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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
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Log # TXX 98004
==== M" File # 10035 L - Ref. # 10CFR50.54(f)
--- .--- GL 97 04 nlELECTRIC' January 14. 1998 C. lance Terry Gmup We Penidru U. S. Nuclear Regulatory Commiscion Attn: Document Control Desk Washington, DC 20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50 445 AND 50 446 RESPONSE TO GENERIC LETTER 97 04, " ASSURANCE OF SUFFICIENT NET POSITIVE SUCTION HEAD FOR EMERGENCY CORE COOLING AND CONTAINMENT HEAT REMOVAL PUMPS" REF: 1) Generic Letter 97 04, " Assurance of Sufficient Net Positive Suction Head for Emergency Core Cooling and Containment Heat Removal Pumps" dated October 7, 1997.
- 2) TU Electric Letter, logged TXX 97238. "Respose tc Generic Letter 97 04 . . . " from C. L. Terry to l' . Nuclear Regulatory Commission dated November 6 1997.
Gentlemen:
On October 7,1997, the NRC issued Generic Letter 97 04 " Assurance of Sufficient Net Positive Suction Head for Emergency Core Cooling and Containment Heat Removal Pumps." Included in this letter was a request for both a 30 day and a 90 day response from al' addressees. TU Electric responded to the 30 day request in Reference 2. TU Electric committed to provide the information requested in the 90 day response by April 7, 1998.
Per conversation with members of NPR on December 12, 1997 TU Electric orally agreed to provide as much of the 90 day requested information as practical, during the week of January 12. 1998. TV Electric is providing the requested information as identified at this time in Attachment 2. TV Electric will provide _ further clarifying information by April 7,1998, as agreed-to by NRR in the phone conversation of December 12, 1997.
Pursuant to Section 182a of the Atomic Energy Act of 1954, as amended, and 10 CFR 50.54(f). TV Electric is submitting a response under affirmation (Attachment 1) to the requested information and requested actions as stated 1n Reference 1, i AUp i \
9901210223 990114 PDR ADOCK 05000445 F'
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P. O. Box 1002 Glen Rose Texas 76043
i I .
TXX 98004 Page 2 of 2
- This communication contains the following commitment which will be completed as noted:
ACL Numt.et Commitment 97 116 TU Electric is providing the requested information as identified at this time in Attachment 2. TU Electric will provide further clarifying information by April 7, 1998, as agreed to by NRR in the phone conversation of December 12, 1997.
The ACL (Action Correspondence Log) number is used by TU Electric for the internal tracking of CPSE' commitments which are one time action requirements.
If you have any questions, please contact Randy Blankenship at (254) 897 5890.
Sincerely.
- 8. Y, Q C. l.. Terry By: On I
~
RogeVD. Walker Regulatory Affairs Manager RTB/rb Attachments c- E. W. Herschoff, Region IV J. I. Tapia. Region IV T. J. Polich. NRR Resident Inspectors, CPSES l
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Attachment 1 to TXX 98004 Page 1 of 1 ;
l'NITED STATES OF AMERICA NilCLEAR REGULATORY COMMISSION In the Matter of )
)
Texas Utilities Electric Company. ) Docket Nos. 50 445
) 50 446 l (Comanche Peak Steam Electric Station, )
Units 1 & 2) ) ;
AFFIDAVII ,
Roger D. Nalker being duly sworn, hereby deposes and says that he is Regulatory Affairs Manager of TU Electric, the 'icensee herein: that he is !
duly 6uthorized to sign and file with the Nuclear Regulatory Commission this Response to Generic Letter 97 04, " Assurance of Sufficient Net Positive Suction Head for Emergency Core Cooling and Containment Heat Removal Pumps": that he is familiar with the content thereof: and that the matters set forth therein are true and correct to the best of his knowledge, information and belief.
- m e49A Roger V, Walker Regulatory Affairs Manager STATE OF TEXAS )
)
COL,NTY OF h49Q O
Subscrihtd and sworn to before me, on this /N day of bmtMir ,
1998. (/ 0 CAROLYN L C0fENTIN0
.. } Notny Pubhc,5bte ct iern
> NotaryPplic i .( My Comm. Expres 04i04/98 *
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- 9. w e. --
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4
i Attachment 2 to TXX 98004 Page 1 of 9-GL 97 04 requested information regarding Net Positive Suction Head (NPSH) for the emergency core cooling and containment heat removal pumps that meet either of the following criteria:
(1) pumps that take suction from the containment sump or suppression pool following a design-basis LOCA or secondary line break, or (2) pumps used in " piggyback" operation that are necessary for rectrculation cooling of the reactor core and containment (that is, pumps that are supplied by pumps which take suction directly from the sump or suppression pool).
TU Electric submits that for Comanche Peak Steam Electric Station (CPSES) the following pumps are inclusive of these classifications for both units.
Emergency Core Coolina Pumos Suction Source Residual Heat Removal (RHR) Pump 01 Sump Residual Heat Removal (RHR) Pump 02 Sump Safety Injection Pump (SIP) 01 RHR 01 or RHR-02 Safety Injection Pump (SIP) 02 RHR 01 or RHR 02 Centrifugal Charging Pump (CCP) 01 RHR 01 or RHR 02 Centrifugal Charging Pump (CCP) 02 RHR 01 or RHR 5.
Containment Heat Removal Pumos Suction Source Containment ", pray Pump 01 Sump Containment Spray Pump 02 Sump Containment Spray Pump 03 Sump Containment Spray Pump 04 Sump With respect to the above 10 pumps for each unit CPSES presents the following responses as to the information requested per the generic letter.
i I .
Attachment 2 to TXX 98004 Page 2 of 9 - ,
Jtem 1 - Specify the general methodology used to calculate the head loss associated with tne ECCS suction strainers.
Response
The general methodology used at CPSES to calculate the head loss associated with the ECCS suction strainer / containment sump is as follows:
The basic equation for calculating NPSH is:
NPSH = h, h,,, + h, h ,,
where: ,
h, - absolute pressure on the surface of the liquid supply level .
h,,, - head corresponding to the vapor pressure of the liquid at the temperature being pumped, s h ,, = static height that the liquid supply level is above or below the pump centerline or impeller eye.
h,, = suction line losses including entrance losses and friction losses.
Additional detail on each of the terms is provided below.
h, - absolute pressure on the surface of the liquid supply level ims term is the containment pressure that is taken credit for in the analysis. CPSES assumes the pressure on the surface of the liquid is equal to the v~ essure of the liquid at the puaped fluid temperature. See t.... response to Question 4 for a discussion en the crediting of containment pressure in the NPSH analysis for CPSES.
h, head correrpondir'; to the vapor pressure of the liquid at the temperature being pumped.
This tern requires the determination of the t a perature of the fluid bein0 pumped. The temperature used in the limiting NPSH calculation is based on a conservative assessment using a sump fluid temperature equivaient to the saturated conditions in containment, at the containment pressure in the NDSH analysis.
CPSES assey s h,,, = h .
h, - static height that the liquid supply level is above or below the pump datum (e.g. centerline or impeller eye)
This term is simply the minimum static height of fluid above the pump reference point (typically pump centerline or impeller
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Attachment 2 to TXX 98004 Page 3 of 9-eye). The containment minimum flood analysis is used as a basis for the height of water on the containment floor (Elevation 808' 0") and in the sump (bottom elevation 802' 0') during the pump operating sequence.
hu - al' suction line losses including entrance losses and friction loss, .
This term involves suction line losses associated with the pump beina evaluated. The following parameters are considered in the NPSH calculation:
- 1. Suction line friction and entrance losses. The important parameters to consider here are the following:
+ Pipe roughness
+ Pipe aging effects
+ Length of piping e Fluid velocity (See Item 4 below)
+ Number and types of valves and fittings in the suction ciping
- 2. Head loss associated with the open area of a strainer / sump screen that is free of debris as confirmed by full scale model testing. The effect of sump screen blockage is considered in the architect / engineer analyses. The analyses by the Nuclear Steam Supply System vendor are performed at the floor level (below the screens) and do not include this head loss.
- 3. Suction line velocity head losses.
- 4. The maximum system flow rates through the strainers / sump and arrociated piping are determined for use in calcuiating friction losses. Higher flow rates create greater line losses. No design mode of operation reducet flow in the spray pump suction lines such that the flow rate is insufficient to maintain check valves in the full open position. There are no check valves in the RHR nump suction.
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Attachment 2 to TXX 98004 Page 4 of 9-Item 2 - Identify the r&qatred NPSH and the available NPSH.
Resoon g:
The following tabulation of NPSH analyses by the NSSS vendor provides the available NPSH (NPSH,), during recirculation, corresponding to flood level at containment elevation 808' 0" which is the flocr elevation ?t the top of the 6 foot deep containment emergency sumps. The actual NPSH, is greater and can be determined by adding the containment flood level above 808' 0" and correcting for head loss across the sump screens. The NPSH, is greater than the NPSH required (NPSH ).
Pumo GPE ESS ESL Harain Residual Heat Removal Pumps 4900* 20' 25' >5' Safety Injection Pumps 403* 9' 96.8' >87.8' Centrifugal Charging Pumps 409* 15' 62.5' >47.5'
- Corresponds to one RHR pump supplying two trains of SI and charging operating in parallel. The calculation [Ref. 7] is for the limiting case for RHR pump NPSH.
The following tabulation of NPSH analyses by the architect / engineer provides the NPSH,, during recirculation, corresponding to flood level at containment floor elevation 808' 0". The assumed RHR pump flow rate was conservatively selected as 5300 gpm. The RHR system is designed to limit the maximum flow durirg recirculation to 4900 gpm. The calculated RHR pump NPSH, also includes a head loss for 50% screen blockage equivalent to 0.5 feet taken from the full scale sump test [Ref. 6]. The calculated containment spray pump NPSH, includes a resistance coefficient to simulate 50% screen blockage equivalent to 0.52 feet at 7000 gpm taken from the full scale sump test [Raf. 6].
Pumo GPE ES& ESL Harain Residual Heat Removal Pumps 5300 23' 23,9' O.9' Containment Soray Pumps 3740* 17.l' 18.7' 1.6'
- Per pump The actual NPSH, is greater and can be determined by adding the containment flood level above 808'-0". The water height above elevation 808' 0" at transfer to ECCS recirculation. Hcces = 1.8' From the NSSS analysis above, the RHR pump margin is also at least 3' greater at the maximum flow of 4900 gpm.
4
Attachment 2 to TXX 98004 Page 5 of 9' This yields NPSH margins for RHR as follows:
RHR Pumps - 0.9' + 3' + 1.8' = >5.7' and the ratio of NPSH availabla to WPSH required is:
NPSH, / NPSH, = [(23.9 + 1.8) / (20)] = 1.3 Yhe water h019ht above elevation 808' 0" at transfer to containment spray recirculation. Hess = 3.5', This yields NPSH margin for containment spray as follows:
Containnent Spray Pumps 1.6' + 3.5' = 5.1' and the ratio of NPSH available to NPSH required is:
NPSH, / NPSH, = [(18.7 + 3.5) / (17.1)] = 1.3
Attachment 2 to TXX 98004 Page 6 of 9-Item 3 - Specify whether the current design-basis NFSH analysis differs from the most recent analysis reviewed and approved by the NRC for which a safety evaluation was issued.
Response
As docueented in the CPSES FSAR [Ref.3] Appendix 1A(N) and 1A(B) and Sections 6.2.2.3.4 and 6.3.2.2.10 the NPSH analy>es for the ECCS and Containment Spray Pumps conform to RG 1.1. This acceptance criteria is reflected in the SER [Ref.4] Sections 6.2.2 and 6.3.2.
FSAR Table 6.2.21 shows the Containment Spray pump NPSH, (13 f eet) at 3000 gpm. FSAR Figure 6.2.2 2 shows the relationship of NPSH required and available as a function of flow. The NPSH, values were increased when new impellers were installed as a design modification fallowing issuance of the operating license.
FSAR Sectior 6.3 2.2.10 notes that the most limiting ECCS NPSH conditions are during injection with charging (and SI) poaps aligned to the Refueling Water Storage Tank (RWST) [see FSAR Table 6.3 1].
NPSH values during recirculation for ECCS are not provided in the FSAR.
The full scale contLinment sump testing (Ref. 6] discussed in SER and SSER section 6.3.4.2 was performed with design pump flows of 5300 for RHR and 3600 for containment spray.
As documented in Ref. 5 and SSER 9. Appendix L. Section 2.1.1. the NPSH margins were given as 4.23 feet for RHR Pumps anc 81 feet for the Containment Spray Pumps. The current NPSH margt- ., 5.7 feet and 5.1 feet, res)ectively, are similar. The NPSH analyses in Ref.
5 were based on t1e following:
RHR Pump Flow 5300 gpm Containment Spray Pump Flow 3900 gpm per pump Hinimum Containment Flood Level 814.8 feet As documented in SSER 17. Appendix A, Open Item F 5: the minimum water level for containment spray pump NPSH analysis (16345 ME(B)-
169) reviewed by the NRC was different than the 814.8 feet in Ref.
5 and was 810 feet. The SSER concluded that this was conservative.
The current minimum containment flood level analysis is 811' 6" for containaent spray NPSH analyses, which remains conservative to the NPSH analyses accepted in SSER 9. The current minimum containment flood level analysis is 809' 9.4" for the RHR Pumps.
Although there are differences in details of the current analyses, the basic methodology design margins and conclusions are still consistent.
Attachment 2 to TXX 98004 Page 7 of 9-Item 4 - Specify whether containment overpressure (1.e., containment pressure above the vapor pressure of the sump or suppression pool fluid) was credited in the calculation of available NPSH.
Specify the amount of overpressure needed and the minimum overpressure available.
Resoonse:
In accordance with References 3 and 4 and Reg. Guide 1.1, no containment overpressure is credited in the calculation of available NPSH for any of the ECCS or containment heat removal pumps at CPSES.
Attachment 2 to TXX 98004 Page 8 of 9-Item 5 - When containment overpressure is credited in the calculation of available NPSH, confirm that an apprcpriate containment pressure analysis was done to establish the minimum containment pressure.
Resoonse:
Not applicable, see item 4.
k.
e Attachment 2 to TXX 93004
' age 9 of 9 h*FERENCES
- 1. Generic Letter 97 04, " Assurance of Sufficient Net Positive Suction Head for Emergency Core Cooling and Containment Heat Removal Pumps" dated October 7, 1997.
- 2. TU Electric Letter, logged TXX 97238. " Response to Generic Letter 97 04, " Assurance of Sufficient Net Positive Suction Head for Emergency Core Cooling and Containment Heat Removal Pumps" from C.
L. Terry to U.S. Nuclear Re9ulatory Commission dated November 6, 1997.
- 3. CPSES Final Safety Analysis Report Amendment 94.
Appendix 1A(N), RG 1.1 Appendix 1A(B), RG 1.1, RG 1.79, RG 1.82 Section 6.2.2.3.4 Section 6.3.2.2.10 Section 6.3.4.2
- t. NUREG 0797, Safety Evaluation Report related to the Operation of Comanche Peak Steam Electric Station, Units 1 and 2, July 1981.[SER]
Sections 6.2.2, 6.3.3.3 and 6.3.4.2, Supplements [SSERs]:
SSER 1, October 1981, Section 6.3.4.2 SSER 9. March 1985, Appendix L SSER 17 November 1988, Appendix A SSER 21, April 1989, Appendix L
- 5. " Evaluation of Paint and Insulation Debris Effects on Containment Emergency Sump Performance, Gibbs & Hill, Inc., Revision 1, October 1984.
- 6. "Model Testing of the Recirculation Containment Sump,' Western Canada Hydraulic Laboratories LTD., November 1981.
- 7. Calc. FSSE/SS-TBX 1192 (10/17/88)
- 8. Calc. ME(B) 325R0,CCN-4 (12/3/97): 2 ME 0147R0,CCN-1 (11/10/97)
- 9. Calc. ME CA 0232 4006R2 (8/21/97)
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