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MONTHYEARML20212L1651999-09-30030 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 Project stage: Other 1999-09-30
[Table View] |
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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 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 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 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) 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 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 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 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-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-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-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 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 ML20211P7871999-09-0909 September 1999 Forwards Safety Evaluation Re First 10-yr Interval Inservice Insp Program Plan Request for Relief RR-ENG-31 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) 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) 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 ML20211J2511999-08-26026 August 1999 Discusses Proposed TS Change on Replacement SG Water Level Trip Setpoint for Plant,Units 1 & 2 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) 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-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-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-000582, Forwards 1RE08 ISI Summary Rept for Welds & Component Supports of STP Electric Generating Station,Unit 1. Summary Rept Satisfies Reporting Requirements of IWA-6000 of Section XI for Welds & Component Supports1999-07-26026 July 1999 Forwards 1RE08 ISI Summary Rept for Welds & Component Supports of STP Electric Generating Station,Unit 1. Summary Rept Satisfies Reporting Requirements of IWA-6000 of Section XI for Welds & Component Supports 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 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 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 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 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) 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 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 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 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 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 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 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 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 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 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 ML20206B6091999-04-22022 April 1999 Forwards Insp Repts 50-498/99-10 & 50-499/99-10 on 990405-09.No Violations Noted 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 ML20205P5951999-04-15015 April 1999 Forwards RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs, Issued on 960918.Response Requested within 90 Days of Date of Ltr 1999-09-09
[Table view] |
Text
.-
PC
'Mr. Willi m T. Cottis' September 30,l1999 N
Pr:sident cnd Chi:f Ex:cutivs Officer STP Nuclear Operating Company South Texas Project Electric '
' Generating Station :
' P. O. Box 289 1Wadsworth, TX=77483
SUBJECT:
SOUTH TEXAS PROJECT, UNITS 1 AND 2 (STP)- REVISION TO TECHNICAL SPECIFICATION BASES PAGES B 3/4 8-14 THROl1GH B 3/4 8-17
. (TAC NOS. MA3880 AND MA3881)
Dear Mr. Cottle:
' We are responding to STP Nuclear Operating Company's October 12,1998, letter, as supplemented by letter dated December 9,-1998, which provided an update to Technical
_ Specification (TS) Bases pages B 3/4 8-14 through B 3/4 8-17. The change affects Bases section 3/4.8.2, *D.C. Sources," to provide additional information on surveillance requirements for the batteries.
1 The NRC staff has reviewed the change and finds that it is consistent with TS 3/4.8.2, "D.C.
Sources." In addition, the staff found a typographical error. On page B 3/4 8-15, there is a notation to Reference 9. However, there are no references in this section of the Bases.
Therefore, we have deleted the notation to Reference 9 in our copy of the Bases. This has been discussed with Ken Taplett of your staff and it was agreed to be acceptable.-
We are enclosing the revised TS Bases pages B 3/4 8-14 through B 3/4 8-17 that the NRC staff will use to update its copy of the STP Bases 6 Bases page B 3/4 8-13 is also enclosed. Page B 3/4 8-13 is an overleaf page and is prcvided to maintain document continuity. No changes were made to this page.
SIGNED BY Thomas W. Alexion, Project Manager, Section 1 Project Directorate IV & Decommissioning 9910070189 990930 PDR ADOCK 05000498 Division of Licensing Project Management P
PDR Office of Nuclear Reactor Regulation
. Docket Nos. 50-498 and 50-499 Bases pakes B 3/4 8-13 f h h t.
h
Enclosure:
I throug B 3/4 8-17 l
lcc w/ encl: See next page
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il South Texas, Units 1 & 2 I
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Mr. Cornelius F. O'Keefe Mr. J. J. Sheppard, Vice President Senior Resident inspector Engineering & Technical Services U.S. Nuclear Regulatory Commission STP Nuclear Operating Company P. O. Box 910 P. O. Box 289 Bay City, TX 77414 Wadsworth, TX 77483 A. Ramirez/C. M. Canady S. M. Head, Supervisor, Licensing City of Austin Quality & Licensing Department Electric Utility Departrnent STP Nuclear Operating Company 721 Barton Springs Road P. O. Box 289 i
' Austin, TX' 78704 Wadsworth, TX 77483 Mr. M. T. Hardt Office of the Governor Mr. W. C. Gunst -
ATTN: John Howard, Director t
City Public Service Board Environmental and Natural P. O. Box 1771 Resources Policy San Antonio, TX 78296 P. O. Box 12428 Austin, TX 78711 i
Mr. G. E. Vaughn'C. A. Johnson Central Power and Light Company Jon C. Wood l
P. O. Box 289 Matthews & Branscomb l
Mail Code: N5012 One Alamo Center l
Wadsworth,TX 74483 106 S. St. Mary's Street, Suite 700 San Ar.tonio, TX 78205-3692 INPO Records Center Arthur C. Tate, Director 700 Galleria Parkway Division of Compliance & Inspection j
Atlanta, GA 30339-3064 Bureau of Radiation Control Texas Department of Health Regional Administrator, Region IV 1100 West 49th Street U.S. Nuclear Regulatory Commission.
Austin, TX 78756 l
611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011 Jim Calloway Public Utility Commission of Texas D. G. Tees /R. L. Balcom Electric Industry Analysis
. Houston Lighting & Power Co.
P. O. Box 13326 P. O.. Box 1700 Austin, TX 78711-3326 Houston, TX 77251 Judge, Matagorda County Matagorda County Courthouse 1700 Seventh Street -
Bay City, TX 77414 Jack R. Newman, Esq.
Morgan, Lewis & Bockius
'1800 M Street, N.W.
Washington, DC 20036-5869 May 1999
ELECTRICAL POWER SYSTEMS BASES A.C. SOURCES. D.C. SOURCES. and ONSITE POWER DISTRIBUTION (Continued)
SR 4.8.1.1.2.e.11 As r quired by Regulatory Guide 1.108, paragraph 2.a.(2), each DG is required to demonstrate proper operation for the D8A loading sequence to ensure that voltage and frequency are maintained within the required limits. Under accident conditions, prior to connecting the DGs to their respective busses, all loads are shed except load center feeders and those motor control centers that power Class IE loads (referred to as " permanently connected" loads).
i Upon reaching 9M of rated voltage and frequency, the DGs are then connected
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to their respective busses.
Loads are tren sequentially connected to the bus by the automatic load sequencer. This sequencing logic controls the permissive and starting signals to motor breakers to prevent overloading of the DGs due to high motor starting j
currents. The IM load sequence time interval tolerance ensures that I
sufficient time exists for the DG to restore frequency and voltsge prior to applying the next load and that safety analysis assumptions regarding ESF i
equipment time delays are not violated.
The Frequency of 18 months is consistent with the reconnendation of Regulatory Guide 1.108, paragraph 2.a.(2), takes into consideration unit conditions required to perform the Surveillance, and is intended to be consistent with expected fuel cycle lengths.
SR 4.8.1.1.2.e.12 l
' This SR verifies that the diesel will not start when the emergency stop
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lockout feature is tripped. This prevents any further damage to the diesel engine or generator.
i SR a.8.1.1.2.e.13 l
This SR verifies the requirements of Branch Technical Position PSB-1 that the load shedding scheme automatically prevents load shedding during the sequencing of the emergency loads to the bus.
It also verifies the reinstatement of the load shedding feature upon completion of the load j
sequencing action.
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SR 4.8.1.1.2.f i
j This Surveillance demonstrates that the DG starting independence has not been compromised. Also, this Suvveillance demonstrates that each engine can achieve proper speed within the specified time when the DGs are started simultaneously.
SOUTH TEXAS - UNITS 1 & 2 B 3/4 8-13 Unit 1 - A,eendment No. 68 Unit 2 - Amendment No. 57
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ELECTRICAL POWER SYSTEMS B ASES A.C. SOURCES. D.C. SOURCES. and ONSITE POWER DISTRIBUTION (Continued)
The 10-year Frequency is consistent with the recommendations of Regulatory Guide 1.108, l
paragraph 2.b, and Regulatory Guide 1.137, paragraph C.2.f.
SR 4.8.1.1.2.c This SR provided assurance that any accumulation of sediment over time or the normal wear on the system has not degraded the diesels.
He OPERABILITY of the minimum specified A.C. and D.C. power sources and associated distribution systems during shutdown and refueling ensures that: (1) the facility can be -
maintained in the shutdown or refueling condition for extended time periods, and (2) sufficient instrumentation and control capability is available for monitoring and maintaining the unit status.
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ne alternate onsite emergency power source will be capable of being loaded with, but not limited to, one train of the following equipment: RHR, ECW, CCW, associated l
instrumentation, Control Room Makeup and Cleanup Filtration System and a 150-ton EAB 1
Chiller. This altemate onsite emergency power source will be capable of being started and loaded in sufficient time to prevent the reactor coolant temperature from exceeding design limits.
The Surveillance Requirements for demonstrating the OPERABILITY of the diesel generators are in accordance with the recommendations of Regulatory Guides 1.9, " Selection of Diesel Generator Set Capacity for Standby Power Supplies," Revision 2, December 1979; 1.108,
" Periodic Testing of Diesel Generator Units Used as Onsite Electric Power Systems at Nuclear Power Plants," Revision 1, August 1977; and ASTM D975-81, ASTM D1552-79, ASTM D262282, ASTM D4294-83, and ASTM D2276-78. The standby diesel generators auxiliary systems are designed to circulate warm oil and water through the diesel while the diesel is not running, to preclude cold ambient starts. For the purposes of surveillance testing, ambient conditions are considered to be the hot prelube condition.
In order to ensure the ability of the batteries to perform their intended functior., the batteries are normally maintained in a fully charged state and the environment in which the batteries are located is maintained within the parameters used to determine battery sizing and operation. Verifying average electrolyte temperature above the minimum for which the battery was sized, total battery terminal voltage on float charge, connection resistance values, and the performance of battery service and discharge tests ensures the effectiveness of the charging system, the ability to handle high discharge rates, and compares the battery capacity at that time with the rated capacity.
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l SOUTH TEXAS - UNITS 1 & 2 B 3/4 8-14 Unit 1 - Amendment No 68r 71 Unit 2 - Amendment No. 6h 60 1
REVISFD BY NRC LETIT.R DATED September 30, 1999
i ELECTRICAL POWER SYSTEMS BASES A.C. SOURCES. D.C. SOURCES. and ONSITE POWER DISTRIBUTION (Continued)
The Surveillance Requirements for demonstrating the OPERABILITY of the station batteries are cased on the recommendations of Regulatory Guide 1.129, " Maintenance Testing and Replacement of Large Lead Storage Batteries for Nuclear Power Plants," February 1978, and j
IEEE Std 450-1980, "lEEE Recommended Practice for Maintenance, Testing, and Replacement of Large Lead Storage Batteries for Generating Stations and Substations.
i The voltage requirements are based on the nominal design voltage of the battery and are consistent with the initialvoltages assumed in the battery sizing calculations. The seven-day Frequency is conservative with respect to manufacturer recommendations and IEEE-450.
SR 4.8.2.1.a I
This action is performed on a nommal seven-day cycle and documents inspection of the battery and battery room condition to the following attributes:
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- Charger output cunent and voltage, Pilot cell voltage, spectfic gravity nd temperature (values-recorded)
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Table 4.8-2 specifies the normallimits for each designated pilot cell and each connected cell for electrolyte level, float voltage, and specinc gravity. The limits for the designated pilot cells float 4'
voltage and specific gravity, greater than 2.13 volts and 0.015 below the manufacturer's full charge specific gravity or a battery charger current that had stabilized at a low value, are characteristic of a charged cell with adequate capacity. The seven-day frequency is conservative with respect to manufacturer, IEEE Std 450-1980 and regulatory guide recommendations.
SR 4.8.2.1.b This action is performed on a nommal 92-day cycle and documents measurement of the battery parameters to include the following attributes:
Voltage and specific gravity of each cell Electrolyte temperature of selected representative cells e
Connections are visually inspected and resistance measurement is performed only on a connection that appears to be loose or corroded Table 4.8-2 specifice the normal limits for each designated pilot cell and each connected cell for electrolyte level, float voltage, and specific gravity. The normallimits for each connected cell for float voltage and specific gravity, greater than 2.13 vohs and not more than 0.020 below the manufacturer's full charge specific gravity with an average specific gravity of all the connected cells not more than 0.010 below the manufacturer's full charge specific gravity, ensures the OPERABILITY and capability of the battery. The 92-day frequency is consistent with manufacturer and regulatory guide recommendations.
SOLTFH TEXAS - UNITS 1 & 2 B 3/4 8-15 Unit 1 - Amendment No. 68,-W76 Unit 2 - Amendment No. Mr60,65 REVISED DY NRC LFilTER DATED September 30, 1999
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FIFCTRICAL POWER SYSTEMS BASES' f
A.C. SOURCES. D.C. SOURCES. and ONSITE POWER DISTRIBUTION (Continued)
. Operation with a battery cell's parameter outside the normallimit but within the allowable value specified in Table 4.8-2 is permitted for up to seven days. During this seven-day period: (1) the allowable values for electrolyte level ensures no physical damage to the plates with an adequate electron transfer capability; (2) the allowable value for the average specific gravity of all the cells,' not more than 0.020 below the manufacturer's recommended full charge specific gravity, ensures that the decrease in rating will be less than the safety margin provided in sizing; (3) the j
allowable value for an individual cell's specific gravity, ensures that an individual cell's specific gravity will not be more than 0.040 below the manufacturer's full charge specific gravity and that the overall capability of the battery will be maintained within an acceptable limit; and (4) the
' allowable value for an individual cell's float voltage, greater than 2.07 volts, ensures the battery's capability to perform its design function.
SR 4.8.2.1.c.1. 2 & 3 This action is performed on an 18-month (maxunum) cycle and documents inspection of the battery to include the following attributes:
i Detailed visual inspection of each cell, including plate condition
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. Detailed visualinspection of battery rack Bolted connections cleaned, coated with anti-corrosion material and retorqued
'* Resistance of bolted connections measured and recorded Visual inspection and resistance measurements of inter-cell, inter-nck, inter-tier, and terminal connections provide an indication of physical damage or abnornd deterioration that could indicate degraded battery condition. The anticorrosion materialis used to help ensure good electrical connections and to reduce terminal deterioration. The visualinspection for corrosion is not intended to require removal of and inspection under each terminal connection. The removal of visible corrosion is a preventive maintenance SR. The presence of visible corrosion does not necessarily represent a failure of this SR provided visible corrosion is removed during performance of SR. The surveillance frequency of 18 months exceeds the IEEE-450 recommendation of 12 months, and is consistent with extension of the refuel cycle to 18 months.
SR 4.8.2.1.c.4 -
This action is performed on an 18-month (maximum) cycle and documents the capability of the battery charger to supply rated current at 125 V for a period of eight hours. The battery charger supply is required to be based on the largest combined demands of the various steady state loads and the charging capacity to restore the battery from the design mimmum charge state to the fully charged state, irrespective of the status of the unit during these demand occurrences.
The mimmum required amperes and duration ensures that these requirements can be satisfied.
The surveillance frequencyis acceptable, and is intended to be consistent with the expected fuel cycle lengths.
SOUTH TEXAS - UNITS 1 & 2 B 3/4 8-16 Unit 1 REVISED BY NRC LETTER Unit 2 DATED September 30, 1999
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l ELECTRICAL POWER SYSTEMS l
BASES l
AC. SOURCES. D.C. SOURCES. and ONSITE POV/ER DISTRIBUTION (Continued)
SR 4.8.2.1.d i
A battery service test is a special test of battery capability, as found, to satisfy the design requirements (battery duty cycle) of the DC electrical power system. The discnarge rate and test length should correspond to the design duty cycle requirements. The surveillance frequency of 18 months is consistent with the recommendations of Regulatory Guide 1.129, which state that the battery service test should be performed during refueling operations, or at some other outage, with intervals between tests not to exceed 18 months.
SR 4.8.2.I.e A battery performance discharge test is a test of constant current capacity of a battery, normally done in the "as found" condition, after having been in service, to detect any change in the capacity determmed by the acceptance test. This test is intended to determine overall battery degradation due to age and usage. A performance discharge test is allowed in lieu of a service test once per 60 months.
SR 4.8.2.1.f The performance discharge test surveillance frequency for this test is normally 60 mondis.
If the battery has reached 85% ofits expected life, or if the battery capacity has decreased by 10 percent or more of the manufacturer's rating, the surveillance frequency is reduced to 18 months because the test must be performed during the refueling operations. The 18 month interval exceeds the IEEE-450 recommendation.
3/4.8.4 (Not Used) i SOUTH TEXAS - UNITS 1 & 2 B 3/4 8-17 Unit 1 REVISED BY NRC LETTER Unit 2 DATED September 30, 1999