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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 TXX-9026, Forwards Addendum to Unit 1 Preservice Insp (PSI) Summary Rept, Providing Remaining Info & Editorial Corrections Re PSI & Addressing Exams & Tests of Code Class 1 & 2 Sys as Stipulated in PSI Plan1990-08-13013 August 1990 Forwards Addendum to Unit 1 Preservice Insp (PSI) Summary Rept, Providing Remaining Info & Editorial Corrections Re PSI & Addressing Exams & Tests of Code Class 1 & 2 Sys as Stipulated in PSI Plan 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 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 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 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 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 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 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 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 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 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 ML20042F3051990-05-0202 May 1990 Provides Revised Response to Generic Ltr 88-17 Re Loss of DHR 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) 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. ML20012D0151990-03-19019 March 1990 Responds to NRC 900216 Ltr Re Violation a Noted in Insp Repts 50-445/90-03 & 50-446/90-03.Corrective Actions: Groundwater Calculations Completed & Engineering Personnel Reminded of Procedural Requirements 1990-09-04
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'::. .lll: File # 10010
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August 4, 1990 a Weise J. Cats, Jr.
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Mr. R. D. Martin. t U. S. Nuclear Regulatory Commission ,
Region IV-
.611 Ryan Plaza Dr., Suite 1000 -
' Arlington, Texas 76011
SUBJECT:
COMANCHEPEAKSTEAMELECTRICSTATION(CPSES)
DOCKET No. S0-445 l
o RESPONSE TO INFORMATION REQUEST MADE DURING THE AUGUST 2, 1990 PUBLIC MEETING
Dear Mr. Martin:
On Aagust 2 1990 the imt cuaducted a Public Meetf 1 at CPSES to discuss the l inadvertent safety injection events which occurrec on July 26 and. July 30, 1990, and the results of'100% power platsau. testing. As a result of the discussions of the safety injection events, NRC representatives requested that. 1 TU Electric submit in-writing the results of its ongoing assessments of three ,
specific topics .at least 24. hours prior to entering Mode 3. . The three topics.
were: 1) the adequacy of installed emergency lighting with respect to regulatory and design requirements and.any actions necessary to establish complianr:e with those requirements; 2) the operability and reliability.of. Steam Generator Atmospheric Relief Valves (ARVs) and short term and/or long term ,
actions that will-be taken to address lany findings in this' area; and 3) t n pott.ntial personnel safety. hazards identified during the events including
- capability to evacuate personnel from containment and observed steam blowback during ART actuation.
L T .TU Electric has completed its assessments of each-of these topics with the-l, following results, i L'
-1. F"*rnancy Lichtine Adecuacy The lighting system at CPSES cotisists of three subsystems; normal ,
h, > . l lighting, which is powered from power supplies which are shed on a safety
*" tinjection er loss of offsite power; essential lighting, powered from yttal buses.which are automatically restored following a safety injection or loss of offsite power; and DC emergency lighting, which is powered from dedicated battery packs. Sufficient essential lighting is provided to assure that upon loss of normal lighting operators can perform essential
, functions as required. The emergency lighting in each area serviced .
' senses power availability to the essential lighting and comes on when 1
, power is not available to essential lighting in the serviced area.
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Our review of the _ design and installation of. these lighting subsystems 1 demonstrated that O,ey conform to existing regulatory and design ,
l ,- requirementt 'and TU Electric commitments. ,
s During tho' safety injection events of July 26 and 30, it was noted that 1 certain essential! lights were not energized and that the associated DC p
'~
emergency lights did-not come on. Investigation of.this condition: '
reveeld that power was available to;the essential'11ghts, but that the ;
lights had been turned off via local switenes. Becaus. m er.was .;
i_ -
available to the essential lights, the emergency lights did not come on. '
To address' this situation.in the longer ters, a design modification ~1s-being processed to remove the local switches for the essential. lights as-appropriate. Until. such time that this modification is fully implemented, ,
plant operators.have been instructed to assure that essential lighting is !
left on. '
2, ARV Ocarability and Reliabilit/ '
Review of the circunstances surrounding the malfunction of the ARV on the- '
Mo. 3 Storm Ge.terate,r on July 30, 1990 determined that the most probable '
cause was water ace,umulation on the upstream side of
- valve. This determinatior:has received preliminary concurrence ' the valve vendor.
The bases for this: determination include the follo.
-a. The ARV stcoked acceptably during the p n ascension test program,
- b. Th m were no outstanding-work requests at the time of the-malfva.: tion which documented conditions which could have contributed to the obierved behavior.
- c. There had been no work performed on the valve subsequent to its last successful stroke that could have contributed to its observed behavior,
- d. The Main Steam Isolation Valve (MSIV), the ARV, and the steam line drains on the No. 3 Steam Generator had been closed for at least 15 hours prior to the event. This allowed significant condensate to -
collect in the steam line. 1
- a. When the ARV actuated, a significant quantity of water was observed coming out of the valve vent stack inlet as well as its outlet.
+ f. The observed. valve behavior was consistent with an accumulation of I water on.the upstream side of the valve. With water pressent on the I
. upstream side of the valve, initial opening of the internal pilot l valve would have allowed only e small quantity of fluid ~ to be passed 1
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-Page 3 of 4 l
through the valve. This would not result in.any.si "
. decrease in differential pressure across the valve.gnificant: . Since the ,
differential pressure across the valve opposes valve opening force, ;
valve opening.would-have been delayed. This, in turn,-caused the
~
valve actuator.to app .an increasing opening force on the valve-
, disk. As additional; uid passed through the valve and flashed to- :
. steam in the valve discharge,:a backpressure developed,' reducing the -
difforential pressure across.the valve and resulting in a greater not valve opening force. Eventually,,the force imbalance resulted :
in sudden valve opening and rapid reduction in steam line pressure.
l
- g. Subsequent to the event, the valve was successfully stroked.without indication of erratic behaviar, i
- h. Subsequent to the event, the valve and actuator were disassembled in :
the presence of the valve vendor. No evidence of valve damage or .
wear was observed which would have contributed to the behavior l observed during the event. Proper stroking of the valve will be l Verified prior to Mode 2 during plant restart. ,
To prevent recurrence of the conditions leading to this event, plant.
procedures are being revised to require periodic draining of the steam-lines under similar plant conditions. In addition, a review'of operations in Modes'3 and 4 is being conducted to detemine if other longer term actions are appropriate.
- 3. potential personnel Safety concerns The review of personnel safety concerns related to perscanal evacuation- !
from containment has determined that personnel could have been evacuated '
within 20 minutes through either the Normal or Emergency Air Locks, o
Testing on. August 3,1990 verified:that containment lighting following a safety injection;(SI) is adequate for personnel egress. P1 ant -Operations made a conscious decision, in comunication and agreement with:those individuals'inside containment, not to evacuate since they knew what 1
caused the'SI and expected the event:to be concluded quickly with normal power restored. The personnel in containment were not-in any cistress and they had no immediate concerns regarding their safety. ;
Our assessment' of the conditions associated with the. events did identify; that at least one individual in containment did understand how to operate the Emergency-Air Lock. However, a number of individuals did not fully.
understand this operation. As a result, job aids on how to use,the Normal and. Emergency Air Locks.are being developed 'o place near the Additionally, we are continuing to evaluate whether vital powe? locks.
r should be j provided to the hydraulic operating system on the Normal Air Lock. Prior to startup the-Emergency Operating Procedures will be revised to provide l additional direction:on the' expeditious removal of personnel from i containment '
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# g.q *' page 4.of 4 The blowback from the ARY ventLwas a steam and water mixture. The vent is . ,
' designed to pass' steam and normally would not contain water.~ .The presence?
of. water restricted flow through the vent, contributing:to the blowback. :
This is confirmed by the absence of: blowback during previous valve operations.. The actions described above to. reduce the accumulation of-condensate in the steam lines will minimize the potential for future 3 blowback. Blowback would.not nonaally represent a personnel safety; hazard, as during plant operation,- the area is not occupied and the only:
personnel in this ' area would be watch standers making periodic rounds. It was recognized some time.ago that manual' closure of an ARY would expose the~individuali As a' result, th. operating the valve to adverse environmental- conditions.
e ARV block valves are located outside the ARY room. : Plant procedures en being modified to reinforce the'use of the block valve.
instead of trying to close' the ARV at the ARV itself.
?
. Based on the results of our assessments and the actions.taken as described above, we have concluded that these-issues have been addressed sufficiently.
.g, such that-plant startup may proceed safely.
If you have any questions on- these matters, pleast contact me.
Sincerely,
/1 William-J. Cahill, 'Jr.
,f.
L' l WGG/dai c Mr. T. P. Gwynn, Region IV Mr.-L. J. Callan, Region IV Mr.: D.: D. Chamberlaim, Region IV Mr. C. I. Grimes, NRR L
Mr.LJ. H. Wilson, NRR -
- Resident! Inspectors,CPSES(3)
-Document Control Desk l
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, INITIAL CONDITIONS-1; i
- o' MODE.3,.SHORT MAINTENANCE OUTAGE l' ' ;6
, o= RCS TEMPERATURE - 558 F-
-. s PRESSURE-- 2250 PSI ?!
o PRESSURIZER LEVEL -'25%
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. o. STEAli GENERATOR PRESSURE- 1120 PSI. ,
1 o'- .RCP'S RUNNING-
-o' MSIV'S CLOSED l
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, .o CLEARANCES BEING HUNG FOR' MAINTENANCE w :o -I'SIV'S-TAGGED CIDSED FOR SECONDARY' WORK K
p' o 'SdQUENCE'OF TAGGING IMPROPER t.' . o MSIV #4 AND #2 OPENED I i
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PLANT RESPONSE I o DECREASING STEAM GENERATOR PRESSURE RATE' INITIATED SIAS (1416) 7.
o OPERATORS RESPONDED PER EOP'S 1 o 'MSIV'S MANUALLY CLOSED LOCALLY Bi OPERATOR (1429) o SYSTEM RESPONSE i
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p - RCS TEMPERATURE' DECREASE TO 542 F L
- RCS PRESSURE DECREAS E TO 2170 PSI / j INCREASE TO 2330 PSC ,
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! - PRESSURIZER LEVEL DECREASE TO 18%/
INCREASE TO 87%
- STEAM GENERATOR:#4 PREESGRE. DECREASE
..TO 8501 PSI (182'IN 56 SECONDS) l o NOTIFICATION OF UNUSUAL"FVENT DECLARED (1420)
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PLANT RECOVERY I i.
o . OPERATOR RECOVERED PLANT-PER-EOP'S o SAFETY INJECTION' SIGNAL RESET (1432)- i o SAFETY INJECTION FLOW SECURED (1435) o EQUIPMENT' RESTORED.TO NORMAL MODE 3 '
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ALIGNMENTS E
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-INITIAL MANAGEMENT RESPONSE
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o . SUSPEND ALL UNNECESSARY TAGGING I o : FORM TWO INVESTIGATION TEAMS -
s REVIEW EVENT FOR PROPER PLANT, ->
EQUIPMENT,.AND PERSONNEL RESPONSE
, CONTINUE TO REVIEW CLEARANCE PROCESS I
o REMAIN IN MODE 3 .,.
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t- ' SEQUENCE OF TIGGING MSIV'S WAS IMPROPER i t
i.. o- REVIEW OF CLEARANCE NOT ADEQUATE g, s Li 'o- RESPONSIBILITIES FOR SEQUENCE REVIEW. .,
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V ROOT CAUSE CORRECTIVE' ACTIONS 1
o o REVIEW OF CLEARANCES NOT ADEQUATE
- CLAP.IFY SHIFT ORDER(COMPLETE)
- RESOLVE CLEARANCE DISCREPANCIES
' (COMPLETE)'
- REVISE ROTATION OF OPERATORS'IN SWCC
- DEVELOP ROUTINE CLEARANCES FOR. COMPLEX ACTIVITIES.
- ENHANCE' FLOW-DIAGRAM.
o RESPONSIBILITY ~FOR SEQUENCING NOT CLEAR
- CLARIFY RESPONSIBILITY FOR SEQUENCING DEVEIDPMENT = (COMPLETE)
- CLARIFY RESPONSIBILITY-FOR SEQUENCE
- ENHANCE COMPLEX CONTROL CIRCUIT LOGICS o FAULTY' PROCEDURE: INTERPRETATION ti
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- PROVIDE JOINT TRAINING ON? PROCEDURE .I CLARIFICATION (COMPLETE):
TAGGING PERMITTED-AFTER IDENTIFIED-CORRECTIVE ACTIONS WERE COMPLETED-i
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-i OTHER FINDINGS o EQUIPMENT RESPONDED PER DESIGN g
- MONITOR LIGHT BOX MALFUNCTIONED:
[ - LIGHTING IN MSIV-AREA INADEQUATE ,
- LETDOWN / SEAL RETURN RELIEF LIFTED
- - CONTAINMENT PERSONNEL HATCPDISABLED t 9
o EMERGENCY PLAN RESPONSE WAS' APPROPRIATE 2E o OPERATOR RESPONSE PER EOP'S.WAS 9 -APPROPRIATE
' --DECISION ON CONTAINMENT EVACUATION-
- ENHANCEMENT IN EOP'S FOR RESTORING'SIAS .
- IMPROVED ~ ABILITY:To LOCALLY CLOSE MSIV'S. '[.
o PLANT, RESPONSE BOUNDED-BY FSAR' a RCS. COMPONENT TRANSIENT' BOUNDED
.BY'THE INADVERTENT SAFETY INJECTION '
ACTUATION TRANSIENT j I
CORRECTIVE ACTIONS PRIOR TO STARTUP
- h. o' . REQUIRED CLEARANCE ENHANCEMENT COMPLETE h- o . FINAL RCS WALKDOWN AFTER RETURN TO
. NORMAL. OPERATING TEMPERATURE / PRESSURE. .
o CONFIRM MONITOR: LIGHT BOX PROBLEM I e i p
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JULY.26 JULY 30-SAFETY' INJECTION SAFETY INJECTION EVENT- EVENT o:1.
STEAM GENERATOR 270 PSI DECREASE
-PRESSURE 320 PSI' DECREASE RATE -182 PSI IN 56. SECONDS 20 PSI ONE~SECOND
' PRESS"",IZER 18%'TO 87%.
E LEVFL 55%TO74%
PRESSURIZER '2170 TO 2330-PRESSURE-2220-TO 2282
.i Tc ' LOOPS
, l', 2, 3) 17 F DECREASE 20 F DECREASE' -1 i
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b . AEMUST NUCLEAR WeSTRURENTATION 5 s0% - I 50%iOAD x - N-30 SvSTEM AruuSTwNr - REKCHON
. CONTROLSYSTERE AEMUSTRENT 40% - . CONTAgdhENT rYans nos 0F13998 j
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-TuRaoEJGEDIERATOR \ ESU
.gop PROGAMA 10% ~ .c - _.-
-RCS FLOUW REASUREasENT
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. CORE PHYSICS TESTW8G 0 -
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' 4 4-( T 07/13M10 07/tFfE0 L I 07/2390 - 07/24t50 07/24 idle - 07/30P50
;;DATE '*38
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.SIGNIFICANT RESULTS O
N16 System Performance O
RCS Flow Measurements -
0-132-HRS at'95 1007. Power
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' 1 0 4 Transient Response O' ,
, Plant Performance 1
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PROCESS RADIATION MONITORS !
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SPLIT-FLOW BYPASS
.I l." O STEAM / FEED FLOW RECALIBRATION O
FEEDW TER CONTROL VALVE POSITION 0
T REFERENCE RECAllBRATION
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I INITIAL STARTUP PROGRAM
SUMMARY
.I 1
THE INITIAL STARTUP FROGRAM ASSuREo: 1 1
0
-DEFERREo PRE 0P TESTS WERE PERFORMED; f
i FUEL LOAo WAS CONDUCTED IH A SAFE MANNER;- =
0 1 PLANT WAS-SAFELY BROUGHT TO RATED CAPACITY; f
0 PLANT PERFORMANCE IS SATISFACTORY IN TERMS-0F..
DESIGN.-CRITERIA)'AND "
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. O 1 PLANT IS CAPABLE OF-WITNSTANDING AND l RESPONDING-TO ANTICIPATED TRANSIENTS. l l
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'TU Electric' >
.w Honorable George Crump- !
County Judge Glen Rose, Texas 76043 :
-Texas Radiation Contro1LProgram Director '
l 1100 West 49th Street
-Austin, Texas 78756 ,
bectbDMB.(IE45).
bec distrib. by RIV:- .
.R.' D. Martin- Resident Inspector (2)
DRP DRS
-SectionChief(DRP/B)~ Project Engineer (DRP/B)'
DRSS-FRPS Lisa Shea, RM/ALF MIS System- RSTS Operator RIV' Files
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- a. iIn Reply Refer.To:'
Dockets: 50-445' )
- 50-446- i y
TV Electric ATTN: W. J. Cahill, Jr., Executive Vice President, Nuclear i Skyway Tower 400 North Olive Street, L.B. 81 j Dallas. Texas 75201 l Gentlemen:
This' refers to the technical maeting conducted at Region IV's request at the .
CNnanche Peak Steam Electric Station (CPSES) engineering building on August 2, I 1090. This meeting, which was open to put ic observation, related to activities. R authorized by NRC License No. NPF-87 for CPSES, Unit 1, and was attended by those'on the enclosed: Attendance List.
, The subjects discussed at this meeting are' described in the enclosed Meeting Sumary. As noted in that sumary, your letter of August 4,1990, which described actions completed or planned prior to restart of Unit 1, was reviewed by representatives of NRC Region IV and the Office of Nuclear Reactor Regulation-(NRR). As discussed with Mr. W. G. Guldemond of your staff on n August 4,1990, actions described in that letter were viewed as appropriate for J restart of the unit.
1 It is our opinion that this meeting ~was beneficial and has provided a better j understanding of the. events and issues presented.. In accordance with Section 2.790 of the NRC's " Rules of Practice," Part 2, Title 10, Code of ~ ,
l Federal Regulations, a copy of this letter will be placed in the NRC's Public Document Room.
L Should you have any. questions concerning this matter, we will be pleased to L discuss them with you.
Sincerely. 1 l
OddnalSigned By-Thomas P.Gwynn i I
L L Samuel J. Collins, Director ;
l' Division of Reactor Projects L
Enclosures:
As stated gl (7- 0
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y eflg/B D:DRS b 4 :DRP RIV:DR B .C:DRP l
CEJohnson;df DDChamberlain LJCallan y SJCollins fq L
-8/10/90 8//0/90 8/ p90 8/&/90 h, p.
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1-TV Electric .
4 f
cc W/ enclosures:~ 4
. TV Electric-
~ ATTN:; Roger D. Walker, Manager, s
Nuclear Licensing i
- Skyway. Tower t
- 400 North Olive Street, L.B. 81 Dallas,. Texas.-75201.
o Juanita Ellis
'" - President - CASE 1426 South Polk- Street ,
- Da11a's, Texas. 75224 GDS Associates, Inc; '
Suite 720 1850-Parkway Place' Marietta, Georgia: 30067-8237 ,
- Billie.Pirner Garde. Esq. -
Robinson, Robinson, et. al.
~
103 East College Avenue
' Appleton Wisconsin 54911 l TV Electric-Bethesda Licensing . I 3 Metro Center. Suite 610. I Bethesda, Maryland 20814-
' Heron, Burchette, Ruckert, & Rothwell ATTN: William A. Burchette, Esq .
y Counsel for-Tex-La Electric Cooperative of Texas 1025~ Thomas Jefferson St., N.W.
Weshington,.D.C. 20007 -
1 E. F. Ottney- _/)
P.O.. Box 1777 3 Glen Rose, Texas 76043 f
- Newman'&.Holtzinger, P.C.
1
. ATTN: _ Jack-R. Newman,1sq. i
- 1615.LaStreet,'N.W.
- Suite 1000 Washington, D.C. 20036 1
Texas Department of Labor'& Standards
~ ATTN:- G." R. Bynog, Program Manager /
- Chief Inspector
. Boiler Division
; P.O. Box 12157, Capitol. Station-
"r 1 Austin, Texas 78711 ]
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l Honorable George Crump -1 County Judge. y \
s = Glen Rose, Tehas= 76043 ;i .
Texas Radiation Control Program Director a 'l 1100 West ~49th Street '
' Austin, Texas 78756
, l
-bectoDMB(IE45) bec distrib. by RIV: s I ={"
Resident. Inspector (2)
R. D. Martin DRP . DRS .
.SectiorJChief(DRP/P) Project Engineer (DRP/8). ,' N DRSS-FRPS: Lisa Shea.: RM/ALF i
.. . ' MIS System. RSTS Operator ,
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h Enclosure 1 l 1- ;
i ATTENDANCE LIST 6
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Nttendance at the-technical meeting between TU Electric ana NRC 'on August 2 1990, .at Comanche Peak ' Steam' Electric Stat. ion:
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,TU Ele,ctric d G.-Stein Administrative and Technical Assistant
- 0. Goodwir,'J. Unit Supervisor .
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'J.; Donahue', Manager, Operations I,0PS)i 1
& a P. 2,'Stevens. Manager, OPS Support 1:ogineering
. i J. J. - Kelley, Plant Manager h4 b'A 8,' R. Blevins, Manager of Nuclear; Operations Support '
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S.: L. E1' sis,~ Performance &' Test Manager !
M' 1 A. 3. Scott, Vice President.- Nuclear:0PS :
W. 'J. Cahill.; Exec 0tiveiVice President l D. M. McAfeel Manager. Quality 'Assbrance dTh':
H C. L. Terry, ' Director. Quality Assurance i
. A. Husain Direct 4r, Reactor Engineering - q
, yi l f J. Muffett,-Manager of Project Engineering !
$' R..D. Walker . Manager of. Nuclear Licensing
!W., G, thldemand, Manager, Site Licensing
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'J. F. Streeter, Executive' Assistant M.;Manrog, Public.Information Supervisor.' ,
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, NRC ;. a
y N Pl Gkmh! Deputy Direc~or, Division of Reactor Projects (DRP). J
,l.;LJ.; CaRen, Director, Division of Reactor Safety t(DRS) ,
R (J. Db Chs e lain,' Chief,; Project Section B,0RP*
C. E. ;Johwx.,l. Project Engineer, DRP ' N W ' 9. i s'W. '
D.sJohnson, Senior Resider,t Inspector, DRP '
u M . 3. .D dlitter,' Resident 2nspector. .DRP t t
D i V A. :T. Howell, Resident inspector DRP !
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' n* mF1 D; > N iGraver.,~ Resident ilnspector, DRP L * > M. ; Fi kunyatG Rta': tor- Engineer,1D'RS -
D M.- LJXT. Gilliland, Public Effair.s Officer. 3' q q w q -:
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~0E 0. Tharo, Co sultant, CASE . i !
'@ E. F.' Ottney; Fmject Manager,i CASE l . .
l1 4 H. S. Phillips, CASE Consultant, Phil.tec Services. -'Inc.
g t y M. Axelrad,' Attorney, Newman *& Holtaniper 9
' S. Jones,' Fort Wirth Star Telegrau a b
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/ R. Richardson, Ritporter, Associated Pres EB. Rosei; Dallas lies Herald -
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- i 7 i, T.liong,\KIRA Radio '
4 4 F.ETrejof Dillas Horning News ~ 1 L f 3,
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;l MEETING
SUMMARY
Licensee: TV Electric-n L
Facility:: CPSES, Unit 1
')
License No.: NPF-87 .
[
Docket No.: 50-445 ,
.?
Subject:
Technical Meeting Open to Public Observation
.On August 2,1990, representatives of TV Electric Corporation presented to RIV '
T T' '
. personnel at the site, technical. issues pertaining to safety injection events
-which occurred on July 26 and 30, 1990, and the results of the 100 percent' / -l
- power. plateau startup testing. This meeting also included discussionscof ~E f i
_ personnel and equipment response to the events MSIY design-features,'. and ' '[ '
corrective. action for clearance tag-out problems. .
s' The-license'e stated that they were still evaluating emergenr.y lighting design'
, adequacy, the atmospheric relief valves (ARV) failure m:!chanism, and other: tO 1 ? aspects of the July 30 event. At the conclusion of the meeting, the'11censee committed to submit a letter concerning three specific topics to the NRCl l'
- 24 hours before entering Mode 3.: The letter was'to address the results of the 4 , R
, review and planned corrective actions, if required, concerning matters related ;
to emergency lighting operations-of the ARV,,and personnel safety ,
considerations for t ' containment air' lock and ARV vent stack, , , , ,j 1
;0n1 August 4, represen 4tives of Region ~ IV and NRR reviewed the< letter (copy attached): submitted by the: licensee pertaining to ther actions taken prior:to ,
1- restart of the plant.- The actions described were viewed as appropritite for- j W
restart of CPSES, Unit 1.- -
a km A copy lof the ifcensm's presentation material is t:nclosed. s P : Attachments-(NRC distribution only)* .
- 1. Licensee Presentation !. .
s~.
SL
- 2. AugustL4,1990, Letter (TXX-90283) j l
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