow Preheat Steam Generator Tube Vibration Summary Rept, Per 10CFR2.790.Affidavit Encl ML20072G2321983-06-21021 June 1983 Advises That Info Submitted by Util on 830610 Re Response to Open Items from Equipment Qualification Branch Sqrt Is Nonproprietary ML20072J4961983-06-21021 June 1983 Advises That Info Provided in Texas Utils Re Open Items from NRC Equipment Qualification Branch Sqrt Audit of Site Not Westinghouse Proprietary as Originally Marked ML20069G1051983-02-28028 February 1983 Forwards Rev 0 to Nonproprietary WCAP-8587,Suppl 1, Equipment Qualification Data Packages & Proprietary WCAP- 8687,Suppl 2 Equipment Qualification Test Repts. Proprietary Repts Withheld (Ref 10CFR2.790) ML20010A7681981-07-24024 July 1981 Forwards Application for Withholding & Proprietary Rept WCAP-8687 Suppl 2,E22A.Also Forwards Revision 2 to Nonproprietary Rept WCAP-8587 Suppl 1,EQDP-ESE-22. Proprietary Rept Withheld (Ref 10CFR2.790) ML19345D4931980-11-26026 November 1980 Forwards Revision 1 of Table 1,providing Scheduled Documentation Submittal Dates to NRC for Equipment Qualification Data Packages Included in Vendor Equipment Qualification Program.Table 2 Re Facility Equipment Encl ML19340C4131980-11-0707 November 1980 Forwards Proprietary & Nonproprietary Versions of Slides Used in Westinghouse Proposal for Addressing Inadvertent Boron Dilution Event at Facility.Application for Withholding & Affidavit Encl ML19323H2991980-06-0303 June 1980 Forwards Qualification Test Schedule & Status for Class IE Equipment to Be Supplied by Vendor.Submittal in Response to Action Item Per 800507 Meeting Re Qualification Programs & Review,Required to Ensure Timely Issuance of OL ML19281A5451979-02-16016 February 1979 Confirms Telcon of 790216 Re Defective Equipment Supplied to Texas Util Generating Co.Two AV Line Switchboards Were Shipped W/Incorrect Ammeters Installed.Incorrect Ammeters Were Removed & Correct Ammeters Installed 1990-06-14 |
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o Westinghouse Water Reactor Ba355 PittsburghPennsy!vania15230 Electric Corporation Divisions NS-EPR-2932 June 14^,1984 (7 Mr. Robert L. Baer, Chief 6h Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Phfilips Building 7920 Norfolk Avenue .
Bethesda, f4aryland 20014 Attention: Mr. W. Anderson
Dear fir. Baer:
The purpose of this letter is to respond to your request for information concerning the Comancho Peak DS-416 breaker moving secondary contact mounting frame welds. This issue was initiated when two frame welds in a Comanche Peak breaker were found to have separated. In the ensuing investigation a number of frames were selected to be returned to Westinghouse for purposes of the investigation.
The Westinghouse investigation began by assuming a worst case operating load in order to establish testing parameters. The nominal load is 65 lbs. maximum but for purposes of this investigation 150 lbs. was assumed as a worst case operational load. The normal operating load per switch assembly is 4 lbs.,
and the maximum this value can be is 9 lbs. For a set of 16 switches in the bracket, the total maximum service load possiole is thus (9x16) 144 lbs.,
which was rounded off to 150 lbs for the purposes of investigating in the worst-mode condition.
The first phase of testing loaded half of the sample welds to 450 lbs. in order to establish a minimum factor of three times the worst case operating load. All welds sustained the 450 lb. load without yielding. The second phase of testing was to establish the maximum load carrying capability of the frame welds. The other half of the welds were loaded until yielding occurco.
In these tests the minimum force necessary to fail the welds was over 900 lbs., six times the assumed worst case operational load.
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NS-EPR-2932 Jun2 14, 1984 Westinghouse conducted a metallurgical investigation of the separated welds which showed that the weld separation is the result of lack of fusion at the weld metal to base metal interface due to the presence of slag inclusions.
Metr 11ographic e.samination of two welds from the field confirmed tht lack of fusi;a does exist in these welds varying from 30% to 70%. However, as noted above, the as-welded condition of the brackets can sustain at least six (6) times the maximum service load.
It is the Westinghouse position th'at the separated bracket welds are not indicative of a generic issue. Their occurrence is attributed to the statistical probability of random failures in any Quality Assurance system.
The mounting frame design is very conservative as demonstrated by the above, i
Very truly yours, i E. P. Rahe, M., Manager Nuclear Safety Department JTC/ KEG I
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