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Category:CORRESPONDENCE-LETTERS
MONTHYEARTXX-9924, Forwards Responses to Questions by NRC Re Application for Amends to Licenses NPF-87 & NPF-89,by Incorporating Changes Increasing RWST low-level Setpoint from Greater than But Equal to 40% to Greater than But Equal to 45% of Span1999-10-22022 October 1999
Forwards Responses to Questions by NRC Re Application for Amends to Licenses NPF-87 & NPF-89,by Incorporating Changes Increasing RWST low-level Setpoint from Greater than But Equal to 40% to Greater than But Equal to 45% of Span
ML20217M5711999-10-20020 October 1999
Forwards Insp Repts 50-445/99-15 & 50-446/99-15 on 990822- 1002.Two Severity Level IV Violations of NRC Requirements Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy
TXX-9923, Forwards Monthly Operating Repts for Sept 1999 for CPSES, Units 1 & 2,per Plant TS 5.6.4.No Failures of Challenges to PORVs of SV for Units Occurred1999-10-15015 October 1999
Forwards Monthly Operating Repts for Sept 1999 for CPSES, Units 1 & 2,per Plant TS 5.6.4.No Failures of Challenges to PORVs of SV for Units Occurred
ML20217E7951999-10-12012 October 1999
Forwards COLR for Unit 1,Cycle 8,per TS 5.6.5
ML20212L2891999-10-0101 October 1999
Discusses Closeout of GL 97-06, Degradation of Steam Generator Internals. Purpose of GL Was to Obtain Info That Would Enable NRC to Verify That Condition of Licensee SG Internals Comply with Current Licensing Bases
TXX-9922, Forwards Revised COLR, for Cycle 5 for Unit 21999-10-0101 October 1999
Forwards Revised COLR, for Cycle 5 for Unit 2
ML20216J5571999-10-0101 October 1999
Provides Final Response to GL 98-01,suppl 1, Y2K Readiness of Computer Sys at Npps
ML20212G0721999-09-24024 September 1999
Forwards Rev 4 to Augmented Inservice Insp Plan for CPSES, Unit 1. Future Changes & Revs to Unit 1 Augmented Inservice Insp Plan Will Be Available on Site
ML20212H0461999-09-24024 September 1999
Forwards Rev 6 to CPSES Glen Rose,Tx ASME Section XI ISI Program Plan for 1st Interval on 990820
ML20212F7481999-09-24024 September 1999
Forwards SER Authorizing Relief from Exam Requirement of 1986 Edition ASME Code,Section XI Pursuant to 10CFR50.55a(a)(3)(ii) for Relief Request A-3 & 10CFR50.55a(g)(6)(i) for Relief Requests B15,16,17 & C-4
ML20212F1041999-09-23023 September 1999
Requests That NRC Be Informed of Any Changes in Scope of Y2K System Deficiencies Listed or Util Projected Completion Schedule for Comanche Peak Steam Electric Station,Units 1 & 2
ML20212E6661999-09-21021 September 1999
Advises That Info Contained in Application & Affidavit, (CAW-99-1342) Re WCAP-15009,Rev 0, Comache Peak Unit 1 Evaluation for Tube Vibration Induced Fatigue, Will Be Withheld from Public Disclosure
ML20212D9111999-09-16016 September 1999
Informs That on 990818,NRC Completed Midcycle PPR of CPSES & Did Not Identify Any Areas in Which Performance Warranted Insp Beyond Core Insp Program.Core Insp Plan at Facility Over Next 7 Months.Insp Plan Through March 2000 Encl
ML20212A7601999-09-14014 September 1999
Forwards Insp Repts 50-445/99-14 & 50-446/99-14 on 990707-0821.Four Violations Occurred & Being Treated as Ncvs.Conduct of Activities Was Generally Characterized by safety-conscious Operations & Sound Radiological Controls
TXX-9921, Suppls 981221 LAR 98-010 to Licenses NPF-87 & NPF-89, Clarfying Conditions of Use Re Analytical Methods Used to Determine Core Operating Limits,Per Telcon with NRC1999-09-10010 September 1999
Suppls 981221 LAR 98-010 to Licenses NPF-87 & NPF-89, Clarfying Conditions of Use Re Analytical Methods Used to Determine Core Operating Limits,Per Telcon with NRC
ML20211P3761999-09-0707 September 1999
Ack Receipt of Ltr Dtd 990615,transmitting Rev 30 to Physical Security Plan,Per 10CFR50.54(p).No NRC Approval Is Required
ML20211L9871999-09-0303 September 1999
Forwards Rev 31 to Technical Requirements Manual. All Changes Applicable to Plants Have Been Reviewed Under Util 10CFR50.59 Process & Found Not to Include Any USQs
TXX-9915, Responds to 990701 & 0825 RAI Telcons Re Spent Fuel Pool Temp,Per LAR 98-008,which Requested Increase in Spent Fuel Storage capacity.Marked-up Page 4-1 of CPSES Fuel Storage Licensing Rept, Encl1999-09-0303 September 1999
Responds to 990701 & 0825 RAI Telcons Re Spent Fuel Pool Temp,Per LAR 98-008,which Requested Increase in Spent Fuel Storage capacity.Marked-up Page 4-1 of CPSES Fuel Storage Licensing Rept, Encl
ML20211K2231999-08-31031 August 1999
Forwards Txu Electric Comments of Rvid,Version 2
ML20211J3801999-08-27027 August 1999
Forwards Corrected TS Page 3.8-26 to Amend 66 to Licenses NPF-87 & NPF-89,respectively.Footnote on TS Page 3.8-26 Incorrectly Deleted
ML20211G7301999-08-26026 August 1999
Forwards Revs 29 & 30 to CPSES Technical Requirements Manual (Trm). Attachments 1 & 2 Contain Description of Changes for Revs 29 & 30 Respectively
ML20211G1081999-08-26026 August 1999
Responds to NRR Staff RAI Re Util Mar 1999 Submittal for NRC Review & Approval of Changes to CPSES Emergency Classification Procedure
ML20211G3441999-08-25025 August 1999
Forwards Response to NRC RAI on LAR 98-010 for Cpses,Units 1 & 2.Communication Contains No New Licensing Commitments Re Cpses,Units 1 & 2
ML20211B2861999-08-18018 August 1999
Forwards Insp Repts 50-445/99-13 & 50-446/99-13 on 990720- 23.No Violations Noted.Insp Included Implementation of Licensee Emergency Plan & Procedures During Util Biennial Emergency Preparedness Exercise
ML20211C4661999-08-18018 August 1999
Discusses Proprietary Info Re Thermo-Lag.NRC Treated Bisco Test Rept 748-105 as Proprietary & Withheld It from Public Disclosure,Iaw 10CFR2.790
ML20210U3981999-08-17017 August 1999
Forwards Monthly Operating Repts for July 1999 for CPSES, Units 1 & 2,per TS 6.9.1.5.No Failures or Challenges to PORVs or SVs for Plant Occurred
ML20211C0991999-08-17017 August 1999
Forwards Rev 3 to ASME Section XI ISI Program Plan,Unit 2 - 1st Interval, Replacing Rev 2 in Entirety
ML20211C4571999-08-16016 August 1999
Forwards Omitted Subj Page of Contractor TER
TXX-9919, Forwards Relief Request A-3,Rev 1 to Unit 1 ISI Program,Per Conversations Between NRC & Txu Electric on 9908021999-08-16016 August 1999
Forwards Relief Request A-3,Rev 1 to Unit 1 ISI Program,Per Conversations Between NRC & Txu Electric on 990802
ML20210R6561999-08-13013 August 1999
Forwards Response to NRR 990805 Telcon RAI Re License Amend Request 98-010,to Increase Power for Operation of CPSES Unit 2 to 3445 Mwth & Incorporating Addl Changes Into Units 1 & 2 TS
ML20211A9501999-08-12012 August 1999
Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl
ML20210S6411999-08-12012 August 1999
Informs That Wg Guldemond,License SOP-43780,is No Longer Performing Licensed Duties.Discontinuation of License Is Requested
ML20210R2221999-08-12012 August 1999
Forwards Insp Repts 50-445/99-10 & 50-446/99-10 on 990510-0628.Violations Noted & Being Treated as Ncvs, Consistent with App C of Enforcement Policy
ML20210N1101999-08-0404 August 1999
Provides Supplemental Info to Util 990623 License Amend Request 99-005 Re Bypassing DG Trips.Info Replaces Info Contained in Subject Submittal in Attachment 2,Section II, Description of TS Change Request
ML20210L1461999-08-0303 August 1999
Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams
ML20210J2301999-08-0202 August 1999
Forwards Amend 96 to CPSES Ufsar.Replacement of FSAR Figures with Plant Process Flow Diagrams Meets Intent & Requirements of NRC Reg Guide 1.70,Rev 2
ML20210J6071999-08-0202 August 1999
Forwards line-by-line Descriptions of Changes in Amend 96 to CPSES UFSAR Transmitted by Util Ltr TXX-99166,dtd 990802. Replacment of FSAR Figures with Plant Process Flow Diagrams Meets Intent & Requirements of NRC Reg Guide 1.70,rev 2
TXX-9916, Notifies NRC That CPSES Units 1 & 2,improved TS Implemented on 9907271999-08-0202 August 1999
Notifies NRC That CPSES Units 1 & 2,improved TS Implemented on 990727
TXX-9918, Forwards CPSES 10CFR50.59 Evaluation Summary Rept 0008,for 970802-990201 & CPSES Commitment Matl Change Evaluation Rept 0003,for 970802-9906301999-08-0202 August 1999
Forwards CPSES 10CFR50.59 Evaluation Summary Rept 0008,for 970802-990201 & CPSES Commitment Matl Change Evaluation Rept 0003,for 970802-990630
ML20210K2321999-07-29029 July 1999
Forwards Insp Repts 50-445/99-12 & 50-446/99-12 on 990530-0710.No Violations Noted
ML20210G5861999-07-29029 July 1999
Forwards fitness-for-duty Program Performance Data for Six Month Period of Jan-June 1999
ML20210J0121999-07-27027 July 1999
Forwards Summary of Methodology for Determination of NDE Measurement Uncertainty,In Response to Recent Discussions with NRC Re LAR 98-006 Concerning Rev to SG Tube Plugging Criteria
TXX-9917, Provides Info Re Augmented Inservice Insp Plan,Which Requires Periodic Insp of Rv Head & Internals Lifting Devices at CPSES1999-07-26026 July 1999
Provides Info Re Augmented Inservice Insp Plan,Which Requires Periodic Insp of Rv Head & Internals Lifting Devices at CPSES
ML20210F3121999-07-26026 July 1999
Responds to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal,
ML20210D8231999-07-23023 July 1999
Forwards Safety Evaluation of Relief Requests Re Use of 1998 Edition of Subsections IWE & Iwl of ASME Code for Containment Insp
ML20210D3211999-07-21021 July 1999
Provides List of Estimates of Licensing Actions,In Response to Administrative Ltr 99-02,dtd 990603
ML20210C2931999-07-21021 July 1999
Supplements 880323 Response to NRC Bulletin 88-02, Rapidly Propagating...Sg Tubes, Non-proprietary WCAP-15010 & Proprietary Rev 0 to WCAP-15009, CP Unit 1 Evaluation for Tube Vibration... Encl.Proprietary Rept Withheld
ML20209H0111999-07-16016 July 1999
Forwards Relief Request C-4 to CPSES Unit 2 ISI Program for Approval
ML20210C3331999-07-16016 July 1999
Forwards Exam Repts 50-445/99-301 & 50-446/99-301 on 990618- 24.Exam Included Evaluation of Six Applicants for Senior Operator Licenses
ML20209H2551999-07-16016 July 1999
Forwards ISI Summary Rept for Fourth Refueling Outage of CPSES Unit 2 & Containment ISI Summary Rept for Fourth Refueling Outage of CPSES Unit 2,per ASME Boiler & Pressure Vessel Code,Section Xi,Paragraph IWA-6230
1999-09-07
[Table view]
Category:INCOMING CORRESPONDENCE
MONTHYEARTXX-9924, Forwards Responses to Questions by NRC Re Application for Amends to Licenses NPF-87 & NPF-89,by Incorporating Changes Increasing RWST low-level Setpoint from Greater than But Equal to 40% to Greater than But Equal to 45% of Span1999-10-22022 October 1999
Forwards Responses to Questions by NRC Re Application for Amends to Licenses NPF-87 & NPF-89,by Incorporating Changes Increasing RWST low-level Setpoint from Greater than But Equal to 40% to Greater than But Equal to 45% of Span
TXX-9923, Forwards Monthly Operating Repts for Sept 1999 for CPSES, Units 1 & 2,per Plant TS 5.6.4.No Failures of Challenges to PORVs of SV for Units Occurred1999-10-15015 October 1999
Forwards Monthly Operating Repts for Sept 1999 for CPSES, Units 1 & 2,per Plant TS 5.6.4.No Failures of Challenges to PORVs of SV for Units Occurred
ML20217E7951999-10-12012 October 1999
Forwards COLR for Unit 1,Cycle 8,per TS 5.6.5
ML20216J5571999-10-0101 October 1999
Provides Final Response to GL 98-01,suppl 1, Y2K Readiness of Computer Sys at Npps
TXX-9922, Forwards Revised COLR, for Cycle 5 for Unit 21999-10-0101 October 1999
Forwards Revised COLR, for Cycle 5 for Unit 2
ML20212G0721999-09-24024 September 1999
Forwards Rev 4 to Augmented Inservice Insp Plan for CPSES, Unit 1. Future Changes & Revs to Unit 1 Augmented Inservice Insp Plan Will Be Available on Site
ML20212H0461999-09-24024 September 1999
Forwards Rev 6 to CPSES Glen Rose,Tx ASME Section XI ISI Program Plan for 1st Interval on 990820
TXX-9921, Suppls 981221 LAR 98-010 to Licenses NPF-87 & NPF-89, Clarfying Conditions of Use Re Analytical Methods Used to Determine Core Operating Limits,Per Telcon with NRC1999-09-10010 September 1999
Suppls 981221 LAR 98-010 to Licenses NPF-87 & NPF-89, Clarfying Conditions of Use Re Analytical Methods Used to Determine Core Operating Limits,Per Telcon with NRC
ML20211L9871999-09-0303 September 1999
Forwards Rev 31 to Technical Requirements Manual. All Changes Applicable to Plants Have Been Reviewed Under Util 10CFR50.59 Process & Found Not to Include Any USQs
TXX-9915, Responds to 990701 & 0825 RAI Telcons Re Spent Fuel Pool Temp,Per LAR 98-008,which Requested Increase in Spent Fuel Storage capacity.Marked-up Page 4-1 of CPSES Fuel Storage Licensing Rept, Encl1999-09-0303 September 1999
Responds to 990701 & 0825 RAI Telcons Re Spent Fuel Pool Temp,Per LAR 98-008,which Requested Increase in Spent Fuel Storage capacity.Marked-up Page 4-1 of CPSES Fuel Storage Licensing Rept, Encl
ML20211K2231999-08-31031 August 1999
Forwards Txu Electric Comments of Rvid,Version 2
ML20211G1081999-08-26026 August 1999
Responds to NRR Staff RAI Re Util Mar 1999 Submittal for NRC Review & Approval of Changes to CPSES Emergency Classification Procedure
ML20211G7301999-08-26026 August 1999
Forwards Revs 29 & 30 to CPSES Technical Requirements Manual (Trm). Attachments 1 & 2 Contain Description of Changes for Revs 29 & 30 Respectively
ML20211G3441999-08-25025 August 1999
Forwards Response to NRC RAI on LAR 98-010 for Cpses,Units 1 & 2.Communication Contains No New Licensing Commitments Re Cpses,Units 1 & 2
ML20210U3981999-08-17017 August 1999
Forwards Monthly Operating Repts for July 1999 for CPSES, Units 1 & 2,per TS 6.9.1.5.No Failures or Challenges to PORVs or SVs for Plant Occurred
ML20211C0991999-08-17017 August 1999
Forwards Rev 3 to ASME Section XI ISI Program Plan,Unit 2 - 1st Interval, Replacing Rev 2 in Entirety
TXX-9919, Forwards Relief Request A-3,Rev 1 to Unit 1 ISI Program,Per Conversations Between NRC & Txu Electric on 9908021999-08-16016 August 1999
Forwards Relief Request A-3,Rev 1 to Unit 1 ISI Program,Per Conversations Between NRC & Txu Electric on 990802
ML20210R6561999-08-13013 August 1999
Forwards Response to NRR 990805 Telcon RAI Re License Amend Request 98-010,to Increase Power for Operation of CPSES Unit 2 to 3445 Mwth & Incorporating Addl Changes Into Units 1 & 2 TS
ML20210S6411999-08-12012 August 1999
Informs That Wg Guldemond,License SOP-43780,is No Longer Performing Licensed Duties.Discontinuation of License Is Requested
ML20210N1101999-08-0404 August 1999
Provides Supplemental Info to Util 990623 License Amend Request 99-005 Re Bypassing DG Trips.Info Replaces Info Contained in Subject Submittal in Attachment 2,Section II, Description of TS Change Request
TXX-9918, Forwards CPSES 10CFR50.59 Evaluation Summary Rept 0008,for 970802-990201 & CPSES Commitment Matl Change Evaluation Rept 0003,for 970802-9906301999-08-0202 August 1999
Forwards CPSES 10CFR50.59 Evaluation Summary Rept 0008,for 970802-990201 & CPSES Commitment Matl Change Evaluation Rept 0003,for 970802-990630
ML20210J2301999-08-0202 August 1999
Forwards Amend 96 to CPSES Ufsar.Replacement of FSAR Figures with Plant Process Flow Diagrams Meets Intent & Requirements of NRC Reg Guide 1.70,Rev 2
ML20210J6071999-08-0202 August 1999
Forwards line-by-line Descriptions of Changes in Amend 96 to CPSES UFSAR Transmitted by Util Ltr TXX-99166,dtd 990802. Replacment of FSAR Figures with Plant Process Flow Diagrams Meets Intent & Requirements of NRC Reg Guide 1.70,rev 2
TXX-9916, Notifies NRC That CPSES Units 1 & 2,improved TS Implemented on 9907271999-08-0202 August 1999
Notifies NRC That CPSES Units 1 & 2,improved TS Implemented on 990727
ML20210G5861999-07-29029 July 1999
Forwards fitness-for-duty Program Performance Data for Six Month Period of Jan-June 1999
ML20210J0121999-07-27027 July 1999
Forwards Summary of Methodology for Determination of NDE Measurement Uncertainty,In Response to Recent Discussions with NRC Re LAR 98-006 Concerning Rev to SG Tube Plugging Criteria
TXX-9917, Provides Info Re Augmented Inservice Insp Plan,Which Requires Periodic Insp of Rv Head & Internals Lifting Devices at CPSES1999-07-26026 July 1999
Provides Info Re Augmented Inservice Insp Plan,Which Requires Periodic Insp of Rv Head & Internals Lifting Devices at CPSES
ML20210F3121999-07-26026 July 1999
Responds to GL 99-02, Laboratory Testing of Nuclear-Grade Activated Charcoal,
ML20210C2931999-07-21021 July 1999
Supplements 880323 Response to NRC Bulletin 88-02, Rapidly Propagating...Sg Tubes, Non-proprietary WCAP-15010 & Proprietary Rev 0 to WCAP-15009, CP Unit 1 Evaluation for Tube Vibration... Encl.Proprietary Rept Withheld
ML20210D3211999-07-21021 July 1999
Provides List of Estimates of Licensing Actions,In Response to Administrative Ltr 99-02,dtd 990603
ML20209H2551999-07-16016 July 1999
Forwards ISI Summary Rept for Fourth Refueling Outage of CPSES Unit 2 & Containment ISI Summary Rept for Fourth Refueling Outage of CPSES Unit 2,per ASME Boiler & Pressure Vessel Code,Section Xi,Paragraph IWA-6230
ML20209H0111999-07-16016 July 1999
Forwards Relief Request C-4 to CPSES Unit 2 ISI Program for Approval
ML20209G0721999-07-13013 July 1999
Forwards Monthly Operating Repts for June 1999 for CPSES, Units 1 & 2,per TS 6.9.1.5.No Failures or Challenges to PORVs of SV Occurred During Reporting Period
ML20209F0681999-07-0909 July 1999
Informs That Effective 990514,TU Electric Formally Changed Name to Txu Electric.Change All Refs of TU Electric to Txu Electric on Correspondence Distribution Lists
ML20209E0421999-07-0909 July 1999
Forwards Response to NRC Request for Addl Info on LAR 98-010.Attachment 1 Is Affidavit for Info Supporting LAR 98-010
ML20209B6021999-06-30030 June 1999
Submits Second Response to NRC GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Npps. Readiness Disclosure for Reporting Status of Facility Y2K Readiness Encl
ML20195J6981999-06-15015 June 1999
Provides Addl Info Related to Open Issue,Discussed in 990610 Conference Call with D Jaffe Re ISI Program Relief Request L-1 Submitted by Util on 980220
ML20196A4921999-06-15015 June 1999
Forwards Rev 30 to Physical Security Plan.Rev Withheld,Per 10CFR73.21
ML20195J0491999-06-14014 June 1999
Submits Response to RAI Re Implementation of 1.0 Volt Repair Criteria
ML20195J0651999-06-14014 June 1999
Submits Response to RAI Re GL 95-07, Pressure Locking & Thermal Binding of Safety Related Power Operated Gate Valves
05000445/LER-1999-001, Forwards LER 99-001-00, Some Electrical Contacts for RCS Pressure Relief Valves Were Not Included in Surveillance Testing Procedures. New Licensing Commitments Identified in Attachment 11999-06-0808 June 1999
Forwards LER 99-001-00, Some Electrical Contacts for RCS Pressure Relief Valves Were Not Included in Surveillance Testing Procedures. New Licensing Commitments Identified in Attachment 1
ML20195F0091999-06-0808 June 1999
Forwards Response to RAI Re Units 1 & 2 ISI Program for Relief Requests E-1 & L-1.Communication Contains No New Licensing Basis Commitments Re Cpses,Units 1 & 2
ML20207E1921999-05-28028 May 1999
Submits Updated Request for NRC Staff to Review & Approve Certain Changes to CPSES Emergency Plan Submitted in 981015 & s Prior to Changes Being Implemented at CPSES
ML20207E1711999-05-28028 May 1999
Supplements 990526 LAR 99-004 as TU Electric Believes Extingency Exists in That Proposed Amend Was Result of NOED Granted to Prevent Shudown of CPSES Unit 1
ML20207D9841999-05-26026 May 1999
Requests That NRC Exercise Enforcement Discretion to Allow Cpses,Unit 1 to Remain in Mode 1,power Operation,Without Having Performed Svc Test,Per SR 4.8.2.1d on Unit 1 Battery BT1ED2
ML20195B6351999-05-25025 May 1999
Submits Response to RAI Re GL 95-07, Pressure Locking & Thermal Binding of Safety Related Power Operated Gate Valves
TXX-9912, Forwards Txu Electric (Formerly TU Electric) CPSES Emergency Preparedness Exercise Scenario Manual for 990721-22,Graded Exercise1999-05-21021 May 1999
Forwards Txu Electric (Formerly TU Electric) CPSES Emergency Preparedness Exercise Scenario Manual for 990721-22,Graded Exercise
ML20206U1981999-05-20020 May 1999
Forwards Form 10K Annual Rept,Per 10CFR50.71(b). Communication Contains No New Licensing Basis Commitments Re Cpses,Units 1 & 2
ML20196L1931999-05-20020 May 1999
Forwards MOR for Apr 1999 for Cpses,Units 1 & 2.During Reporting Period There Have Been No Failures or Challenges to Power Operated Relief Valves or Safety Valves
TXX-9911, Forwards non-proprietary & Proprietary Responses to RAI Re LAR 98-010 by Incorporating Attached Changes Into CPSES Unit 2 OL NPF-89 & CPSES Units 1,OL NPF-87 & 2 TS to Increase Licensed Power.W & Caldon Proprietary Responses Withheld1999-05-14014 May 1999
Forwards non-proprietary & Proprietary Responses to RAI Re LAR 98-010 by Incorporating Attached Changes Into CPSES Unit 2 OL NPF-89 & CPSES Units 1,OL NPF-87 & 2 TS to Increase Licensed Power.W & Caldon Proprietary Responses Withheld
1999-09-03
[Table view]
Category:UTILITY TO NRC
MONTHYEARML20059K6141990-09-17017 September 1990
Submits Documentation of 900906 Telcon Re Addl Util Candidate for Licensed Operator Generic Fundamentals Exam Section
ML20059G8761990-09-10010 September 1990
Forwards Rev 8 to Physical Security Plan.Rev Withheld (Ref 10CFR73.21)
ML20059F8461990-09-0404 September 1990
Responds to NRC Re Violations Noted in Insp Repts 50-445/90-22 & 50-446/90-22 on 900606-0705.Corrective action:OPT-467A Changed to Provide Addl Prerequisite Info Re Solid State Protection Sys Switch Lineup During Testing
ML20059E4981990-08-31031 August 1990
Forwards Revised Radial Peaking Factor Limit Rept for Cycle 1 Per Tech Specs Through Amend 1 &
ML20059E4201990-08-30030 August 1990
Forwards Objectives & Guidelines for 1990 Emergency Preparedness Exercise Scheduled for 901113
ML20028G8281990-08-29029 August 1990
Forwards Comanche Peak Unit 1 Semiannual Radioactive Effluent Release Rept,900403-0630 & ODCM
TXX-9030, Forwards Endorsements 40 & 4 to Nelia Policy NF-274 & Maelu Policy M-90,respectively & Endorsements 10,11,12,13,14 & 15 to Maelu Policy MF-1311990-08-27027 August 1990
Forwards Endorsements 40 & 4 to Nelia Policy NF-274 & Maelu Policy M-90,respectively & Endorsements 10,11,12,13,14 & 15 to Maelu Policy MF-131
ML20059F4381990-08-23023 August 1990
Forwards Public Version of Revised Emergency Plan & Corporate Emergency Response Procedures,Consisting of Rev 1 to EPP-313,Rev 7 to CERP-101,Rev 7 to CERP-102 & Revised Forms.W/Dh Grimsley 900906 Release Memo
TXX-9029, Responds to NRC Re Violations Noted in Insp Repts 50-445/89-57 & 50-446/89-57.Corrective Actions:Storage Facilities for Instrumentation & Control Work Packages Improved to Provide Acceptable Protection for Documents1990-08-20020 August 1990
Responds to NRC Re Violations Noted in Insp Repts 50-445/89-57 & 50-446/89-57.Corrective Actions:Storage Facilities for Instrumentation & Control Work Packages Improved to Provide Acceptable Protection for Documents
ML20058P0571990-08-13013 August 1990
Forwards, Comanche Peak Steam Electric Station Unit 1 Control Room Simulator 10CFR55 Certification Initial Rept
ML20058N2311990-08-0909 August 1990
Forwards First Half 1990 fitness-for-duty Program Performance Data,Per 10CFR26.71(d).Point of Contact for Personnel,Random Testing Program Results & Confirmed Positive Tests Summary & Mgt Summary Included in Data
ML20059A5831990-08-0404 August 1990
Responds to Info Request Made During 900802 Meeting Re Inadvertent Safety Injections on 900726 & 30 & Results of 100% Power Plateau Testing
TXX-9024, Provides Status of Exam Activity & Revised Completion Schedule for Portion of Exam.Util Deferred Preoperational Testing of Facility Spent Fuel Pool Cooling & Cleanup Sys Until Prior to First Off Loading of Spent Fuel1990-08-0303 August 1990
Provides Status of Exam Activity & Revised Completion Schedule for Portion of Exam.Util Deferred Preoperational Testing of Facility Spent Fuel Pool Cooling & Cleanup Sys Until Prior to First Off Loading of Spent Fuel
TXX-9022, Forwards Detailed Descriptions of Changes in Amend 79 to FSAR for Comanche Peak Steam Electric Station1990-07-31031 July 1990
Forwards Detailed Descriptions of Changes in Amend 79 to FSAR for Comanche Peak Steam Electric Station
TXX-9027, Responds to NRC Re Violations Noted in Insp Repts 50-445/90-19 & 50-446/90-19.Corrective Action:Specific Activity within Tech Spec Limits.No Further Corrective Action Required1990-07-30030 July 1990
Responds to NRC Re Violations Noted in Insp Repts 50-445/90-19 & 50-446/90-19.Corrective Action:Specific Activity within Tech Spec Limits.No Further Corrective Action Required
ML20055J1571990-07-27027 July 1990
Submits Info Re Replacement of Borg-Warner/Intl Pump,Inc Check Valve Swing Arms,Per .Swing Arms in ASME Code Class 2 Check Valves Will Be Replaced During First Refueling Outage
ML20056A0461990-07-24024 July 1990
Requests Regional Waiver of Compliance for Containment Pressure Transmitter 1-PT-934 During Coming Outage
TXX-9023, Responds to NRC Bulletin 90-001, Loss of Fill-Oil in Transmitters Mfg by Rosemount. No Subj Transmitters in Existence at Facility1990-07-18018 July 1990
Responds to NRC Bulletin 90-001, Loss of Fill-Oil in Transmitters Mfg by Rosemount. No Subj Transmitters in Existence at Facility
ML20055G6351990-07-17017 July 1990
Submits Results of Remote Shutdown Panel Environ Survey
ML20055F9391990-07-13013 July 1990
Advises That Operators Have Gained Significant Experience in Operating Plant Under Wide Range of Conditions & Have Demonstrated Necessary Proficiency to Safely Operate Unit
ML20055F9371990-07-13013 July 1990
Submits Info Re Revised Acceptance Criteria for THERMO-LAG Fire Barrier,Per 900705 Telcon.On Exposure to Heat Flux at Surface of Barrier,Listed Mechanisms Activated.Fire Testing Demonstrates That Panels Qualified W/Variation in Thickness
ML20044A7001990-06-26026 June 1990
Responds to Generic Ltr 90-04, Request for Info on Status of Licensee Implementation of Generic Safety Issues Resolved W/Imposition of Requirements or Corrective Actions. Util Will Implement for Unit 2 Activities Performed for Unit 1
ML20044A1411990-06-20020 June 1990
Forwards Endorsements 4 & 5 to Nelia Certificate N-90, Endorsements 5 & 6 to Maelu Certificate M-90 & Endorsements 34,35,36,37,38 & 39 to Nelia Policy NF-274
ML20043H7031990-06-18018 June 1990
Discusses Mod/Rework to Auxiliary Feedwater Sys Check Valves Mfg by Bw/Ip Intl,Inc.All But One Affected Check Valve modified.Motor-driven Auxiliary Feedwater Pump Discharge Valve Check Valve Body Replaced
ML20043H2181990-06-15015 June 1990
Forwards Response to 900515 Request for Addl Info on Emergency Preparedness.Ongoing Emergency Preparedness Programs Address Concerns Raised by Citizens for Fair Util Regulation
ML20043G3131990-06-15015 June 1990
Forwards Addl Info Re Pressurizer Surge Line Thermal Stratification & leak-before-break Evaluation & Nonproprietary Suppl 3 to WCAP-12247, Supplementary Assessment... & Proprietary Suppl 3 to WCAP-12248
ML20043C5671990-06-0101 June 1990
Discusses Identification of Slave Relays Tested Using Alternative Methodology,Per 900402 Commitment.Encl Tabulation Identifies Test Type,Applicable Procedures & Equipment & Impact of Improper Documentation
ML20043E7131990-06-0101 June 1990
Responds to NRC 900517 Notice of Violation & Imposition of Civil Penalty in Amount of $25,000.Corrective Action:Qc Mgt Counseled Level III Inspector & QC Supervisor on Importance of Good Communications W/Receipt Inspectors
ML20043C4501990-05-31031 May 1990
Advises That Util Revised FSAR Section 15.1.2 & Question/ Response 32.108,per 10CFR50.59
ML20043B5471990-05-25025 May 1990
Provides Status of Facility Design & Const Activities,Per Request.Detailed Design Work Will Resume in June 1990.Const Activities Expected to Increase Signficantly by Jan 1991
ML20043B5481990-05-23023 May 1990
Provides Clarification of 890710 Commitment Re Power Ascension Program.Cooldown Portion of Remote Shutdown Test Performed During Preoperational Testing,Per FSAR & Reg Guide 1.68.2
ML20043D1711990-05-21021 May 1990
Forwards Public Version of Revised Emergency Plan Procedures,Including Rev 8 to EPP-109,Rev 7 to EPP-112,Rev 4 to EPP-116 & Rev 6 to EPP-121.W/DH Grimsley 900604 Release Memo
TXX-9018, Advises of Completion of Implementation of Requirements of Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety- Related Equipment1990-05-21021 May 1990
Advises of Completion of Implementation of Requirements of Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety- Related Equipment
ML20043B0981990-05-15015 May 1990
Forwards Radial Peaking Factor Limit Rept for Cycle 1, Containing F(Xy) Limits for All Core Planes Containing Bank D Control Rods & All Unrodded Core Planes
ML20042F2851990-05-0303 May 1990
Supplemental Response to Generic Ltr 90-01, Request for Voluntary Participation in NRC Regulatory Impact Survey.
ML20042F3861990-05-0303 May 1990
Responds to NRC 900410 Ltr Re Violations Noted in Insp Repts 50-445/90-10 & 50-446/90-10 on 900206-07 & 0226-0302. Corrective Action:Memo Issued Emphasizing That Discrepancies Should Be Brought to Attention of Site Organizations
ML20042F3021990-05-0202 May 1990
Responds to NRC 900402 Ltr Re Violations Noted in Insp Repts 50-445/89-23 & 50-446/89-23.Util Does Not Believe That Circumstances Described in 900402 Ltr Constitutes Violation of 10CFR50.9(a)
ML20042F3051990-05-0202 May 1990
Provides Revised Response to Generic Ltr 88-17 Re Loss of DHR
ML20042E4581990-04-12012 April 1990
Responds to Inconsistencies in Terminology & Labelling Identified During NRC 890118 & 19 Audit of Facility Dcrdr. Util Believes Control Room Inventory Requirement of Suppl 1 to NUREG-0737,satisfied
ML20042E0701990-04-10010 April 1990
Discusses 900305 Meeting W/Nrc in Rockville,Md Re Offsite Power Availability for Automatic Switch Co Solenoids for MSIV in Event of Nonmechanistic Main Steam Line Crack in Superpipe Region
ML20012F5011990-04-0303 April 1990
Forwards Corrections to 891016 Response to Emergency Diesel Generator Engine Requirements.Lengths of Two Pairs of Bolts Above Crankpin Shall Be Measured Ultrasonically Before Detensioning & Disassembly of Bolts
ML20012F3221990-04-0202 April 1990
Discusses ESF Sys Slave Relay Alternate Test Methodology. Implementation Schedule for Design Mods to Relay Will Be Submitted by 900601
ML20042D8081990-03-29029 March 1990
Forwards Proposed Change to FSAR Section 13.4 Re Station Operations Review Committee.Similar Change Submitted in 900328 Ltr for Chapter 6 of Facility Tech Specs
ML20012F0411990-03-28028 March 1990
Forwards marked-up Pages of Facility Draft Tech Specs & Bases (NUREG-1381) Provided W/Low Power OL
ML20012E6051990-03-27027 March 1990
Forwards Endorsements 1-4 to Maelu Certificate M-90, Endorsements 1-9 to Maelu Policy MF-131,Endorsements 29-33 to Nelia Policy NF-274 & Endorsements 1-3 to Nelia Certificate N-90
ML20012E6531990-03-27027 March 1990
Provides Final Response to Reporting Requirement 2 of NRC Bulletin 88-008, Thermal Stresses in Piping Connected to RCS, for Unit.Nde Requirements of Action 2 Not Considered Applicable to Unit
ML20012E1911990-03-23023 March 1990
Forwards Comanche Peak Steam Electric Station Unit 1 Cycle 1 Startup Physics Tests Control Rod Worth Predictions Utilizing TU Electric Control Rod Swap Methodology.
ML20012E1581990-03-23023 March 1990
Clarifies 880624 Response to NRC Generic Ltr 88-05, Boric Acid Corrosion of Carbon Steel Reactor Pressure Boundary Components in PWR Plants.
ML20012D0201990-03-19019 March 1990
Advises That Allegations Provided to NRC by Former Util Employee Unsubstantiated,Based on Investigation by Util Safeteam Organization
ML20012E2181990-03-19019 March 1990
Responds to Generic Ltr 89-19 Re USI A-47, Safety Implication of Control Sys in LWR Nuclear Power Plants. Util Determined That Loss of safety-related Inverters 1 or 2 Would Involve Coincidental Opening of Main Feedwater Valves
1990-09-04
[Table view] |
Text
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log # TXX 90217 file # 10035 C Gl.90 04 1RIELECTRIC R ' " * *C ' R* * ' *
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wiisi m J. 0.hm. Jr,
- o. nw,a to e nus,,o U 5. Nuclear Regulatory Commission Attn: Document Control Desk i Washington, DC 20555 SUDJECT: C0HANCHE PEAK STEAH ELECTRIC STATION (CPSES)
DOCKET NOS. 50 445 AND 50 446 RESPONSE TO GENERIC LETTER 90 04: RE0 VEST FOR l INFORMATION ON THE STATUS Of LICENSEE IMPLEHENTATION Of GENERIC SAFETY ISSUES (GSI) RESOLVED WITH '
IMPOSITION Of REQUIREMENTS OR CORRECTIVE ACTIONS Gentlemen:
Enclosed is the CPSES response to Generic letter 90 04. The response includes l the table entitled " Status of Licensee Implementation of Generic Status. Issues Resolved with imposition of Requirements or Corrective Actions" (Enclosure 1) i which has been marked up to indicate the CPSES status for each of the GSI's as requested, in addition. Enclosure 2.provides a listing of docketed correspondence related to the GSis and in some cases a brief explanation of the outstanding work.
i for those GSI's statused as incomplete in Enclosure 1, the dates correspond to CPSES current scheduled milestones (i.e.. GS! 99 Prior to end of first refuel outage for Unit 1/ Unit 2 fuel load, GSI A prior to initial. full power o"eration for Unit 2). The date indicated for colnpletion of Unit 2 activities, except that for GSI A 35, corresponds to CPSES current scheduled Unit 2 fuel load milestone.
Activities necessary to resolve each GSI were discussed in the CPSES correspondence related to each GSI and were discussed and accepted in NUREG 0797 Supplement No. 24. 10 Electric intends to implement for Unit 2 the same activities that were performed for Unit 1 (Enclosure 2). Host of these Unit 2 activities have not been completed because Unit 2 is still in the early stages of the re initiated design and construction activities.
9007020086 900624 PDR ADOCK 0D000440 ;400 wnh ouve Street Lit. si palla, Temu 75201 '
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TXX 90217 Page 2 of 2 Since the specifics of the Unit 2 GSI activities have been previously described in the referenced correspondence, a restatement of all of'these activities for this response is not necessary.
i Sincerely, RI.] h4]Af' )
By: 81 A 9)
Roder/D. Walker Manager of Nuclear Licensing -
RSB/vid Enclosures c Mr. R. D. Martin, Region IV Resident inspectors, CPSES (3) :
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Enclosure 1 to TXX-90217 _
Page 1 of 5 i
FACILITY NAK: CPSES Units I and 2 DOCKET fe.: 50-445 and 50-446 LICENSEE: IU Electric .
STATUS OF LICENSEE 19 FLEE NTATION OF GENERIC SAFETY ISSUES RESOLVED WITU IIFOSITION OF REQUIREENTS OR CORRECTIVE ACTIONS TITLE APPtICA9IlITY 5TATUS* COBOIENIS GSI/(SPA IIo.)
All SWRs NA 40 (9065) Safety Concerns Associated With Fipe Breaks In The BldR Scram System IRfR Scram Discharge Volume Systems All 9WRs NA 41 (8058) 43 (8107) Re!!:6ility Of Air Systems All Plants- .NC (Ul)
I (U2) 1/93 See Enc'esure 2 51 (L913) Improving the Reliability of All Plants . C (01) S/90 Open-Cycle Service Water Systems I (U2) 1/93 See Enclosure 2 67.3.3 (A017)- Improved Accident 90snitoring All Plants NC (UI)
I (U2) I/93 See Enclosure 2 75** (9076) Item 1.1 - Post-Trip Review All Plants g (Program Description and Procedure) 75 (9085)' Item 1.2 - Post-Trip Review - A' Plants NC Data and Info mstfon Capability
- P1sese follow attached guidance for completing this column.
- The 16 items listed for GSI 75 all relate to actions derived from the generic implications of Sales ATWS events. Item nes6ers ce..e C --2 to Generic Letter 83-28 action item numbers.
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Enclosure I to TXX-90217
- Page 2 of 5 GSI/(f5>A No.} TITLE APPLICABILITY STATUS
- CopeEENTS 75 (8077) Item 2.1 - Equipment Classi- All Plants NC fication and Vendor Interface (Reacter Trip System Camponents) 75 (8096) Item 2.2.1 - Espsipment Classiff- All Plants NC (U1) cation for Safety-Related e J u..ts I (U2) 1/93 See Enclosure 2 75 (L903) Item 2.2.2 - Vender Interface All Plants NC -
for Safety-Belated Ceaponents 75 (9078) Items 3.1.1 & 3.1.2 - Post - All Plants NC (U1)
Waintenance Testing (Reactor I (U2) 1/93 See Enclosure 2 Trip System Companants) 75 (8079) Item 3.1.": - Post-Maintenance All Plants NC (01)
Testing-Changes to Test Regpstre- I (U2) 1/93 See Enclosure 2 monts (Reacter Trip System Components) 75 (9087) Items 3.2.1 & 3.2.2 - Post- All Plants NC (01) '/
Maintenance Testing (All Other I (U2) 1/93 See Enclosure 2 Safety-Related Ceaponents) 75 (9088) .
Item 3.2.3 - Post-Maintenance .All Plants NC Testing-Changes to Test Require-nents (All Other Safety-Related Ceaponents) 75 (8000) Itee 4.1 - Reactor Trip System All Plants NC (UI)
Reliability (Vendor-Related I (U2) 1/13 See En losure 2 Modifications)
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Page 3 of 5 GSI/(MPA No.) . TITLE APPLI N ILITY STATUS
- COBOWETS 75 (8081) Items 4.2.1 & 4.2.2 - Reactor All PWRs NC Trip Systee Reliability-Maintenance and Testing (Preventative Maintenance and Surveillance Program for Reactor Trip Breakers) -
75 (8082) Ites 4.3 - Reactor Trip System All W and 88W NC Reliability - Design Modifications . Plants (Automatic Actuation of.-Shunt Trip Attachment for Westlaghouse and 88W Plants) -
75 (8090) Item 4.3 - Reector Trip System All W & 88W NC Reliability - Tech Spec Changes Plants (Auteentic Actuation of Shunt-Trip Attachment For Westinghouse and 88W Plants). ?
75 (80s' J Ites 4.4 ' Reactor Trip System All 88W Plants NA Reliability'(Improvements in
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Maintenance and Test Procedures for 88N Plants) k
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Enclosure.1 to TXX-90217. ~'
- Page"4 of 5.
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GSI/(MPA No.) TITLE APPLICABILITY ' STATtFS* C0f9ENTS 75 (8092) Ites 4.5.1 - Reactor Trip System All Plants NC Reliability-Diverse Trip Features (System Functional Testing.)
75 (B093) Items 4.5.2 & 4.5.3 - Reactor Trip All' Plants NC (U1)
System Reliability - Test Alterna- f (U2) 1/93 See Enclosure'2 tives and Intervals'(System Functional Testing) 86 (8084) long Range Plan for Dealing All BWRs NA with Stress Corrosion =
Cracking in SWR ~ Piping.
93 (8098) Steam Binding of Auxiliary All PWRs NC (U1) ..
Feedwater Pumps I (U2) 1/93 See Enclosure 2 99 (L817) RCS/RHR Suction Line Valve All PWRs I (01) 7/91 Interlock on PWRs I (U2) 1/93 See Enclosure 2 124 Auxiliary Feedwater System AND-1&2, Rancho
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'NA Reliability Seco,-Prairie Island 1&2, Crystal River-3 Ft. Calhoun A-13 (8017) -Snubber Operability Assurance - All Plants NC (U1)
Hydraulic Snubbers I (U2) 1/93 See Enclosure 2
I i Enc 1'osure 1 to TXX-90217 "
Page 5 of. 5 GSI/(MPA flo.) TITLE APPLICABILITY STATUS
- COWitTS A-13 (8022) Snubber Operablifty Assurance - All Plants N Mechanical Snebbers U 1/93 See Enclosure 2 A-16 (0012) Steam Effects on SWR Core Oyster Creek NA-Spray Distribution & 88F-1 A-35 (8023) Adequacy of Offsite Power All Plants NC-(U1)
Systems I (U2) 6/93 See. Enclosure 2 B-10 Behavior of BWR Mark III All BWR Mark III NA Containments Plants B-36 Develop Design, Testing and .All Plants with NA Maintenance Criterfa for OL Applications Atmospheire Cleanup System After 4/1/9a -
Air Filtration and T A .ption Units for Engineered Safety Features Systems and for 16ernal Ventilation Systems B-63 (8045) ' Isolation of Lou' Pressure All Plants NC (U1)
Systems Connected to the Reactor Coolant System Pressure I (U2) 1/93 See Enclosure 2 Boundary 4
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.- .. Ent1osuro 2 to TXX 90217 PageL1 of 2 Q31/iMPA NO.) STATUS - COMMENTS 43 (B107) NC (U1) TXX 89052, dated 02/06/89 I (U2) 1/93 TXX 89191, dated 05/11/89 TXX 89461, dated 07/31/89 TXX 89561, dated 08/09/89 51 (L913) C (U1) 5/90 TXX-90186c dated 05/21/90 (U1 only)-
I (U2) 1/93- TXX 90031, dated 01/26/90 t
67.3.3 (A017) NC (U1) TXX 3639, dated 03/08/83 I (U2) 1/93 TXX 4646, dated 12/16/85 TXX 88096, dated 01/22/88 TXX-89253, dated 05/19/89 TXX 89409, dated 06/16/89 75 (B086) NC (U1) TXX-88397, dated 05/20/88 I (U2) 1/93 75 (B078)
NC (U1) TXX 4071, dated 11/03/83 I (U2) 1/93 1
75 (0079) NC (U1) TXX 4071, dated 11/03/83 i I (U2) 1/93 TXX-4486, dated 06/07/85 .'
TXX-4526, dated 08/19/85 !
75 (8087) NC (01) TXX 4071, dated 11/03/83 1 (U2) 1/93 TXX 4828. dated 06/02/86 75 (8080) NC (U1) TXX-4071, dated 11/03/83 !
! (U2) 1/93 TXX 4486, dated 06/07/85-75 (8093) NC (U1) ' TXX-4071, dated 11/03/83 I (U2) 1/93 TXX-4486,-dated 06/07/85 93 (B098) NC (U1) TXX-88456, dated 05/17/88 l I (U2) 1/93 99 (L817) I (U1) 7/91 All required changes and additions I (U2) 1/93 to the existing instrumentation-identified as a. result of the RHR site vortex evaluation-(TXX 89804) and the investigation to determine the feasibility of removing the auto closure interlocks for RHR suction valvus will'be completed'by the end of the first refueling outage for ,
Unit I and fuel load for Unit 2. !
TXX-88865, dated 12/21/88-TXX-89041, dated 02/10/89 TXX-89282, dated 06/01/89 i TXX-89804.cdated 11/20/89- {
TXX-90169, dated 05/02/90 J
A-13 (8017) NC (01) Issuance of Unit 2 Technical
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I (U2) 1/93 Specifications
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i . .. Erfclosure 2 to TXX 90217 Page 2 of 2 L GSI/(MPA NO.) STATUS COMMENTS A 13 (8022) NC (U1) Issuance of Unit 2 Technical I (U2) 1/93 Specifications A 35 (8023) NC (U1) Design same for both units. Voltage ,
I (U2) 6/93
. measurements will be performed prior !
to initial full power operation. i
' Set points for Unit 2_480V and 6.9kV- '
buses will be finalized with the issuance of Unit 2 Technical Specification:.
B-63 (B045) NC (U1) .
Issuance of th11t 2 Technical !
! (U2) 1/93 Specifications !
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