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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 ML20216J5571999-10-0101 October 1999 Provides Final Response to GL 98-01,suppl 1, Y2K Readiness of Computer Sys at Npps 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 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 TXX-9922, Forwards Rev 6 to CPSES Glen Rose,Tx ASME Section XI ISI Program Plan for 1st Interval on 9908201999-09-24024 September 1999 Forwards Rev 6 to CPSES Glen Rose,Tx ASME Section XI ISI Program Plan for 1st Interval on 990820 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 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 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 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 TXX-9920, Forwards Revs 29 & 30 to CPSES Technical Requirements Manual (Trm). Attachments 1 & 2 Contain Description of Changes for Revs 29 & 30 Respectively1999-08-26026 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 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 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 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 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 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 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 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 ML20210K2321999-07-29029 July 1999 Forwards Insp Repts 50-445/99-12 & 50-446/99-12 on 990530-0710.No Violations Noted TXX-9918, Forwards fitness-for-duty Program Performance Data for Six Month Period of Jan-June 19991999-07-29029 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 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 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 TXX-9917, 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-62301999-07-16016 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 ML20209H7501999-07-15015 July 1999 Forwards Safety Evaluation on GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Comanche Peak Steam Electric Station,Units 1 & 2 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 ML20209G7421999-07-0808 July 1999 Forwards SER Concluding That Licensee Individual Plant Exam of External Events Process Capable of Identifying Most Likely Severe Accidents & Severe Accident Vulnerabilities & IPEEE Met Intent of Supp 4 to GL 88-20 ML20196L0121999-07-0808 July 1999 Forwards Safety Evaluation Granting First 10-Year Interval Inservice Insp Requests for Relief B-6 (Rev 2),B-7 (Rev 2), B-12,B-13,B-14 & C-9,pursuant to Tile 10CFR50.55a(g)(6)(i) ML20196K6771999-07-0202 July 1999 Ack Receipt of & Encl Scenario for Comanche Peak Steam Electric Station Emergency Plan Exercise Scheduled for 990721-22.Determined That Exercise Scenario Sufficient to Meet Emergency Plan Requirements & Exercise Objectives 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 ML20196J0401999-06-29029 June 1999 Forwards Safety Evaluation Re Plant,Units 1 & 2 Proposed Changes to Emergency Plan 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 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 TXX-9922, Forwards Rev 6 to CPSES Glen Rose,Tx ASME Section XI ISI Program Plan for 1st Interval on 9908201999-09-24024 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-9920, Forwards Revs 29 & 30 to CPSES Technical Requirements Manual (Trm). Attachments 1 & 2 Contain Description of Changes for Revs 29 & 30 Respectively1999-08-26026 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 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 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 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 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 TXX-9918, Forwards fitness-for-duty Program Performance Data for Six Month Period of Jan-June 19991999-07-29029 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 ML20210D3211999-07-21021 July 1999 Provides List of Estimates of Licensing Actions,In Response to Administrative Ltr 99-02,dtd 990603 ML20209H0111999-07-16016 July 1999 Forwards Relief Request C-4 to CPSES Unit 2 ISI Program for Approval TXX-9917, 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-62301999-07-16016 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 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 ML20196A4921999-06-15015 June 1999 Forwards Rev 30 to Physical Security Plan.Rev Withheld,Per 10CFR73.21 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 ML20195J0651999-06-14014 June 1999 Submits Response to RAI Re GL 95-07, Pressure Locking & Thermal Binding of Safety Related Power Operated Gate Valves TXX-9913, Submits Response to RAI Re Implementation of 1.0 Volt Repair Criteria1999-06-14014 June 1999 Submits Response to RAI Re Implementation of 1.0 Volt Repair Criteria 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 TXX-9913, 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 CPSES1999-05-28028 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 TXX-9912, Submits Response to RAI Re GL 95-07, Pressure Locking & Thermal Binding of Safety Related Power Operated Gate Valves1999-05-25025 May 1999 Submits Response to RAI Re GL 95-07, Pressure Locking & Thermal Binding of Safety Related Power Operated Gate Valves 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 TXX-9911, 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 Valves1999-05-20020 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 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 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 TXX-9910, Forwards Rev 28 to CPSES Technical Requirements Manual. Ltr Contains No New Licensing Basis Commitments Re CPSES, Units 1 & 21999-05-13013 May 1999 Forwards Rev 28 to CPSES Technical Requirements Manual. Ltr Contains No New Licensing Basis Commitments Re CPSES, Units 1 & 2 ML20206Q5951999-05-11011 May 1999 Requests That Proprietary Version of Response to NRC RAI for LAR 98-010 Be Withheld from Public Disclosure ML20206F9841999-04-30030 April 1999 Requests That NRC Return Bisco Tests & Remove Them from Docket Re Thermo-Lag Cable Functionality Issues for CPSES, Unit 1 ML20206E1301999-04-29029 April 1999 Lists Open Items Requiring NRC Action in Response to 990226 Meeting to Discuss Topical Rept Control of Hazard Barriers ML20206D9951999-04-29029 April 1999 Forwards 1998 Annual Radiological Environ Operating Rept for Cpses. Rept Summarizes Results of Measurements & Analysis of Data Obtained from Samples Collected During Interval ML20206Q5731999-04-28028 April 1999 Requests That Proprietary Responses to RAIs for CPSES Unit 2 Uprating Be Withheld from Public Disclosure ML20206B0671999-04-23023 April 1999 Forwards Response to NRC 990413 RAI on License Amend Request 98-010,to Incorporate Changes Into CPSES Units 1 & 2 TS & Unit 2 OL to Increase Licensed Power for Operation to 3445 Mwt TXX-9909, Forwards Rev 15 of CPSES Fire Protection Rept (Fpr), Including Page by Page Description1999-04-19019 April 1999 Forwards Rev 15 of CPSES Fire Protection Rept (Fpr), Including Page by Page Description 1999-09-03
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l Log # TXX 97023 y-;
File # 10010.1 q
905.4 Ref. # 10CFR50.55a(f) l 1UELECTRIC' January 31, 1997 i
C. Lance Terry Gnnep Mce President U. S. Nuclear Regulatory Commission j
-Attention:
Document Control Desk i
Washington, DC 20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50 445 AND 50 446 UNIT 1/ UNIT 2 INSERVICE TESTING PLAN FOR l
PUMPS AND VALVES, REVISION 8 (1989 EDITION OF ASME CODE. SECTION IX, NO ADDENDA:
i UNIT 1 INTERVAL START DATE: AUGUST 13, 1990 FIRST. INTERVAL:
i UNIT 2 INTERVAL START DATE: AUGUST 3, 1993. FIRST INTERVAL) i Gentlemen:
Enclosed is Revision 8 to the Comanche Peak Steam Electric Station (CPSES)
Units 1 and 2 Inservice Testing Plan (IST) for Pumps and Valves in the first interval. The Plan is a combined Unit 1/ Unit 2 Plan, implementing i
the same requirements from the ASME Boiler and Pressure Vessel Code,Section XI, 1989 Edition of Section XI (No Addenda) on Units 1 and 2.
The effective date of this revision was January 31, 1997, at 11:01 PM CST.
The attachment provides a detailed description of the changes made by Revision 8 to the Plan in a format identical to that provided for changes to the Final Safety Analysis Report (FSAR). All changes described in the j
attachment have been evaluated for relative significance (i.e., the group number 1, 2, 3 or 4 corresponds to each change justification as discussed in TV Electric letter 1XX 88467 dated June 1, 1988).
In addition, all changes applicable to CPSES Units 1 and 2 have been reviewed under the TU Electric 10CFR50.59 pro ess and found not to include any "unreviewed safety questions."
This transmittal does not contain a request for relief from ASME Code Requirements and is provided to update your manual.
1 i
r
[0h1 P"030054288 2 &;8;g 6 -
i l
PDR v
P. O. Box 1002 Glen Rose Texas 76N3 i
TXX 96489 Page 2 of 2 If you have any questions, please call Mr. Carl Corbin at (817) 897 0121.
Sincerely, C. Lance Terry By:
0304 M-Roger 1. Walker Regulatory Affairs Manager CBC Attachment Enclosure c-Mr. L. J. Callan, Region IV Mr. J. I. Tapia, Revion IV Resident Inspectors, CPSES Mr. T. J. Polich, NRR Mr. G. Bynog, TDLR (clo)
Mr. J. C. Hair, Authorized Nuclear Inservice Inspector
Attachment to TXX-97023 CPSES -INSERVICE TEST PROGRAM REVISION-8 DETAILED DESCRIPTION Prefix Page Page 1 (as amended)
Group Description 3-2 2
Adds text to Section 3.2," Scope" stating that ASME Code Class 2 and 3 pressure relief devices that only protect systems / components that perform a safety function as described above are not tabulated in FSAR Tables 3.9N-10 and 3.98-10, but have been included in this testing plan under Revision 8.
The relief valves added by Revision 8 will be tested over the required test interval of 10 years commencing upon the issuance of Revision 3.
Revision nelusion of these relief valves brings the IST Plan into compliance with the current NRC/ASME philosophy on the scope of relief valves required in the IST Plan.
Change Request Number IT 3. 10 Related SER : 3.9.6 SSER 26 App. R SER/SSER Impact Y
See Change Request Number IT-96-3.1 TABLEl-2 Pages ll and l2 Include ASME Code Class 2 and 3 relief valves that protect systems /
components that 1) preform a specific function in shutting down the reactor to the safe shutdown condition,2) maintain the safe shutdown condition, or
- 3) mitigate the consequenses of an accident.
Also adds note at end of Table which states that the relief valves do not perform a specific safety function but protect systems / components that perform a specific safety function.
Revision Inclusion of these relief valves brings the IST Plan into compliance with the current NRC/ASME philosophy on the scope of relief valves required in the IST Plan.
Change Request Number IT 3. 1 Related SER : 3.9.6 SSER 26 App. R SER/SSER Impact Y
The Unit 1 Plan was approved in an NRC letter dated January 29,1993, in which it was stated that:
"The Licensee has indicated that the valve inservice testing meets the requirements of OM-10...., and that safety and relief valve testing is conducted in accordance with OM-1 1987. The scope statement in Section 3.2 of the IST program for safety and relief valves does not appear to be consistent with all Class 1,2, and 3 vlaves that provide overpressure protection; however, the applicable valves are included in the program."
The Unit 2 IST Plan was approved in SSER-26 in February 1993 which stated in part:
Attachment to TXX-97023 CPSES -INSERVICE TEST PROGRAM REVISION-8 DETAILED DESCRIPTION Prefix Page page 2 (as amended)
Group Description "The 1989 Edition of ASME Section XI references Operations and Maintenance (OM) Standards, Parts 6 and 10,1988 Addenda, for the rules of inservice testing of pumps and valves. Additionally, when using OM-10 for inservice testing requirements, OM-1-1987 must be used for safety and relief j
valves testing (not OM 1-1981). The scope of the safety and relief valves includes Class 1,2 or 3 valves which provide a specific function in shutting down the reactor or mitigating the consequences of an accident, as first stipulated incorporates these requirements."
TU Electric provided additional clarification (TXX-93237 of July 1,1993) on the method for determining the scope of the IST program for relief valves, and stated in part:
"ASME/ ANSI OM Part 1 provides requirements for pressure relief devices which are required to perform a specific function in shutting down a reactor or in mitigating the consequences of an accident. Consistent with ASME/ ANSI OM-1987 interpretation No.1-2 and the FSAR active component classification methodology described above, the CPSES IST Program scope includes those pressure relief devices which themselves perform an active nuclear safety function. TU Electric notes that the referenced NRC safety evaluation for CPSES Unit 2 reflects this position (page 2 of Reference 3). The discussion ofIST Program scope in the Unit I safety evaluation should be clarified to reflect this position."
TU Electric is in compliance with the code of record (1989 Edition No Addenda to ASME Section XI). Ilowever, inclusion of these relief valves brings the IST Plan into compliance with the current NRC/ASME philosophy on the scope of relief valves required in the IST Plan.
TABLE 2-2 Pages 10,11 and 13 include ASME Code Class 2 and 3 relief valves that protect systems /
components that 1) preform a specific function in shutting down the reactor to the safe shutdown condition,2) maintain the safe shutdown condition, or
- 3) mitigate the consequenses of an accident.
Also adds note at end of Table which states that the relief valves do not perform a specific safety function but protect systems / components that perform a specific safety function.
Revision inclusion of these relief valves brings the IST Plan into compliance with the current NRC/ASME philosophy on the scope of relief valves required in the IST Plan.
Change Request Number IT 3. 2 Related SER : 3.9.6 SSER 26 App. R SER/SSER Impact Y
See Change Request Number IT-96-3.1
Attachment to TXX-97023 CPSES -INSERVICE TEST PROGRAM REVISION. 8 DETAILED DESCRIPTION Prefix Page Page 3 (as amended)
Group Description TABLE 3-2 Pages I and 2 Include ASME Code Class 2 and 3 relief valves that protect systems /
components that 1) preform a specific function in shutting down the reactor to the safe shutdown condition,2) maintain the safe shutdown condition, or
- 3) mitigate the consequenses of an accident.
Also adds note at end of Table which states that the relief valves do not perform a specific safety function but protect systems / components that perform a specific safety function.
Revision Inclusion of these relief valves brings the IST Plan into compliance with the i
current NRC/ASME philosophy on the scope of relief valves required in the IST Plan.
Change Request Number IT 3. 3 Related SER : 3.9.6 SSER 26 App.R SER/SSER 1mpact Y
See Change Request Number IT-96-3.1 TABLE 4-2 Pages 12 and 16 include ASME Code Class 2 and 3 relief valves that protect systems /
components that 1) preform a specific function in shutting down the reactor to the safe shutdown condition,2) maintain the safe shutdown condition, or
- 3) mitigate the consequenses of an accident.
Also adds note at end of Table which states that the relief valves do not perform a specific safety function but protect systems / components that perform a specific safety function.
Revision inclusion of these relief valves brings the IST Plan into compliance with the current NRC/ASME philosophy on the scope of relief valves required in the IST Plan.
Change Request Number IT 3. 4 Related SER 3.9.6 SSER 26 App. R SER/SSER Impact Y
See Change Request Number IT-96-3.1 TABLE 5-2 Pages 6 and 7 include ASME Code Class 2 and 3 relief valves that protect systems /
components that 1) preform a specific function in shutting down the reactor to the safe shutdown condition,2) maintain the safe shutdown condition, or
- 3) mitigate the consequenses of an accident.
Also adds note at end of Table which states that the relief valves do not perform a specific safety function but protect systems / components that perform a specific safety function.
Revision
Attachment to TXX-97023 CPSES -INSERVICE TEST PROGRAM REVISION - 8 DETAILED DESCRIPTION Prefix Page Page 4 (as amended)
Group Description inclusion of these relief valves brings the IST Plan into compliance with the current NRC/ASME philosophy on the scope of relief valves required in the IST Plan.
Change Request Number IT 3. 5 Related SER. 3.9.6 SSER-26 App.R SER/SSER impact Y
See Change Request Number IT-96-3.1 TABLE 7-2 Pages 5 and 6 Include ASME Code Class 2 and 3 relief valves that protect systems /
components that 1) preform a specific function in shutting down the reactor to the safe shutdown condition,2) maintain the safe shutdown condition, or
- 3) mitigate the consequenses of an accident.
Also adds note at end of Table which states that the relief valves do not perform a specific safety function but protect systems / components that perform a specific safety function.
Revision inclusion of these relief valves brings the IST Plan into compliance with the current NRC/ASME philosophy on the scope of relief valves required in the IST Plan.
Change Request Number IT 3. 6 Related SER 3.9.6 SSER - 26 App.R SER/SSER 1mpact Y
See Change Request Number IT-96-3.1 TABLE 11-2 Pages 4 and 5 include ASME Code Class 2 and 3 relief valves that protect systems /
components that 1) prefomi a specific function in shutting down the reactor to the safe shutdown condition,2) maintain the safe shutdown condition, or
- 3) mitigate the consequenses of an accident.
Also adds note at end of Table which states that the relief valves do not perform a specific safety function but protect systems / components that perform a specific safety function.
Revision inclusion of these relief valves brings the IST Plan into compliance with the current NRC/ASME philosophy on the scope of relief valves required in the IST Plan.
Change Request Number IT 3. 7 Related SER : 3.9.6 SSER 26 App.R SER/SSER Impact Y
See Change Request Number IT-96-3.1 TABLE 13-2 Pages 18,19, and 23 include ASME Code Class 2 and 3 relief valves that protect systems /
Attachment to TXX-97023 CPSES -INSERVICE TEST PROGRAM REVISION-8 DETAILED DESCRIPTION Prefix Page Page 5 (as amended)
Group Description components that 1) preform a specific function in shutting down the reactor to the safe shutdown condition,2) maintain the safe shutdown condition, or
- 3) mitigate the consequenses of an accident.
Also adds note at end of Table which states that the relief valves do not perform a specific safety function but protect systems / components that perform a specific safety function.
Revision Inclusion of these relief valves brings the IST Plan into compliance with the current NRC/ASME philosophy on the scope of relief valves required in the IST Plan.
Change Request Number IT 3. 8 Related SER : 3.9.6 SSER 26 App. R SER/SSER impact Y
See Change Request Number IT-96-3.1 TABLE 14-2 Pages 4 and 5 Include ASME Code Class 2 and 3 relief valves that protect systems /
components that 1) preform a specific function in shutting down the reactor to the safe shutdown condition,2) maintain the safe shutdown condition, or
- 3) mitigate the consequenses of an accident.
Also adds note at end of Table which states that the relief valves do not perform a specific safety function but protect systems / components that perform a specific safety function.
Revision inclusion of these relief valves brings the IST Plan into compliance with the current NRC/ASME philosophy on the scope of relief valves required in the IST Plan.
Change Request Number IT - 96 ;. 9 Related SER : 3.9.6 SSER - 26 App. R SER/SSER 1mpact Y
See Change Request Number IT-96-3.1
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-a-Aka-ENCLOSURE TO TXX 97023
COMANCHE PEAK STEAM ELECTRIC STATION UNITS 1 & 2 INSERVICE TESTING PLAN (IST)
INSTRUCTION SHEET (Page 1 of 3)
The following instructional information and checklist is being furnished to help insert Revision 8 into the Comanche Peak Steam Electric Station IST.
Discard the old sheets and insert the new sheets, as listed below.
Remove Insert Cover Sheet Cover Sheet Section 3 Page 3-2 Page 3-2 Table 1 Page 1 of 12 thru Page 12 Page 1 of 12 thru Page 12 Table 2 Page 1 of 10 Page 1 of 13 Page 2 of 10 Page 2 Page 3 of 10 Page 3 Page 4 of 10 Page 4 Page 5 of 10 Page 5 Page 6 of 10 Page 6 Page 7 of 10 Page 7 Page 6 of 10 Page 8 Page 9 of 10 Page 9 Page 10 of 10 Page 10 Notes. Page 1 Page 11 Notes. Page 2 Page 12 Page 13 Table 3 Page 1 of 1 Page 1 of 2 Page 2 Table 4 Page 1 of 16 thru Page 16 Page 1 of 16 thru Page 16 Table 5 Page 1 of 6 Page 1 of 7 Page 2 of 6 Page 2 Page 3 of 6 Page 3 Page 4 of 6 Page 4 Page 5 of 6 Page 5 Page 6 of 6 Page 6 Notes. Page 1 Page 7 January 31. 1997
COMANCHE PEAK STEAM ELECTRIC STATION UNITS 1 & 2 4
INSERVICE TESTING PLAN (IST)
INSTRUCTION SHEET (Page 2)
Remove Insert Table 7 Page 1 of 4 Page 1 of 6 Page 2 of 4 Page 2 Page 3 of 4 Page 3 Page 4 of 4 Page 4 Notes. Page 1 Page 5 i
Page 6 i
Table 11 Page 1 of 3 Page 1 of 5 Page 2 of 3 Page 2 Page 3 of 3 Page 3 Notes, Page 1 Page 4 Page 5 Table 13 Page 1 of 21 Page 1 of 23 Page 2 Page 2 i
Page 3 Page 3 Page 4 Page 4 Page 5 Page 5 Page 6 Page 6 Page 7 Page 7 4
Page 8 Page 8 Page 9 Page 9 Page 10 Page 10 Page 11 Page 11 Page 12 Page 12 Page 13 Page 13 Page 14 Page 14 Page 15 Page 15 Page 16 Page 16 Page 17 Page 17 Page 18 Page 18 Page 19 Page 19 Page 20 Page 20 Page 21 Page 21 Page 22 Page 23 January 31. 1997
COMANCHE PEAK STEAM ELECTRIC STATION UNITS 1 & 2 INSERVICE TESTING PLAN (IST)
INSTRUCTION SHEET (Page 3)
Table 14 Page 1 of 4 Page 1 of 5 Page 2 Page 2 Page 3 Page 3 Page 4 Page 4 Page 5 List of Effective Paaes EPL-1 thru EPL-5 EPL-1 thru EPL-5 NOTE:
Please complete the entry for insertion of Revision 8 on the " Record of Changes" form located at the beginning of the IST Plan.
l d
A d
s January 31. 1997