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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] |
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l Log # TXX 95235 P7 File # 916 (5.6)
._ = 10010
lilELECTRIC September 14, 1995 C. lance Terry Greap Vkt PresMnet.Marient U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES) ~
DOCKET NOS. 50 445 AND 50 446 SUPPLEMENTAL RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION ON LICENSE AMENDMENT REQUEST 94 022, SPENT FUEL STORAGE CAPACITY INCREASE REF: 1) TV Electric letter logged TXX 94325, from C. L. Terry to the NRC, dated December 30, 1994
- 2) NRC Letter from Timothy J. Polich to C. Lance Terry, dated May 23. 1995
- 3) TU Electric letter logged TXX 95187, from C. L. Terry to the NRC, dated July 28, 1995 Gentlemen:
TU Electric transmitted License Amendment Request 94 022 (Reference 1) which revises the specification for fuel storage to authorize usage of the high density fuel storage racks, to increase the spent fuel storage capacity, and to adopt the wording, content, and format of the Improved Standard Technical Specifications. The NRC transmitted (Reference 2) a Request for Additional Information (RAI) regarding the subject License 8 Amendment Request. TU Electric provided an initial response to the RAI in 1 Reference 3. The Attachment herein contains TV Electric's updated '
responses for RAI No. 8 and 11. With these updated responses, TV Electric ,
has provided complete responses to all the requests in the NRC's RAI. l The information provided in the Attachment does not affect the proposed l Technical Specification changes, the safety analysis of those changes, or the determination that the proposed changes do not involve a significant hazard consideration (provided by Attachments 2 and 3 of Reference 1).
i ;
L
. ..i CCCG0 "
i 9509180377 950914 j i PDR ADOC P__._ _ _ _K 05000445 ,_p I C.-________...__________
l 1
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TXX 95235 Page 2 of 2 Should you have any questions, please contact Carl B. Corbin at (214) 812 8859 or David A. Bersi at (817) 897-8134.
Sincerely, 1 l
C. L. Terry I By:
D. R. Woodlan Docket Licensing Manager CBC/cbc
Attachment:
Response to Request for Additional Information Regarding Spent Fuel Pool Storage Increase c- Mr. L. J. Callan. Region IV Mr. T. J. Polich. NRR Hr. D. F. Kirsch, Region IV Resident Inspector, CPSES Mr. D. K. Lacker Bureau of Radiation Control Texas Department of Public Health 1100 West 49th Street
' Austin. Texas 78704 l
l 1
I t
Attachment to TXX 95235 Page 1 of 9 RESPONSE TO NRC RE0 VEST FOR ADDITIONAL INFORMATION (RAI) 4 REGARDING SPENT FUEL POOL STORAGE INCREASE NRC RAI # 8:
f With respect to the fuel pool structure analyses, a table in the submittal 4
(Reference 2) shows a safety margin of 1.02 for the South Wall. TV Electric concluded that the pool structure maintains its structural integrity during
> a critical loading combination since the safety margin is larger than 1.0.
However, the calculated factor of safety is very marginal, and it could be changed depending on analytical methodologies used and other parameters (i.e., material properties used in the analyses, etc.). Submit the input
- and output of the pool structural analyses of the slab and South Wall for
' different critical loading conditions including the physical dimensions and a locations of the reinforcement of the pool structure. Any technical assumptions made during the analyses should be discussed in detail.
TU ELECTRIC RESPONSE TO RAI # 8 :
TU Electric provided a response to RAI # 8 in Reference 1. As a result of subsequent discussions with the NRC staff regarding the safety margin for the south wall, additional information is provided below.
l The data points for forces and moments on the South wall elements under critical load combinations are within the interaction curve, with the
- exception of element 303. The axial force and bending moment in the horizontal and vertical directions were averaged with the adjacent elements
< of element 303. This averaged value was used to determine the safety margin for element 303. The safety margin was determined as follows. The distance of the line joining the data point on the interaction diagram with the
- origin was taken as L1. The distance of the intersection point of the above 4
line with the interaction curve from the origin was taken as L2. The ratio L2/L1 was taken as the safety margin. The computed safety margin was 1.23.
In the initial submittal of Licensing Amendment Request 94 22 (TXX 94325),
no stress averaging was done for element 303 of the South wall. The safety margin was computed as follows. For the axial force in the element, bending moment capacity (Mu) was obtained from the interaction diagram. The ratio
' of Hu/M, where M is the bending moment on the element, was taken as the
- safety margin. The computed safety margin was 1.02, 4
In summary, the improvement in the safety margin for the South wall is attributable to:
- 1) Stress averaging with the adjacent elements
- 2) More standard determination of the Safety Margin.
- 1 f
' Attachment to TXX 95235-Page 2 of 9
- NRC RAI # 11: ]
TV Electric indicated that the rack design is controlled by the results of 1' the single rack analysis. Provide justification that the results of a
- single rack analysis are more conservative than the results of a whole pool multiple rack (WPMR) analysis, or provide comparison of results from a single rack and WPMR results.
TU ELECTRIC RESPONSE TO RAI # 11 :
A whole pool multiple rack (WPHR) analysis has been performed for the high density rack arrangement to be used in Comanche Peak spent fuel pool 2.
~
This evaluation is a supplement to the single rack analysis, previously performed and documented in the CPSES Fuel Storage Licensing Report 4
(References 1 and 2), which has demonstrated acceptable loads, displacements, and stresses for the fuel rack modules. The WPMR analysis includes all nine rack modules as well as the hydrodynamic effect of the ,
- surroundirig fluid. Thus, the interactions between the individual rack l
, module 3, the surrounding fluid, and the pool structure are fully I i represented. The results obtained from the WPHR analysis confirm that the i single rack analysis results previously reported well represent the limiting ;
response of the racks. 1 A series of evaluations were performed in the process of completing the WPMR I analysis. The key steps in the process are:
i i L Develop a reduced element (reduced degree of freedom) single rack j model.
- 2. Perform a fluid structure interaction analysis to determine the fluid i- coupling hydrodynamic mass matrix for the pool and all nine racks.
} 3. Based on steps 1 and 2, create the WPMR model with nine racks modeled and incorporating the whole pool fluid coupling hydrodynamic mass matrix.
- 4. Perform WPHR time history seismic analyses for both SSE and OBE for cases with friction coefficients equal to 0.8 and 0.2.
- 5. Determine the maximum rack displacements and stresses for the WPMR 4 analysis and compare to the results previously calculated for the single rack analysis.
Each of these steps is discussed below.
In order to perform the WPMR analysis, a reduced element, i.e. reduced degree of freedom (00F), finite element model for a single rack has been developed. Figure 11 1 shows the full D0F model (2 D view of the 3 D model) used in the single rack analysis, while Figure 11 2 provides the same 2 D
. view of the 3 D reduced DOF model used to represent an individual rack in 0 the WPHR evaluation. Both models represent the rack in a similar manner, with the elements representing the rack base and support pads being the same in both models. The major difference between the full 00F and reduced DOF 1
4 .
] ' Attachment to TXX 95235 Page 3 of 9 )
i models is a decrease in the number of elements used to represent the cell and fuel beams, the number of fuel to cell impact elements, and the number .
j of elevations at which hydrodynamic fluid coupling mass matrix elements are
- used, i I
- The reduced DOF model has been qualified by applying both SSE and OBE loadings using the same sets of acceleration time histories as in the full D0F single rack analysis. For both seismic loading conditions, evaluations were made for friction coefficients of 0.8 and 0.2. The results from the evaluation demonstrate that comparable displacements and loads are obtained for the reduced D0F model when compared to those of the full 00F single rack model. It is concluded, therefore, that the use of the reduced D0F model to i represent an individual rack in the WPMR analysis is acceptable.
I Having developed an acceptable single rack reduced 00F model, the WPMR model l 'is compiled by combining nine such single rack models in a 3x3 array using
- the same rack to rack spacing as in the Comanche Peak spent fuel pool. Each i single rack model within the WPMR model has the appropriate mass and g stiffness properties for the rack size (either 11x14 or 12x14) it i represents. The WPHR finite element model is shown in Figure 113. ,
1
! The hydrodynamic effect of the water surrounding the fuel rack modules is j incorporated into the WPMR model as 20x20 mass matrices. The twenty rows !
l and columns represent two horizontal D0F's for each of the nine fuel rack
< modules plus the pool wall. Since the mass matrix is fully populated, the i hydrodynamic' interaction effects, both rack to rack and rack to wall, are
! included in the analysis. Three such mass matrices are used over the height 4 of the WPMR model.
{ The hydrodynamic mass matrix is calculated using a two dimensional finite i element analysis in which a horizontal cross section of the entire pool
! fluid area is meshed with pressure elements bounded by fluid structure i
interface (FSI) elements. The finite element model is shown in Figure 11 4.
- The FSI elements, not depicted in the figure, serve to account for the interactions between the fluid pressure and the in plane structural i accelerations. By using the substructuring capabilities of the finite
- element code, the hydrodynamic mass matrix is obtained by substructural
, elimination of the pressure D0F's, retaining only two in plane (horizontal)
- acceleration D0F's for each fuel rack plus the pool wall. The result is a
- 10 node, 2 00F "superelement" which is included in the WPMR finite element 4
model to incorporate the 20x20 hydrodynamic mass matrix into the overall
! system mass matrix.
The WPMR model is evaluated for both SSE and OBE by applying the same acceleration time histories as were used in the single rack analysis.
i.
4 . Analyses have been performed for friction coefficients equal to 0.8 and 0.2 for both seismic loading conditions. The stress results for the limiting i locations from the WPMR analysis are summarized in Table 11 1 along with the corresponding results from the single rack analysis. An inspection of this 4
table reveals that, in all cases, larger margins are obtained for the WPMR analysis versus the single rack analysis. The displacement results, suma rized in Table 11 2, show that the maximum relative displacement between adjacent racks is smaller for the WPMR analysis than for the single 4
s l
I
j
- Attachment to TXX 95235 Page 4 of 9 rack analysis, thus indicating larger margin against rack to rack collision.
The maximum individual rack displacement is slightly higher for the WPHR analysis than for the single rack analysis, but ample margin exists against rack to wall collision. Therefore, it is concluded that both the single rack analysis and the WPHR analysis demonstrate acceptable loads, displacements, and stresses for the Comanche Peak fuel racks.
Table 111
< Comparison of Single Rack and WPHR Analysis Stress Results OBE Minimum Margin to SSE Hinimum Margin to Location Allowable
- Single Rack WPHR Single Rack WPHR
- Support Pads 0.35 0.79 0.82 0.96 Cells 0.09 0.42 0.38 0.49 t se 0.95 1.58 0.51 1.28 e
Cell to Cell 0.13 0.41 0.45 0.64 Weld Cell Seam Weld 0.26 0.64 0.58 0.79 Cell to Spacer 0.26 0.71 0.25 0.54 Weld 1
- Note: Hargin to Alowable = -1 Applied Stress
' Table 11 2 Comparison of Single Rack and WPHR Analysis Displacement Results Single WPHR Rack Maximum Individual Rack 0.29 0.30 Displacement (inches)
Maximum Relative Displacement 0.58** 0.28
_Setween Adjacent Racks (inches)
- Conservative value was reported based on the assumption that adjacent racks move completely out of phase.
Attachment to TXX 95235 RACK HYDRODYNAMIC MA$$
Page 5 of 9 CELL-TO-CELL CONNECT!ON CELL ASSEMBLY FUEL-TO-CELL GAP CLEMENT FUEL ASSEM8LY e,-
g
\
FUEL GRID ROTATIONAL ' ,
\
STIFFNESS a T [8H] \
p g eu,3s 6 g
s T (" : N a.Qs, \
Aj v I :: (\
{ g 1 *: \
1.7 \
a I :=~) \
' \
J g / ru,,a u
\
\
, \
s T Cus : N N
FUEL BASE \
LIFT-OFF ELEMENT [g]
' / \
/ ..
N SUPPORT PAD ELEMENT
\
h O \
\
\
NNNNNNNNNNNNNNNNNNNNNNNNNNNNN Figure 11 1. Full DOF Nonlinear Finite Element Model (2 D View of 3 D Model)
' Attachment to TXX 95235 RACK HYDRODYNAM[C MASS Page 6 of 9 CELL-70-CELL CONNECT [GN CELL ASSEMBLY FUEL-TO-CELL GAP ELEMENT FUEL ASSEM8LY q
\
R TAT C L 1 ["H3 \
ST(FFNESS
\
\
\
\
x \
g ts: N
= o, >
N x
' \
A i,, \
N 13 \
3 g .
Es: \
\
q
\
\
FUEL BASE
w , ,
N LIFT-OFF ELEMENT \& (<]
\
\
i
/ \
U
/ ..
N SUPPORT PAD \
ELEMENT g \
\
Nggg%N%%\%%\%%\%%
Figure 11 2. Reduced 00F Nonlinear Finite Element Model (2-0 View of 3 0 Model)
\
n
' Attachment to TXX 95235 Page 7 of 9 4
t t
c 1
i l
t b
i i
. ~ 1 aus i
t
- i 4 ..
I a ,
. .. pes
.... N
... .. N x s N s N
$ .........,,, N N h
.......... h ..;..__ N.______ ..............,y.....
y x Figure 11 3. WPMR Finite Element Model 1
l
-- .-__---________--__--__-_____________-____________--__-__1
- _ . - . - - -- - - ~ .
Attachment to TXX 95235 Page 8 of 9 i
l I a
4 x-m/w/Mm/- N-VN/NNmN./ /N-/rN-pNA/N/%/M/TN/MLM N#WN/NNVV /Nh/TNN
_N#XIX/%##Mm/M N N#VN/NNWV /NMm6
/N/\/\/N g X/\/\/N/ I
- X/N/\/N N/N/\/\/ !'
4
/\/N./\/\ ,
tN /N/\/\/
j NN/\/N ,
Nam /\/N/
'/N/N/\/\ l j A/N/\/N/
/N/\/\/\ l ,,
gj N_/N/\/\/ i l l 4
X/N/\/\/ 3
/N/N/\/\ ,
l X/N/\/\/
/N/\/\/\ l X/N/\/\/
/N/N./\/N l, VN/\/\/ g i i A/N./\/\ ,
l N/.N/\/\/
t /N'A/N/\ l N/N/N /\/ s i
X/N/N/\/ l h
/N/N./\/N 1 l j VN/\/\/ l ,
A/\/\/N l
[N/Wi\./\/ l l
'/XAi/\/N t l l
N/WN/\/ 4
~
' /NA/\/N 3 N/N/N/N/ l h
/N/N./\/\ l l N/N/\/\/ l l
/v%/\/s x n m .v _- - mm_ _ - ,i
-~
x _-
n m--m,,
I n
l i
.i n .. ,
t 1
i 4
Figure 11-4. WPMR Hicrodynamic Mass Finite Element Model
'~ ,-
' Attachment to TXX 95235 Page 9 of 9
References:
- 1. " Comanche Peak Steam Electric Station (CPSES), Docket Nos. 50 445 and 50 446. Response to Request for Additional Information on License Amendment Recuest 94 022, Spent fuel Storage Capacity Increase,"
letter loggec TXX 95187, dated July 28, 1995, from TV Electric to U.S.
NRC.
- 2. " Comanche Peak Steam Electric Station (CPSES), Docket Nos. 50 445 and' 50 446, Submittal of License Amendment Request 94 022. Spent fuel Storage Capacity Increase " letter logged TXX-94325, dated December 30, 1994, from TU Electric to U.S. NRC.
- - - -