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MONTHYEARML20217J4651997-08-11011 August 1997 Requests Addl Info on Proposed License Amend Re Reactor Coolant Sys Flow Monitoring for Plant,Units 1 & 2 Project stage: Other ML20210L8501997-08-14014 August 1997 Informs That Proprietary Rept, RCS Flow Measurement Using Elbow Tap Methodology Licensing Submittal, Dtd Jul 1997, Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954 Project stage: Other ML20217M7511997-08-21021 August 1997 Informs of Completed Review of Proposed License Amend to TS 2.2-1 & 3/4.2.5 & Concludes That Due to Magnitude & Complexity of Issues Involved,Nrc Will Not Be Able to Meet Util 970913 Scheduled Refueling Outage Project stage: Approval ML20217E0991997-09-25025 September 1997 Informs That NRC Staff Has Identified Inconsistencies Between Info Identified as Proprietary in Responses to Listed NRC Questions Re 970827 Application (CAW-97-1158) & 970829 Affidavit Project stage: Other ML20211Q6461997-10-15015 October 1997 Responds to W 970912 Request That Revised Responses to NRC Questions on South Texas Project Elbow Tap Submittal Be Withheld from Public Disclosure.Determined That Submitted Info Contains Proprietary Info & Will Be Withheld Project stage: Other ML20212B7361997-10-21021 October 1997 Forwards Request for Addl Info in Support of Proposed Amend to South Texas Project TS Re Use of Elbow Tap Differential Pressure Flow Monitoring for Reactor Coolant Sys Flow Rate Project stage: RAI ML20236V5211998-07-29029 July 1998 Requests Addl Info on Proposed License Amend Re RCS Flow Monitoring Project stage: Other IR 05000498/19980111999-02-0404 February 1999 Insp Repts 50-498/98-11 & 50-499/98-11 on 981129-990109.No Violations Noted.Major Areas Inspected:Operations, Maintenance,Engineering & Plant Support Project stage: Request ML20205P5821999-04-15015 April 1999 Advises That Version of Application & Affidavit Dtd 990127, Executed by Ha Sepp,Marked Proprietary,Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954,as Amended Project stage: Other 1997-08-21
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Category:CORRESPONDENCE-LETTERS
MONTHYEARNOC-AE-000675, Forwards Clarification on Items Included in 990531 Response to RAI Re Proposed License Amend Associated with Operator Action for Sbloca,As Requested1999-10-21021 October 1999 Forwards Clarification on Items Included in 990531 Response to RAI Re Proposed License Amend Associated with Operator Action for Sbloca,As Requested NOC-AE-000680, Forwards Rev 5 to 0PGP03-ZV-0001, Severe Weather Plan1999-10-20020 October 1999 Forwards Rev 5 to 0PGP03-ZV-0001, Severe Weather Plan NOC-AE-000683, Forwards 30-day Rept Concerning Significant Changes to Accepted Large Break Loss of Coolant Accident ECCS Evaluation Model for South Tx Project,Units 1 & 2,IAW 10CFR50.46(a)(3)(ii)1999-10-19019 October 1999 Forwards 30-day Rept Concerning Significant Changes to Accepted Large Break Loss of Coolant Accident ECCS Evaluation Model for South Tx Project,Units 1 & 2,IAW 10CFR50.46(a)(3)(ii) ML20217K9341999-10-15015 October 1999 Forwards SER Accepting Util 990609 Relief Request RR-ENG-2-4 for Relief from ASME Code,Section XI, Nondestructive Exam Requirements Applicable to Stp,Units 1 & 2,reactor Vessel Closure Head Nuts ML20217K9091999-10-15015 October 1999 Forwards SER Accepting Util 990609 Relief Request RR-ENG-2-3 from ASME Code,Section Xi,Nondestructive Exam Requirements Applicable to South Texas Project,Units 1 & 2, Pressurizer Support Attachment Welds 05000498/LER-1999-008, Forwards LER 99-008-00 Re Turbine Trip That Occurred While Performing Main Turbine Emergency Trip Test.Commitments Made by Licensee Are Listed in Corrective Actions Section of LER1999-10-12012 October 1999 Forwards LER 99-008-00 Re Turbine Trip That Occurred While Performing Main Turbine Emergency Trip Test.Commitments Made by Licensee Are Listed in Corrective Actions Section of LER NOC-AE-000674, Forwards Requested Estimates of Needs for Operator Licensing Exams,Per AL-99-03, Operator Licensing National Exam Schedule1999-10-12012 October 1999 Forwards Requested Estimates of Needs for Operator Licensing Exams,Per AL-99-03, Operator Licensing National Exam Schedule NOC-AE-000625, Requests Partial Relief from ASME Section XI Visual Exam Requirements of IWA-5242(a).Relief Request Is Based on Provisions of Draft ASME Section XI Code Case N-616,which Is Expected to Be Published in Near Future1999-10-0707 October 1999 Requests Partial Relief from ASME Section XI Visual Exam Requirements of IWA-5242(a).Relief Request Is Based on Provisions of Draft ASME Section XI Code Case N-616,which Is Expected to Be Published in Near Future NOC-AE-000610, Requests Relief from ASME Section XI Code Nondestructive Exam Requirements of IWA-5250(a)(2) for Second Inservice Insp Interval,Per Provisions of 10CFR50.55a(3)(i)1999-10-0707 October 1999 Requests Relief from ASME Section XI Code Nondestructive Exam Requirements of IWA-5250(a)(2) for Second Inservice Insp Interval,Per Provisions of 10CFR50.55a(3)(i) NOC-AE-000653, Requests Relief from ASME Section XI Code Requirements of Table IWE-2500-1 for VT-3 Visual Exam of Seals & Gaskets on Airlocks,Hatches & Other Devices Required to Assure Containment leak-tight Integrity,Per 10CFR50.55a(a)(3)(i)1999-10-0707 October 1999 Requests Relief from ASME Section XI Code Requirements of Table IWE-2500-1 for VT-3 Visual Exam of Seals & Gaskets on Airlocks,Hatches & Other Devices Required to Assure Containment leak-tight Integrity,Per 10CFR50.55a(a)(3)(i) ML20217C3221999-10-0707 October 1999 Forwards Insp Repts 50-498/99-16 & 50-499/99-16 on 990808-0918.No Violations Noted.Insp Generally Characterized by safety-conscious Operations,Sound Engineering & Maint Practices & Careful Radiological Work Controls 05000499/LER-1999-006, Forwards LER 99-006-00,re Entry Into TS 3.0.3.Licensee Commitments Listed in Corrective Actions Section of Attachment1999-09-30030 September 1999 Forwards LER 99-006-00,re Entry Into TS 3.0.3.Licensee Commitments Listed in Corrective Actions Section of Attachment ML20212L1651999-09-30030 September 1999 Responds to STP Nuclear Operating Co 981012 & s Which Provided Update to TS Bases Pages B 3/4 8-14 Through B 3/4 8-17.NRC Staff Found Change Consistent with TS 3/4.8.2 DC Sources. Staff Found & Deleted Typographical Error NOC-AE-000664, Forwards Rev 1 to STP Electric Generating Station Unit 1 Cycle 9 COLR & Rev 1 to STP Electric Generating Station Unit 2 Cycle 7 Colr1999-09-30030 September 1999 Forwards Rev 1 to STP Electric Generating Station Unit 1 Cycle 9 COLR & Rev 1 to STP Electric Generating Station Unit 2 Cycle 7 Colr ML20212J7141999-09-29029 September 1999 Forwards Insp Repts 50-498/99-15 & 50-499/99-15 on 990920-24 at South Texas Project Electric Generating Station.No Violations Noted.Insp Covered Requalification Training Program & Observation of Requalification Activities NOC-AE-000646, Informs NRC That STP Nuclear Operating Co Is Y2K Ready IAW Nei/Nusmg 97-07 Guidelines & Also Provides Response to NRC Ltr1999-09-28028 September 1999 Informs NRC That STP Nuclear Operating Co Is Y2K Ready IAW Nei/Nusmg 97-07 Guidelines & Also Provides Response to NRC Ltr ML20212J0651999-09-27027 September 1999 Discusses Licensee 980330 Response to GL 97-06, Degradation of SG Internals. Concludes That Response to GL Provides Reasonable Assurance That Condition of SG Internals in Compliance with Current Licensing Bases for Facility ML20212F1791999-09-24024 September 1999 Discusses 990923 Meeting Conducted in Region IV Ofc Re Status of Activities to Support Confirmatory Order, ,modifying OL & to Introduce New Director,Safety Quality Concerns Program.List of Attendees Encl ML20212E9091999-09-23023 September 1999 Discusses GL 98-01, Year 2000 Readiness of Computer Sys at Npps, Supplement 1 & STP Nuclear Operating Co Response for STP Dtd 990629.Understands That at Least One Sys or Component Listed May Have Potential to Cause Transient ML20212F2111999-09-22022 September 1999 Forwards Review of SG 90-day Rept, South Texas Unit-2 Cycle 7 Voltage-Based Repair Criteria Rept, Submitted by Util on 990119 NOC-AE-000633, Forwards Rev 3 to SG-99-04-005, STP 1RE08 Outage Condition Monitoring Rept & Final Operational Assessment. Rept Satisfies Reporting Requirements of NEI 97-06,dtd Dec 19971999-09-21021 September 1999 Forwards Rev 3 to SG-99-04-005, STP 1RE08 Outage Condition Monitoring Rept & Final Operational Assessment. Rept Satisfies Reporting Requirements of NEI 97-06,dtd Dec 1997 NOC-AE-000634, Forwards Addl Info Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Povs. MOV design-basis Review Checklist,Encl1999-09-21021 September 1999 Forwards Addl Info Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Povs. MOV design-basis Review Checklist,Encl NOC-AE-000649, Forwards Current Annual Financial Data for STP Electric Generating Station Per 10CFR50.71(b),acting on Behalf of Central Power & Light Co,City of Austin,Tx,City Public Svc Board of San Antonio & Hl&P1999-09-21021 September 1999 Forwards Current Annual Financial Data for STP Electric Generating Station Per 10CFR50.71(b),acting on Behalf of Central Power & Light Co,City of Austin,Tx,City Public Svc Board of San Antonio & Hl&P 05000499/LER-1999-005, Forwards LER 99-005-00,re Esfa Following Loss of Power to Standby Transformer 2 Due to Electrical Fault.Licensee Commitments Are Listed in Corrective Actions Section of LER1999-09-20020 September 1999 Forwards LER 99-005-00,re Esfa Following Loss of Power to Standby Transformer 2 Due to Electrical Fault.Licensee Commitments Are Listed in Corrective Actions Section of LER ML20212D9171999-09-16016 September 1999 Informs That on 990818,NRC Completed Midcycle PPR of South Texas Project & Identified No Areas in Which Performance Warranted Insp Beyond Core Insp Program.Details of Insp Plan Through Mar 2000 & Historical Listing of Plant Issues,Encl ML20216F5471999-09-15015 September 1999 Discusses 990914 Meeting Conducted at Region Iv.Meeting Was Requested by Staff to Introduce New Management Organization to Region IV & to Discuss General Plant Performance & Mgt Challenges IR 05000498/19990121999-09-14014 September 1999 Forwards Insp Repts 50-498/99-12 & 50-499/99-12 on 990816-19.Three Violations Occurred & Being Treated as Ncvs. Areas Examined During Insp Included Portions of Access Authorization & Physical Security Programs 05000498/LER-1999-007, Forwards LER 99-007-00 Re Train 'B' CR Makeup & Cleanup Filtration Sys Being Inoperable for Greater than Aot.Util Intends to Append Addl Info Section of LER with Brief Description of Test Results,Rather than Submit Separate LER1999-09-13013 September 1999 Forwards LER 99-007-00 Re Train 'B' CR Makeup & Cleanup Filtration Sys Being Inoperable for Greater than Aot.Util Intends to Append Addl Info Section of LER with Brief Description of Test Results,Rather than Submit Separate LER ML20211P8201999-09-0909 September 1999 Forwards SE Authorizing 990224 Submittal of First 10-year Interval ISI Program Plan - Relief Request RR-ENG-24,from ASME Section XI Code,Table IWC-2500-1 NOC-AE-000638, Forwards License Renewal Applications & Certifications of Medical Exam for Seven Listed Licensed Operators at Stp,Per 10CFR55.57.Encl Withheld,Per 10CFR2.790(a)(6)1999-09-0909 September 1999 Forwards License Renewal Applications & Certifications of Medical Exam for Seven Listed Licensed Operators at Stp,Per 10CFR55.57.Encl Withheld,Per 10CFR2.790(a)(6) ML20211P7671999-09-0909 September 1999 Forwards SER Authorizing Licensee 990517 Alternative Proposed in Relief Request RR-ENG-2-8 to Code Case N-491-2 for Second 10-year Insp Interval of South Texas Project, Units 1 & 2,pursuant to 10CFR50.55a(a)(3)(i) ML20211P7871999-09-0909 September 1999 Forwards Safety Evaluation Re First 10-yr Interval Inservice Insp Program Plan Request for Relief RR-ENG-31 IR 05000498/19990141999-09-0303 September 1999 Forwards Insp Repts 50-498/99-14 & 50-499/99-14 on 990627-0807.Apparent Violations Identified & Being Treated as Noncited Violations Consistent with App C of Enforcement Policy NOC-AE-000562, Requests Relief from Contruction Code non-destructive Exam Requirements for Repair/Replacement Activities During Second Inservice Insp Interval of Units 1 & 2,IAW Provisions of 10CFR50.55a(a)(3)(i)1999-08-31031 August 1999 Requests Relief from Contruction Code non-destructive Exam Requirements for Repair/Replacement Activities During Second Inservice Insp Interval of Units 1 & 2,IAW Provisions of 10CFR50.55a(a)(3)(i) ML20212A4351999-08-27027 August 1999 Discusses Investigation Rept OI-4-1999-009 Re Activites at South Texas Project.Oi Investigation Initiated in Response to Alleged Employment Discrimination Complaint. Allegation Not Substantiated.No Further Action Planned NOC-AE-000617, Forwards semi-annual Fitness for Duty Program Performance Rept for 990101-990630,IAW 10CFR26.71(d)1999-08-26026 August 1999 Forwards semi-annual Fitness for Duty Program Performance Rept for 990101-990630,IAW 10CFR26.71(d) ML20211J2511999-08-26026 August 1999 Discusses Proposed TS Change on Replacement SG Water Level Trip Setpoint for Plant,Units 1 & 2 NOC-AE-000585, Provides Notification That South Texas Project Has Completed Integrity Evaluation of Units 1 & 2 Reactor Coolant Pump Casings Required by Paragraph (D) of Code Case N-4811999-08-25025 August 1999 Provides Notification That South Texas Project Has Completed Integrity Evaluation of Units 1 & 2 Reactor Coolant Pump Casings Required by Paragraph (D) of Code Case N-481 ML20211F4421999-08-24024 August 1999 Forwards SE Authorizing Licensee 990513 Request for Relief RR-ENG-2-13,seeking Relief from ASME B&PV Code Section Xi,Exam Vessel shell-to-flange Welds for Second ISI Intervals ML20211F5031999-08-23023 August 1999 Forwards SE Authorizing Licensee 990315 Request for Relief RR-ENG-30,seeking Relief from ASME B&PV Code,Section Xi,Nde Requirements Applicable to Stp,Unit 2 SG Welds ML20212A4391999-08-17017 August 1999 Discusses Investigation Rept OI-4-1999-023 Re Activities at South Texas Project.Oi Investigation Initiated in Response to Alleged Employment Discrimination for Initiating Condition Report to Document Unauthorized Work Practices ML20210U1271999-08-16016 August 1999 Forwards Insp Repts 50-498/99-08 & 50-499/99-08 on 990517-21 & 0607-10.No Violations Noted.Corrective Action Program Was Reviewed 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 ML20211B7881999-08-10010 August 1999 Transmits Summary of Two Meetings with Risk-Informed TS Task Force in Rockville,Md on 990514 & 0714 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 NOC-AE-000603, Informs of Addition of Restriction to SRO License 42658, for KM Espinoza,Effective 990721,per 10CFR50.74.Encl Info Withheld,Per 10CFR2.790(a)(6)1999-07-29029 July 1999 Informs of Addition of Restriction to SRO License 42658, for KM Espinoza,Effective 990721,per 10CFR50.74.Encl Info Withheld,Per 10CFR2.790(a)(6) NOC-AE-000470, Forwards Amend 12 to STP Fire Hazards Analysis Rept. Summary of Changes Made Under Provision of 10CFR50.59 Also Encl1999-07-28028 July 1999 Forwards Amend 12 to STP Fire Hazards Analysis Rept. Summary of Changes Made Under Provision of 10CFR50.59 Also Encl NOC-AE-000599, Forwards STP Unit 1,Cycle 9 Startup Testing Summary Rept. No New Licensing Commitments Contained in Ltr1999-07-28028 July 1999 Forwards STP Unit 1,Cycle 9 Startup Testing Summary Rept. No New Licensing Commitments Contained in Ltr NOC-AE-000589, Forwards Rev to 1RE08 ISI Summary Repts for Repairs & Replacements & for Sys Pressure Tests,Corecting Date of End of Insp Interval Provided in Item 9 of from NIS-1 from 09/24/99 to 09/24/20001999-07-26026 July 1999 Forwards Rev to 1RE08 ISI Summary Repts for Repairs & Replacements & for Sys Pressure Tests,Corecting Date of End of Insp Interval Provided in Item 9 of from NIS-1 from 09/24/99 to 09/24/2000 ML20210F3851999-07-26026 July 1999 Forwards Exam Repts 50-498/99-301 & 50-499/99-301 on 990706- 15.Exam Included Evaluation of 9 Applicants for SO Licenses & 8 Applicants for RO Licenses 1999-09-09
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217K9341999-10-15015 October 1999 Forwards SER Accepting Util 990609 Relief Request RR-ENG-2-4 for Relief from ASME Code,Section XI, Nondestructive Exam Requirements Applicable to Stp,Units 1 & 2,reactor Vessel Closure Head Nuts ML20217K9091999-10-15015 October 1999 Forwards SER Accepting Util 990609 Relief Request RR-ENG-2-3 from ASME Code,Section Xi,Nondestructive Exam Requirements Applicable to South Texas Project,Units 1 & 2, Pressurizer Support Attachment Welds ML20217C3221999-10-0707 October 1999 Forwards Insp Repts 50-498/99-16 & 50-499/99-16 on 990808-0918.No Violations Noted.Insp Generally Characterized by safety-conscious Operations,Sound Engineering & Maint Practices & Careful Radiological Work Controls ML20212L1651999-09-30030 September 1999 Responds to STP Nuclear Operating Co 981012 & s Which Provided Update to TS Bases Pages B 3/4 8-14 Through B 3/4 8-17.NRC Staff Found Change Consistent with TS 3/4.8.2 DC Sources. Staff Found & Deleted Typographical Error ML20212J7141999-09-29029 September 1999 Forwards Insp Repts 50-498/99-15 & 50-499/99-15 on 990920-24 at South Texas Project Electric Generating Station.No Violations Noted.Insp Covered Requalification Training Program & Observation of Requalification Activities ML20212J0651999-09-27027 September 1999 Discusses Licensee 980330 Response to GL 97-06, Degradation of SG Internals. Concludes That Response to GL Provides Reasonable Assurance That Condition of SG Internals in Compliance with Current Licensing Bases for Facility ML20212F1791999-09-24024 September 1999 Discusses 990923 Meeting Conducted in Region IV Ofc Re Status of Activities to Support Confirmatory Order, ,modifying OL & to Introduce New Director,Safety Quality Concerns Program.List of Attendees Encl ML20212E9091999-09-23023 September 1999 Discusses GL 98-01, Year 2000 Readiness of Computer Sys at Npps, Supplement 1 & STP Nuclear Operating Co Response for STP Dtd 990629.Understands That at Least One Sys or Component Listed May Have Potential to Cause Transient ML20212F2111999-09-22022 September 1999 Forwards Review of SG 90-day Rept, South Texas Unit-2 Cycle 7 Voltage-Based Repair Criteria Rept, Submitted by Util on 990119 ML20212D9171999-09-16016 September 1999 Informs That on 990818,NRC Completed Midcycle PPR of South Texas Project & Identified No Areas in Which Performance Warranted Insp Beyond Core Insp Program.Details of Insp Plan Through Mar 2000 & Historical Listing of Plant Issues,Encl ML20216F5471999-09-15015 September 1999 Discusses 990914 Meeting Conducted at Region Iv.Meeting Was Requested by Staff to Introduce New Management Organization to Region IV & to Discuss General Plant Performance & Mgt Challenges IR 05000498/19990121999-09-14014 September 1999 Forwards Insp Repts 50-498/99-12 & 50-499/99-12 on 990816-19.Three Violations Occurred & Being Treated as Ncvs. Areas Examined During Insp Included Portions of Access Authorization & Physical Security Programs ML20211P8201999-09-0909 September 1999 Forwards SE Authorizing 990224 Submittal of First 10-year Interval ISI Program Plan - Relief Request RR-ENG-24,from ASME Section XI Code,Table IWC-2500-1 ML20211P7671999-09-0909 September 1999 Forwards SER Authorizing Licensee 990517 Alternative Proposed in Relief Request RR-ENG-2-8 to Code Case N-491-2 for Second 10-year Insp Interval of South Texas Project, Units 1 & 2,pursuant to 10CFR50.55a(a)(3)(i) ML20211P7871999-09-0909 September 1999 Forwards Safety Evaluation Re First 10-yr Interval Inservice Insp Program Plan Request for Relief RR-ENG-31 IR 05000498/19990141999-09-0303 September 1999 Forwards Insp Repts 50-498/99-14 & 50-499/99-14 on 990627-0807.Apparent Violations Identified & Being Treated as Noncited Violations Consistent with App C of Enforcement Policy ML20212A4351999-08-27027 August 1999 Discusses Investigation Rept OI-4-1999-009 Re Activites at South Texas Project.Oi Investigation Initiated in Response to Alleged Employment Discrimination Complaint. Allegation Not Substantiated.No Further Action Planned ML20211J2511999-08-26026 August 1999 Discusses Proposed TS Change on Replacement SG Water Level Trip Setpoint for Plant,Units 1 & 2 ML20211F4421999-08-24024 August 1999 Forwards SE Authorizing Licensee 990513 Request for Relief RR-ENG-2-13,seeking Relief from ASME B&PV Code Section Xi,Exam Vessel shell-to-flange Welds for Second ISI Intervals ML20211F5031999-08-23023 August 1999 Forwards SE Authorizing Licensee 990315 Request for Relief RR-ENG-30,seeking Relief from ASME B&PV Code,Section Xi,Nde Requirements Applicable to Stp,Unit 2 SG Welds ML20212A4391999-08-17017 August 1999 Discusses Investigation Rept OI-4-1999-023 Re Activities at South Texas Project.Oi Investigation Initiated in Response to Alleged Employment Discrimination for Initiating Condition Report to Document Unauthorized Work Practices ML20210U1271999-08-16016 August 1999 Forwards Insp Repts 50-498/99-08 & 50-499/99-08 on 990517-21 & 0607-10.No Violations Noted.Corrective Action Program Was Reviewed 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 ML20211B7881999-08-10010 August 1999 Transmits Summary of Two Meetings with Risk-Informed TS Task Force in Rockville,Md on 990514 & 0714 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 ML20210F3851999-07-26026 July 1999 Forwards Exam Repts 50-498/99-301 & 50-499/99-301 on 990706- 15.Exam Included Evaluation of 9 Applicants for SO Licenses & 8 Applicants for RO Licenses ML20210D9011999-07-23023 July 1999 Forwards Safety Evaluation Re Inservice Testing Plan Request for Relief RR-5 Component Cooling Water & Safety Injection Sys Containment Isolation Check Valve Closure Test Frequency ML20210C2111999-07-21021 July 1999 Forwards Insp Repts 50-498/99-13 & 50-499/99-13 on 990516-0626.Two Severity Level IV Violations Occurred & Being Treated as Noncited Violations ML20209H9231999-07-16016 July 1999 Discusses South Texas Project,Units 1 & 2 Updated Response to GL 92-01,Rev 1,Suppl 1, Rv Structural Integrity. Staff Revised Info for Plant in Rvid & Being Released as Rvid Version 2 ML20207H6261999-07-0808 July 1999 Responds to Re 2nd 10 Yr Interval ISI Program Plan Request to Use ASME Section XI Code Case N-546, Alternative Requirements for Qualification of VT-2 Exam Personnel,Section Xi,Division 1.Forwards SE ML20195J6731999-06-17017 June 1999 Responds to Re Request for Relief from ASME Code, Section Xi,Requirement to Perform VT-1 Visual Exam on Accessible Surfaces of RPV Flange Inserts (Bushings). Safety Evaluation Encl ML20195F7561999-06-10010 June 1999 Forwards Insp Repts 50-498/99-11 & 50-499/99-11 on 990404-0515 at South Texas Project Electric Generating Station,Units 1 & 2.No Violations Were Identified ML20207H0031999-06-0909 June 1999 Discusses 990419 Meeting in Region IV Ofc Re South Texas Project EP Program Status,Including Initiatives in EP Program,Future Revs to EP & Dept Performance Indicators. Meeting Attendance List & Licensee Presentation Encl ML20195G3241999-06-0909 June 1999 Ack Receipt of Re Changes to Plant Emergency Plan Change Notice 18-2.No Violations of 10CFR50.54(q) Were Identified ML20207D7371999-05-28028 May 1999 Discusses Re Process for Reclassification of non- Risk Significant Components.Forwards Concerns & Cautions for Consideration Based on Limited Review of Reclassification Process Overview That Was Provided IR 05000498/19980151999-05-28028 May 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-498/98-15 & 50-499/98-15.Corrective Actions Reviewed & Found to Be Responsive to Issues Raised ML20207E1961999-05-25025 May 1999 Forwards Insp Repts 50-498/99-09 & 50-499/99-09 on 990503-06.No Violations Noted.Primary Focus of Insp to Review Operational Status of Emergency Preparedness Program ML20207A8771999-05-25025 May 1999 Forwards RAI Re Licensee 960213 180-day Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Plant,Units 1 & 2.Response Requested within 120 Days from Date of Ltr IR 05000498/19990061999-05-12012 May 1999 Submits Corrected First Page of Cover Ltr Re Insp Repts 50-498/99-06 & 50-499/99-06 Conducted on 990221-0403.Subj Line Was Corrected ML20206S3201999-05-12012 May 1999 Forwards Corrected First Page of Cover Ltr,Which Forwarded Insp Repts 50-498/99-06 & 50-499/99-06,issued on 990505. Subj Line Indicated on NOV Was Incorrect ML20206N5481999-05-11011 May 1999 Informs That NRC Office of Nuclear Reactor Regulation Reorganized Effective 990328.As Part of Reorganization,Div of Licensing Project Mgt Created.Ra Gramm Will Be Section Chief for South Texas Project.Organization Chart Encl ML20206J4321999-05-0707 May 1999 Informs That on 990407,NRC Administered Gfes of Written Operator Licensing Exam.Licensee Facility Did Not Participate in Exam,However,Copy of Master Exam with Answer Key Encl for Info.Without Encl ML20206J4211999-05-0606 May 1999 Ack Receipt of in Response to & Insp Repts 50-498/99-04 & 50-499/99-04,confirming Commitments as Stated in 990225 Exit Meeting ML20206H6201999-05-0505 May 1999 Forwards Insp Repts 50-498/99-06 & 50-499/99-06 on 990221- 0403.Three Violations of NRC Requirements Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20206H3811999-05-0505 May 1999 Responds to STP Nuclear Operating Co Which Provided Update to TS Bases Pages B 3/4 2-6.Revised TS Bases B 3/4 2-6 That NRC Staff Will Use to Update Copy of STP Bases Encl ML20206H2001999-05-0404 May 1999 Forwards Exemption from Requirements of 10CFR50.60, Acceptance Criteria for Fracture Prevention Measures for Lightwater Nuclear Power Reactors for Normal Operation ML20206B6091999-04-22022 April 1999 Forwards Insp Repts 50-498/99-10 & 50-499/99-10 on 990405-09.No Violations Noted ML20206B3281999-04-22022 April 1999 Forwards Insp Repts 50-498/99-07 & 50-499/99-07 on 990405- 09.Insp Focused on Radiological Controls in Place During Unit Refueling Outage.Violations Identified Involving Failure to Follow Radiation Work Permit Instructions ML20205Q8151999-04-16016 April 1999 Forwards Request for Addl Info Re Proposed Amends on Operator Action for small-break-LOCA,dtd 980728.Response Requested within 45 Days of Ltr Date ML20205P5821999-04-15015 April 1999 Advises That Version of Application & Affidavit Dtd 990127, Executed by Ha Sepp,Marked Proprietary,Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954,as Amended 1999-09-09
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August 11, 1997 Mr. William T. Cottle Group-.Vice-President, Nuclear Houston Lighting & Power Company
. South Texas Project Electric-Generating Station
-P.O. Box 289
=Wadsworth,-TX 77483 ,
SUBJECT:
-REQUEST FOR ADDITIONAL INFORMATION ON THE PROPOSED LICENSE AMENDMENT REGARDING REACTOR COOLANT SYSTEM FLOW MONITORING SOUTH TEXAS PROJECT, UNITS 1 AND 2 (STP) (TAC NOS. M99245-AND M99246)
Dear Mr.1Cottle:
The staff has reviewed your application for amendment dated August 6,1997, to allow the use of elbow taps to measure reactor coolant system (RCS) flow rate at the STP, The staff has identified a need for additional information as !
requested in the enclosed request for additional information (RAI).
-If you have any questions regarding this request, please contact me at (301) 415-1326.
Sincerely, Orig signed by Thomas W.-Alexion, Project Manager Project Directorate IV-1 >
Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation )
Docket Nos.-50-498 and 50-499
Enclosure:
Request for Additional Information
=cc w/ enc 1: -See next page /
DISTRIBUTION: /
- Docket File GHill (4) PUBLIC CHawes TAlexion (2) PDIV-1 r/f ACRS JRoe EAdensam (EGAl)
TGwynn. RIV OGC MShuaibi CDoutt-Document Name: STP99245.RAI 0FC PM/PD(A d LA/PD4-1 BC/SRXBfNRR e MhAphdR /
NAMEi TAlexioN[ CHawes(1Ald JLyonN (b
DATE [/[/97 2///97 9/ll/97- N N /97[
< COPY dEhN0 'YES/NO YES/ h [ENNd' u 0FFICIAL RECORD COPY '
fj" "S" -
ggitBUS#
11Il!Ilill,1.1!Il .
gaairg y- % UNITE 3 STATES
,1 NUCLEAR REGULATORY COMMISSION
Mr. William T. Cottle Group Vice-President, Nuclear Houston Lighting & Power Company South Texas Project Electric Generating Station P.O. Box 289 Wadsworth, TX 77483
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION ON THE PROPOSED LICENSE AMENDMENT REGARDING REACTOR COOLANT SYSTEM FLOW MONITORING - SOUTH TEXAS PROJECT, UNITS 1 AND 2 (STP) (TAC NOS. M99245 AND M99246)
Dear Mr. Cottle:
The staff has reviewed your application for amendment dated Auguit 6, 1997, to allow the use of elbow taps to measure reactor coolant system (R S) flow rate at the STP. The staff has identified a need for additional infc1 nation as-requested in the enclosed request for additional information (RA').
If you Save any questions regarding this request, please contact me at (301) 415-136.
, Sincerely, n
rJ m n .Jhpu Thomas W. Alexion, Project planager Project Directorate IV ,
Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation Docket Nos. 50-498 and 50-499
Enclosure:
Request for Additional Information cc w/ encl: See next page
-we
Mr. William T. Cottle Houston Lighting & Power Company South Texas, Units 1 & 2 Cc:
Mr. David P. Loveless Jack R. Newman, Esq.
Senior Resident inspector Morgan, Lewis & Bockius U.S. Nuclear Regulatory Commission 1800 M Street, N.W.
P. O. Box 910 Washington, DC 20036-5869 Bay City TX 77414 Mr. Lawrence E. Martin Mr. J. C. Lanier/M. B. Lee General Manager, Nuclear Assurance Licensing City of Austin Houston Lighting and Power Company Electric Utility Department P. O. Box 289 721 Barton Springs Road Wadsworth, TX 77483 Austin, TX 78704 Rufus S. Scott Mr. M. T. Hardt Associate General Counsel Mr. W. C. Gunst Houston Lighting and Power Company City Public Service Board P. O. Box 61867 P. O. Box 1771 Houston, TX 77208 San Antonio, TX 78296 Joseph R. Egan, Esq.
Mr. G. E. Vaughn/C. A. Johnson Egan & Associates, P.C.
Central Power and Light Company 2300 N Street, N.W.
P. O. Box 289 Washington, DC 20037 Mail Code: N5012 Wadsworth, TX 74483 Office of the Governor ATTN: Andy Barrett, Director INP0 Environmental Policy Records Center P. O. Box 12428 700 Galleria Parkway Austin, TX 78711 Atlanta, GA 30339-3064 Arthur C. Tate, Director Regional Administrator, Region IV Division of Compliance & Inspection
. U.S. Nuclear Regulatory Commission Bureau of Radiation Control 611 Ryan Plaza Drive, Suite 400 Texas Department of Health Arlington, TX 76011 1100 West 49th Street Austin, TX 78756 Dr. Bertram Wolfe 15453 Via Vaquero Texas Public Utility Commission Monte =Sereno, CA 95030 ATTN: Mr. Glenn W. Dishong 7800 Shoal Creek Blvd.
Judge, Matagorda County Suite 400N Matagorda County. Courthouse Austin, TX 78757-1024 1700 Seventh Street Bay City, TX 77414
1 RE0VLST FOR AD91T10NAL INFORMAT10N PROPOSED AMENDMENT TO ALLOW USE OF ELBOW TAPS TO MEASURE REACTOR COOLANT SYSTEM FLOW RATE
- 1. Section 2.0 states that surveil'ence requirement (SR) 4.2.5, which currently requires the performance of precision heat balance measurements every 18 months, will no longer specify the method to be used for RCS flow measurement. Explain the elimination of the reference to RCS flow measurement methodology from the SR (i.e., why not reference both the precision heat balance measurements and the specific elbow tap methodology described in the application). Additionally, the proposed SR does not provide a reference as to when the measurements are to be taken. Section 2 of the submittal references 'beginning of cycle" as does the analysis, include such a reference in the SR or justify its ommission. Also include the power level at which the surveillance is to be performed at in the proposed SR (per analysis assumption) or justify its ommission.
- 2. Based on the change 4 RCS flow measurement methodology, are any revisions required
- the revised thermal design procedure? Normally the RTDP references th t..lorimetric. Has streaming uncertainty increased from the assumptiuns made in the RTDP7 Are the uncertainties for the elbow tap transmitters zerced out in the South Texas RTDP7
- 3. Describe how the calorimetric uncertainties will be accounted for in the proposed methodology given that the proposed elbow tap correlation method relies on previous calorimetrics.
- 4. Section 3.4.2 states that calorimetric flows from all fuel cycles are evalcated for use in defining baseline calorimetric flow. What does the term
- evaluated" mean? Was the average for all cycles used? How many cycles of data were utilized?
- 5. Section 3.4.2, " Baseline Elbow Tap AP," states that the average AP from all elbow taps is used as the basis for the baseline elbow tap coefficient. Considering potential differences in installation and initvidual elbow ta) and hydraulic characteristics, explain why this approach is accepta)1e. The AP data su) plied seems to indicate that loop 4 is consistently different from the otler loops, is this measurement an indication of different flow characteristics or a sensing element installation effects? Would separate flow coefficients for each elbow tap better reflect flows? If you choose to use the proposed averaging method, provk'e a justification of this method including (but not limited to) a compe non of this method to using individual elbow tap correlation and show that your proposed method is conservative.
Identify all alaces (analyses, calculation methods, etc. that may be affected by t1is approach and specify whether this would) result in a net benefit or penalty (i.e., why are you proposing this approach in lieu of correlating each elbow tap individually?).
ENCLOSURE
2-
- 6. Section 3.4.2, ' Flow Verification for Future Cycles," states the average of all elbow tap & s measured at or near full power... What is considered at or near full power?
- 7. Section 3.4.2, ' Elbow Tap Flow Measurement Procedure," states that calorimetric flows that fell well outside the allowance (either high or low) should not be used in defining baseline flow. How was the allowance and screening criteria determined? Was this procedure used at South Texas and were any calorimetric measurements deleted from the baseline flow determination.
- 8. The RTDP calorimetric flow uncertainty is given as a 95/95 value. Do the elbow tap flow measurements and best estimate hydraulic analysis provide equivalent results with regard to the 95/95 value? In Section 3.4.2 of your submittal you proposed to compare R to 1.004*R'. In Section 3.5.2 of your submittal you stated that the best estimate flow analysis has an accuracy of 12%. Discuss how this uncertainty (associated with your best estiinate analytical methodology) is accounted for. Provide a more detailtd justification of your proposal to allow elbow taps to exceed the best estimate flow by as much as 0.4% and still be accepted at a valid measurement of flow. Explain this from an RTDP uncertainty assumption perspective as well as from the perspective of uncertainties assumed in other analyses that include an RCS flow assumption. Provide all places (analyses, calculation methods, etc.) that are affected by this credit.
- 9. Section 3.5 states that the component & accuracy for the Prairie Island measurements was established by calibrations to be within 11% of the measured op. The sum of the & s measured across the reactor and steam generator were within 1% of the pump & , confirming measurement accuracy.
Explain how this confirms accuracy of the measured M .
- 10. In Section 3.6.3, " Evaluation of Calorimetric Flows," the second bullet references the " baseline calorimetric flow defined above." Where is this reference in the submittal?
- 11. Provide and explain plant saecific data and or exptrience of the temperature profile in the lot leg as a result of streaming and its plant specific effect on temperature readings. Provide information on this phenomenon for each cycle considered in your proposed methodology.
Explain the effect of power level on this phenomenon. In addition explain how the hot leg temperature was obtained for the calorimetrics used (i.e., wAs the high, average of each loop or average of all RTDs used?).
- 12. Provide plant specific configurations of hot leg RTDs and elbow taps.
With regard to RTDs, Figure 3.3-2 seems to indicate that an average of the three RTDs (assuming that they are located at 0, 120, and 2'O w ws-M6de-**'P*db w *rh4-- -a +mw- 4':
degrees) would eliminate the difference. Explain the streaming effect in this case and include a temperature profile plot for the hot leg cross section. Provide similar plots for South Texas.
- 13. In your cerrelations you neglect any changes in specific volume due to cold leg temperature changes. Provide a justification of this approach with regard to potential future changes in parameters that may affect the specific volume of the cold leg watet (e.g., temperature and pressure).
- 14. An implicit assumption in your correlation methodology is that the correlation coefficient (K) in the following equation remains constant.
How will your methodology address changes to this coefficient should they occur given that you're proposing to freeze the current coefficients.
W = K (MP)*
- 15. Section 3.4.1 states.
- tests have demonstrated that elbow tap flow measurements have a high degree of repeatability...." Were such tests performed for configurations similar to )lant installations - with short stretches of straight pipe upstream of tie elbow taps? Provide results and conclusions. (i.e., justify your assumption of repeatability for the plant specific configuration in light of the lack of straight pipe upstream of the elbow taps.)
- 16. Explain the statement " Repeatability and accuracy are improved when all elbow tap AP measurements are used" in Section 3.4.2 and discuss the benefits realized from this approach.
- 17. Section 1-5-4 of " Fluid Meters, Their Theory and Applications," 6th Edition, Howard S. Bean, ASME, New York, 1971; reference 1 to your
... be arithmetical mean values submittal, obtained bystates, "Letover averaging the the values wholeofsec pg, tion, A, and. if the fluid motion is not strictiv steady (laminar) but turbulent. a time averaae over the section." How was this considered / applied in your proposed methodology?
- 18. Sections 1-5-27 and I-5-55 of " Fluid Meters, Their Theory and Applications," 6th Edition, Howard S. Bean, ASME, New York, 1971; reference 1 to your submittal, states, that "a uniform fluid velocity was assumed, thus neglecting any effect of normal stream turbulence." In addition, " Application, Part !! of Fluid Meters, Sixth Edition 1971, Interim Supplement 19.5 on Instrument and Apparatus " ASME, New York, 1972; provides guidance on length of piping required upstream of the elbow taps to ensure uniform velocity profiles. Considering that the recommended length of pipe does not exist upstream of the elbow taps in your plant, discuss how this was addressed in your proposed methodology,
1 1 !
! l
\ i t t i
i 19. ' Flow Messurement Engineering Handbook,' R. W. Miller, McGraw-Hill Book
, Company, New York,19831 gives an accuracy for elbow taps of 14%.
j- - Additionally, tists source states that the minimum length of piping as !
presented in Fluid Meters (see question above) is necessary to hold ;
t piping bias errors, due to piping influence, to less than 10.5%. It !
, further states that an additional 10.5% should be added to the flow- !
- coefficient accuracy value for any decrease in length of pipe. Discuss !
how each of these factors was addressed in your proposed methodology. !
List and justify the accuracy and precision values used in your l
< methodology and explain how they were applied. ;
- 20. Describe how feedwater venturt fouling and its effect on feedwater measurement uncertainty was addressed in the calorimetrics that will be ,
- used to derive the elbow tap coefficients. List the uncertainties for i feedwater measurement and explain how they were used to determine the !
overall uncertainty. In addition, discuss how feedwater venturi area !
expansion factor uncertainties were accounted for.
5 21. Discuss the type of quality assurance review performed on the analytical F model. How does this meet the requirements of 10 CFR Part 50 Appendix B7 i In addition, provide data relating to changes in the slant (steam 4 i generator tube plugging, fuel des'gn changes, etc.) t1at have affected flow condition and confim that the model was able to predict these l
i changes accurately. What confirmatory checks were perfomed to ensure t accuracy of the analytical model at South Texast $1nce the RCS loops 4
experience changes at different rates (e.g., steam generator tube plugging) provide this data on a loop specific basis, i '
- 22. Periodic confirmation of elbow tap characteristics is important in i ensuring reliability. How will you do this? In the proposed methodology you are proposing to use-the best estimate model to confira your elbow
- . tap readings. The best estimate methodology is used to confirm that your ,
" measured" flow is in agreement with your expected (predicted) flow.
Discuss the actions that you intend to take (evaluation, recalibrations, n etc.) should the elbow taps read higher / lower than your best estimate ^
predictions to ensure that flow ' measurements" are obtained in an
- acceptable manner and that they are not replaced by the unconfirmed analytical' method. The use of 'unconfimed analytical method" in this question refers to a prediction of. flow without confirmation through
. actual measurement. The staff requests that the licensee also commit to 5
= 1)~ notify the NRC of any changes to the hydraulic flow model in a scnner which~affects the results of the model and 2) contact the NRC for further 8
review of the methodology if the elbow tap-determined flow rate exceeds (becomes less conservat' ve than) the analytically determined flow rate.
< 23. Discuss the effect of vibration and turbulence induced noise on elbow tap -
measurement and how this was accounted for in your proposed methodology. '
Address erosion and deposit fomation with respect to the elbow tap f
?
t
..,_.i. .w..-. . -. ,.,_J_. . .-,. _., . ~, %._ ~.._, _ . .-%_ . -~+,m-,-.---.ie%e-~n . <w .;
1 5-instrument tube connection to the RCS legs. For exam)1e, if the throughwall penetration initially terminates with a starp edge at the leg inner wall surface, does this sharp edpe change with time due to flow impingement? If it changes, what is t!)e effect on indicated behavior?
If it does not change, wiat is the basis for that conclusion?
- 24. In Section 3.4.2 of ou stated, "If a known hydraulic
- change (e.g.,tubepfoursubmittal uggint was made before a cycle, calorimetric flow L
for the cycle should be ad;u)sted so all flows have a common hydraulic
- baseline." Was this approach used in your proposed methodology? If so,
- discuss how this was done and justify this approach.
l 25. Section 3.6.1 states, 'Considering all of the above, the overall impact i of the hydraulic changes was expected to be 0.3 to 0.9% flow over seven cycles of operation ..." However, Section 3.5.2 states that the best !
estimate flow analysis has an accuracy of 12%. Exslain how you were able !
l to predict the flow changes to a better accuracy tian that of the l analytical model. Similar statements were also made for Unit 2.
- 26. Section 3.6.2 states that AP measurements were obtained at 70% power for some of the cycles. Additionally, this section states that a decrease of 1.2% flow from zero to 100% power and 0.4% from 70% power to 100% power ,
exists. Justify these statements. How was this data obtained? Are you assuming a linear relationship between flow and power? If so, why?
Section 3.6.3 further states that in addition to the calorimetrics at 70%
power, calorimetric data was al:,o obtained shortly after full power was attained. Why was this data not used instead of the 70% data? Also .'
explain the statement, "Another adjustment was made in normalizing flows to the baseline flow to account for the decrease in cold Itg temperature
-in Cycles 6 and 7..."
- 27. Explain the statement in Section 3.6.4 that less precision was used when averaging cibow tap data during early cycles and how this was accounted i for in uncertainty tems. Also explain the statement that the difference l between elbow tap and best estimate flows would be about 1% if impeller smoothing sctually occurred before Cycle 1 (i.e., What was asaused for -
impeller smoothing and when did it occur? Justify this assumption).
Explain the statement for Unit 2 that if Cycle I had been used to define baseline calorimetric flow, the flow difference in Cycles 5 and 6 would be larger and would be a mNe representative indication of low leakage loading pattern impact. With regard to the statement that based on comparisons of adjusted calorimetric flows in Table 3.6-3, the Cycle 6 -
- - flow is almost 25 below the Cycle 1 flow,-it appears that a large portion
, of that difference-is attributable to impeller smoothing and tube L plugging. Present your understanding of what this 2% reduction is j attributable to. !
L 28. The first plots of Figures 3.6-1 and 3.6-2 show that the elbow tap flows L are higher than the best estimate flows whereas the second plots show the l
L L ,
. - - - -..-,-_ - _.- 22 [ $ 25 2 1 -.I2.- __-- -- ~ - . ._m.-_..
. _ _ _ , . - - ~ _ - . _ _ ~ . - _ _ -
l <everse is true. Explain this difference. Pro' vide a plot which includes
- 11 of the following (on the same plot) for comparison and/or the data ror such a plot 1) elbow tap flows (per your proposed methodology), 2) calorimetric flows, and 3) best estimate flows.
- 29. Please address each of the items in Attachment 1, " Staff Guidelines for Use of Elbow Taps for RCS Flow Rate Measurement," Item 1.0, "Use of Elbow Taps " and 2.0, " Assurance to Show that the Elbow Tap Correlation Remains Viable." Explain how your proposed method to measure RCS flow rate addresses each of the items of the above guidelines. Some specific questions pertaining to these items are given below.
- 30. Provide the correlation used to measure RCS flow rate by the use of elbow taps. If you use a correlation for the elbow taps that is in the form oft m K V(3PT(4J where: m - the RCS flow rate K - the elbow tap flow correlation coefficient AP= the elbow tap pressure drop, and p - the cold leg density please provide the values of correlation coefficient K for each of the 3 taps in each loop of the celd legs and information on determined, including background of the data used,(2)and(1) what how they were conservatism has been applied for these values. It is noted that because the elbow taps are not calibrated in a laboratory environment, as the feedwater venturi meters are, but only normalized against the
! calorimetric heat balance, we expect that a conservative margin will be I applied in this method.
- 31. Regarding the confirmation of the correlation coefficient K, a hydraulic i analytic prediction method is needed to confirm that the elbow tap-based flow rate indication is within the uncertainty bounds.
Please describe your hydraulic analysis program for estimating RCS flow rate including the inputs needed and the breakdown of items used in the calculations such as: RCS 100) pressure drops, flow fractions used to adjust the pressure drops in tie downcomer and the core regions, pressure drops for fuel, steam generator (SG) pressure drops, reactor coolant pump head, RCS pump wear, and tube plugging. Provide the results of using
- this program and also provide its accuracy in predicting RCS flow rate.
The results should show that the analysis program can predict past physical changes, such as from SG tube plugging and sleeving, core bundle changes, etc., within acceptable bounds of accuracy.
l
- 2. '2 7-~~ "~77~
?_. __ _ _ _ , _ , _
i Staff Guidelines for Use of Elbow Tans for RCS Flow Rate Measur-- nt i The RCS flow rate is one of the inputs for calculation of the Departure from Nucleate Boiling Ratio fDNBR). The transient and accident analyses include as inputs the initial condition of RCS thermal design flow. The minimum RCS flow
- rate requirement in the Technical Specifications (TS) is consistent with the 1 assumed RCS thermal design flow.
The criteria established in 10 CFR 50. Appendix A require a high degree of are not assurancethatspecifiedacceptablefueldesignlletts(SAFDL)(A00)arethat exceeded. The SAFDLs for anticipated operational occurrences i neither DNB nor melting at the fuel centerline occurs. The results of the :
. safety analyses calculation are used to assure that the SAFDLs are met. The nuclear industry has developed Limiting Safety System Settings (LS$$). !
- methodologies which combine uncertaint' es statistically. The validity of such !
- methodologies requires that input uncertainties be statistically valid. _
1 The staff believes that the most important potential safety need directly <
associated with RCS flow rate is maintenance of an adequate margin to prevent :
departure from nucleate boiling. The next safety need is providing a reactor i trip due to a low RCS flow rate, with the concerns being departure from nucleate boiling and an overtemperature condition. However, the importance of RCS flow rate to reactor trip is diminished by other trip parameters, such as -
loss of pump power, too large a temperature difference between the hot and -
cold legs, or high pressure; trip parameters that will often cause a trip prior-to a flow rate trip. ,
The staff has reviewed ine use of elbow taps for RCS flow measurement previously for another nuclear power plant and has developed guidelines for the acceptability of the use of cold leg elbow taps to measure RCS flow rate.
- This guidance follows. ,
1.0 Use of Elbow Tans ;
In using elbow taps for indication of RCS flow rate, one should assure that:
1.1 There'is' reasonable confirmation that'the elbow tap correlation used to determine RCS flow rate is accurate to within a known uncertainty and bias or that the perceived rate (correlation determined rate including ,
uncertainty and bias) is less than the actual flow rate.
.l.2 There is reasonable confimation to assure that the proposed method of i determining RCS flow rate remains within acceptable bounds of accuracy. l Reasonable confirmation that the originally determined RCS flow rate is accurate to within a known uncertainty and/or that it is less than the
, actual flow rate should be supported by either:
ATTACMENT 1-
~ ,,,.:.,-< ~ - ,
_ -,-J L -, T -T*' * *. * *C L:,_-4'C.L-.,J._.._..u_._..-._.m,--.---- - . - - - - , - - . ~ . _ _ _ - - - - _ _ _ - - _ -
(1) App 11able flow test data that correlates RCS flow instrumentation to flow rate, or (2) Some other method of correlating RCS flow rate to the RCS flow instrumentation.
2.0 Assurance to. Show that the Elbow Tan Correlation Remains Viable 2.1 'With an elbow tap correlation and an acceptance bound established, there is need to assure that the correlation remains viable. A reasonable a)proach is to provide an analysis program that correlates all physical c1anges in the RCS flow path to the RCS flow rate and use this for confirmation of the elbow tap measurements of flow rate.
(1) To confirm this, one should demonstrate that the elbow tap-based flow rate indication is within the uncertainty bound that was established-for the elbow tap correlation when compared to an analysis prediction. Primary em)hasis upon the analysis is acceptable since no change in el)ow tap correlation is anticipated when physical changes are made in the plant.
(2) An acce) table analysis program is one that accurately calculates plant c1anges in pump performance, core bundle changes, SG tube SG tube sleeving, SG replacement, and any other physical pluggingIntheRCSthataffecttheRCSflowrate(thesamecriteria changes as applied to the above confirmation process)..
2.2 Acceptability is established by comparing analysis results with available plant data.
(1) If the proposed elbow tap correlation is "best-estimate," then the staff will expect a direct comparison of elbow tap determined flow
! rate based upon the proposed elbow tap correlation.
(2) If the elbow tap correlation is conservative, then the staff will expect two comparisons - one with a best-estimate correlation coefficient that provides the best fit to the analysis and the other with the proposed correlation.
(3) If the elbow tap determined flow rate crosses over and becomes less conservative than the analytically determined flow rate, the NRC should be contacted for further review of acceptability.
L l
l l . .. __
_ _. _ .