|
---|
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:INCOMING CORRESPONDENCE
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) 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 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-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) 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 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 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 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 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 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) 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) 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 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 05000498/LER-1999-006, Forwards LER 99-006-00 Re Automatic Reactor Trip Due to over-temp delta-temp Actuation.Licensee Commitments Are Listed in Corrective Actions Section of LER1999-07-26026 July 1999 Forwards LER 99-006-00 Re Automatic Reactor Trip Due to over-temp delta-temp Actuation.Licensee Commitments Are Listed in Corrective Actions Section of LER 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 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 NOC-AE-000597, Forwards voltage-based Criteria 90-day Rept for SG Tube Exam Performed Under NRC GL 95-05 During Refueling Outage 1RE08. Rept Contains Info Required by Section 6.b of Attachment 2 to GL 95-051999-07-23023 July 1999 Forwards voltage-based Criteria 90-day Rept for SG Tube Exam Performed Under NRC GL 95-05 During Refueling Outage 1RE08. Rept Contains Info Required by Section 6.b of Attachment 2 to GL 95-05 NOC-AE-000598, Forwards Four Copies of 1RE08 Refueling Outage ISI Summary Rept for Steam Generator Tubing1999-07-23023 July 1999 Forwards Four Copies of 1RE08 Refueling Outage ISI Summary Rept for Steam Generator Tubing NOC-AE-00586, Forwards Results of Control Rod Testing,In Response to NRC Bulletin 96-01, Control Rod Insertion Problems, Dtd 960308.Core Map Provided to Assist in Understanding Test Data1999-07-21021 July 1999 Forwards Results of Control Rod Testing,In Response to NRC Bulletin 96-01, Control Rod Insertion Problems, Dtd 960308.Core Map Provided to Assist in Understanding Test Data NOC-AE-000595, Forwards Chapters 1.0 & 16.0 to Operations QA Plan for South Texas Project.Rev Is Strictly Administrative & All Content Was Previously Submitted to NRC on 990503 & 9906151999-07-21021 July 1999 Forwards Chapters 1.0 & 16.0 to Operations QA Plan for South Texas Project.Rev Is Strictly Administrative & All Content Was Previously Submitted to NRC on 990503 & 990615 NOC-AE-000518, Requests Exemption from Various Special Treatment Requirements of 10CFR50,as Described in Encls to Ltr.Stp Believes That Pilot Application Will Assist NRC in Development & Implementation of risk-informed 10CFR501999-07-13013 July 1999 Requests Exemption from Various Special Treatment Requirements of 10CFR50,as Described in Encls to Ltr.Stp Believes That Pilot Application Will Assist NRC in Development & Implementation of risk-informed 10CFR50 NOC-AE-000536, Submits Request for Exemption from Requirements of 10CFR50.34(b)(11),10CFR50,App A,Gdc 2 & 10CFR100,App a, Section VI(a)(3) Re Maint of Seismic Instrumentation.Revised Page to Procedure OERP01-ZV-IN01 Included1999-07-13013 July 1999 Submits Request for Exemption from Requirements of 10CFR50.34(b)(11),10CFR50,App A,Gdc 2 & 10CFR100,App a, Section VI(a)(3) Re Maint of Seismic Instrumentation.Revised Page to Procedure OERP01-ZV-IN01 Included NOC-AE-000580, Forwards Response to NRC 990415 RAI Re Implementation of Commitments Related to GL 89-10, Safety-Related MOV Testing & Surveillance & GL 96-05, Periodic Verification of Design Basis Capability of Safety-Related Movs1999-07-13013 July 1999 Forwards Response to NRC 990415 RAI Re Implementation of Commitments Related to GL 89-10, Safety-Related MOV Testing & Surveillance & GL 96-05, Periodic Verification of Design Basis Capability of Safety-Related Movs NOC-AE-000574, Forwards ISI Summary Repts for Repairs & Replacements & for Sys Pressure Tests Performed Between 971004 & Completion of Eighth RO on 9904281999-07-0606 July 1999 Forwards ISI Summary Repts for Repairs & Replacements & for Sys Pressure Tests Performed Between 971004 & Completion of Eighth RO on 990428 NOC-AE-000557, Requests Relief from ASME Section XI Code Nondestructive Exam Requirements of App III,III-3410 for Second ISI Interval.Proposed Alternatives for Ultrasonic Exam of Piping Sys Welds,Attached1999-07-0606 July 1999 Requests Relief from ASME Section XI Code Nondestructive Exam Requirements of App III,III-3410 for Second ISI Interval.Proposed Alternatives for Ultrasonic Exam of Piping Sys Welds,Attached NOC-AE-000498, Requests Relief from ASME Section XI Code Nondestructive Exam Requirements Applicable to SG Main Steam Nozzle inside- Radius Sections.Attachment Includes Discussion of Basis & Justification for Request & Implementation Schedule1999-07-0606 July 1999 Requests Relief from ASME Section XI Code Nondestructive Exam Requirements Applicable to SG Main Steam Nozzle inside- Radius Sections.Attachment Includes Discussion of Basis & Justification for Request & Implementation Schedule NOC-AE-000573, Requests Relief from Requirements of ASME Section XI Code Case N-498,exempting Isolated Class 1 Reactor Vessel Head Vent Atmospheric Vent Piping & Valve from Being Tested at Full RCS Pressure1999-07-0606 July 1999 Requests Relief from Requirements of ASME Section XI Code Case N-498,exempting Isolated Class 1 Reactor Vessel Head Vent Atmospheric Vent Piping & Valve from Being Tested at Full RCS Pressure NOC-AE-000541, Submits Response to GL 98-01,Suppl 1, Y2K Readiness of Computer Systems at Npps. Readiness Disclosure for STP, Encl1999-06-29029 June 1999 Submits Response to GL 98-01,Suppl 1, Y2K Readiness of Computer Systems at Npps. Readiness Disclosure for STP, Encl NOC-AE-000571, Forwards Final Operating Exam Matls for STP Exam Scheduled for 990705.Revised Operating Exam Outline & post-validation Change Summary Has Been Included.Without Encls1999-06-24024 June 1999 Forwards Final Operating Exam Matls for STP Exam Scheduled for 990705.Revised Operating Exam Outline & post-validation Change Summary Has Been Included.Without Encls NOC-AE-000512, Responds to NRC 981201 Telcon Re Jco 93-0004,per Revised MSLB Analysis1999-06-23023 June 1999 Responds to NRC 981201 Telcon Re Jco 93-0004,per Revised MSLB Analysis NOC-AE-000560, Forwards LER 99-S02-00,re Failure to Maintain Positive Control of Vital Area Security Key.Licensee Commitments Are Found in Corrective Action Section of LER1999-06-23023 June 1999 Forwards LER 99-S02-00,re Failure to Maintain Positive Control of Vital Area Security Key.Licensee Commitments Are Found in Corrective Action Section of LER 05000498/LER-1999-005, Forwards LER 99-005-00,re Failure to Meet Requirements of TS Surveillance 3.7.1.2 Action B for Auxiliary FW Sys.Only Commitments Contained in Ltr Are Located in Corrective Action Section of LER1999-06-17017 June 1999 Forwards LER 99-005-00,re Failure to Meet Requirements of TS Surveillance 3.7.1.2 Action B for Auxiliary FW Sys.Only Commitments Contained in Ltr Are Located in Corrective Action Section of LER NOC-AE-000565, Forwards Amended Pages for Insertion Into South Texas Project Nuclear Operating Co Previously Submitted Response to NRC Rai.New Pages Include Expanded Answer to Question 4.b1999-06-16016 June 1999 Forwards Amended Pages for Insertion Into South Texas Project Nuclear Operating Co Previously Submitted Response to NRC Rai.New Pages Include Expanded Answer to Question 4.b NOC-AE-000548, Forwards Response to RAI Re Proposed Amends on Replacement SG Water Level Trip Setpoint Differences for Stp,Units 1 & 2.Nothing Contained in Response Should Be Considered Commitment Unless So Specified in Separate Correspondence1999-06-16016 June 1999 Forwards Response to RAI Re Proposed Amends on Replacement SG Water Level Trip Setpoint Differences for Stp,Units 1 & 2.Nothing Contained in Response Should Be Considered Commitment Unless So Specified in Separate Correspondence NOC-AE-000561, Forwards Change QA-042 to Operations QAP, Rev 13, Reflecting Current Organizational Alignment for STP & Culminating Organizational Realigment That Has Been Taking Place During Past Several Months1999-06-15015 June 1999 Forwards Change QA-042 to Operations QAP, Rev 13, Reflecting Current Organizational Alignment for STP & Culminating Organizational Realigment That Has Been Taking Place During Past Several Months NOC-AE-0559, Forwards STP Commitment Change Summary Rept for Period 981209-990610.Rept Lists Each Commitment for Which Change Was Made During Reporting Period & Provides Basis for Each Change1999-06-15015 June 1999 Forwards STP Commitment Change Summary Rept for Period 981209-990610.Rept Lists Each Commitment for Which Change Was Made During Reporting Period & Provides Basis for Each Change NOC-AE-000499, Forwards Relief Request RR-ENG-2-3,proposing to Perform Alternative Ultrasonic Examination from Outside Surface of Skirt Attachment Weld as Described in Encl,In Lieu of Surface Examination from Inside Pressurizer Skirt1999-06-0909 June 1999 Forwards Relief Request RR-ENG-2-3,proposing to Perform Alternative Ultrasonic Examination from Outside Surface of Skirt Attachment Weld as Described in Encl,In Lieu of Surface Examination from Inside Pressurizer Skirt NOC-AE-000502, Forwards Relief Request RR-ENG-2-6,proposing That Boroscopic VT-1 Visual Examination Be Allowed as Alternative to Section XI Surface Examination of Pump Casing Welds,Or Portions of Welds within Pits1999-06-0909 June 1999 Forwards Relief Request RR-ENG-2-6,proposing That Boroscopic VT-1 Visual Examination Be Allowed as Alternative to Section XI Surface Examination of Pump Casing Welds,Or Portions of Welds within Pits NOC-AE-000500, Forwards Relief Request RR-ENG-2-4,proposing to Perform Alternative Ultrasonic Examination from Outside & End Surfaces of Reactor Vessel Closure Head Nuts,As Described in Encl in Lieu of Surface Examination of Threaded Region1999-06-0909 June 1999 Forwards Relief Request RR-ENG-2-4,proposing to Perform Alternative Ultrasonic Examination from Outside & End Surfaces of Reactor Vessel Closure Head Nuts,As Described in Encl in Lieu of Surface Examination of Threaded Region NOC-AE-000545, Forwards Response to NRC 990416 RAI Re Util Proposed Amend on Operator Action for Small Break Loca, .Draft EOP Re Small Break Loca,Encl to Aid Discussion of Proposed Amend1999-05-31031 May 1999 Forwards Response to NRC 990416 RAI Re Util Proposed Amend on Operator Action for Small Break Loca, .Draft EOP Re Small Break Loca,Encl to Aid Discussion of Proposed Amend 1999-09-09
[Table view] Category:UTILITY TO NRC
MONTHYEARST-HL-AE-3578, Forwards 1RE02 Inservice Insp Summary Rept for Welds & Component Supports..., Describing Exams Performed During Period of 900329-0621,per 1983 Edition of ASME Code,Section XI & Summer 1983 Addenda1990-09-20020 September 1990 Forwards 1RE02 Inservice Insp Summary Rept for Welds & Component Supports..., Describing Exams Performed During Period of 900329-0621,per 1983 Edition of ASME Code,Section XI & Summer 1983 Addenda ST-HL-AE-3577, Responds to Generic Ltr 90-07, Operator Licensing Natl Exam Schedule1990-09-18018 September 1990 Responds to Generic Ltr 90-07, Operator Licensing Natl Exam Schedule ST-HL-AE-3567, Requests NRC Review of Proposed Rev to Schedule for Inservice Insp Exam of Class 1,Category B-D Vessel Nozzles1990-09-14014 September 1990 Requests NRC Review of Proposed Rev to Schedule for Inservice Insp Exam of Class 1,Category B-D Vessel Nozzles ST-HL-AE-3570, Forwards Rev 5 to, South Texas Project Unit 1 Pump & Valve Inservice Test Plan1990-09-14014 September 1990 Forwards Rev 5 to, South Texas Project Unit 1 Pump & Valve Inservice Test Plan ST-HL-AE-3553, Forwards WCAP-12629, Analysis of Capsule U from South Texas Unit 1 Reactor Vessel Radiation Surveillance Program. Pressure-temp Curves Currently in Use in Facility Tech Specs Are More Conservative than Presented in App a of Rept1990-09-10010 September 1990 Forwards WCAP-12629, Analysis of Capsule U from South Texas Unit 1 Reactor Vessel Radiation Surveillance Program. Pressure-temp Curves Currently in Use in Facility Tech Specs Are More Conservative than Presented in App a of Rept ST-HL-AE-3565, Forwards Rev 8 to Operations QA Plan. Plan Revised in Order to Include More Detailed Criteria of Chapter 17.2 of Updated Fsar.Approval Requested1990-09-10010 September 1990 Forwards Rev 8 to Operations QA Plan. Plan Revised in Order to Include More Detailed Criteria of Chapter 17.2 of Updated Fsar.Approval Requested ST-HL-AE-3546, Forwards Corrected Semiannual Radioactive Effluent Release Rept for Second Half of 19891990-08-28028 August 1990 Forwards Corrected Semiannual Radioactive Effluent Release Rept for Second Half of 1989 ST-HL-AE-3550, Forwards Semiannual fitness-for-duty Program Performance Rept for Jan-June 1990,per 10CFR26.71(d)1990-08-28028 August 1990 Forwards Semiannual fitness-for-duty Program Performance Rept for Jan-June 1990,per 10CFR26.71(d) ST-HL-AE-3540, Provides Schedule Under Which Facility Turbine Components Inspected for Functional Integrity.Required Insp Intervals Calculated to Maintain Probability of Missile Generation for Each Low Pressure Rotor1990-08-28028 August 1990 Provides Schedule Under Which Facility Turbine Components Inspected for Functional Integrity.Required Insp Intervals Calculated to Maintain Probability of Missile Generation for Each Low Pressure Rotor ST-HL-AE-3551, Forwards Responses to NRC 900807 Request for Addl Info Re Probabilistic Safety Assessment Human Reliability Analysis. Paper on Quantification of Human Error Rates Using slim-based Approach Encl1990-08-26026 August 1990 Forwards Responses to NRC 900807 Request for Addl Info Re Probabilistic Safety Assessment Human Reliability Analysis. Paper on Quantification of Human Error Rates Using slim-based Approach Encl ML20043H6191990-06-21021 June 1990 Forwards 1989 Annual Financial Repts for Licensees for Plant ML20043H5971990-06-19019 June 1990 Forwards Responses to Open Items Resulting from Sandia Draft Rept on Probabilistic Safety Assessment.Dominant Sequence Model Encl,Per NRC Reviewers Request ML20043H7781990-06-18018 June 1990 Forwards Rev 1 to SER Commitment Status for Plant,Per NUREG-0781.List of Action Items Completed But Not Incorporated Into Sser & List of Items for Actions Not Completed Also Encl ML20043F6261990-06-11011 June 1990 Forwards Rev 0 to Unit 1 Cycle 3 Core Operating Limits Rept. ML20043F3191990-06-0404 June 1990 Responds to NRC 900504 Ltr Re Violations Noted in Insp Repts 50-498/90-01 & 50-499/90-01.Corrective Actions:Compressed Gas Cylinders Removed from Power Block & Nashua 357 Tape Returned to Nuclear Purchasing Matl Mgt Co ML20043D3241990-06-0101 June 1990 Forwards Rev 10 to Safeguards Contingency Plan.Rev Withheld (Ref 10CFR73.21) ML20043B1651990-05-21021 May 1990 Advises That Qualified Display Processing Sys on Line Parameter Update Mod Will Be Completed During Next Refueling Outages,Per 900312 Ltr ML20043A9951990-05-16016 May 1990 Discusses Actions Taken Re Prompt Notification Sys.Util Found Autodialer Sys Offer Acceptable Alternative to Replacing Majority of Tone Alert Radios ML20043H6531990-05-16016 May 1990 Forwards Plant Owner Draft Decommissioning Certificate & Util & City Public Svc Board of San Antonio Decommissioning Master Trust Agreements for South Texas Project ML20043A6081990-05-16016 May 1990 Forwards Rev 16 to Physical Security Plan.Rev Withheld (Ref 10CFR73.21) ML20043A8641990-05-14014 May 1990 Clarifies Operation of Telephone Autodialer Sys,As Part of Prompt Notification Sys.Autodialer Sys,As Currently Configured,Can Autodial & Deliver Prerecorded Message to Residents at Rate of Approx 20 Calls Per Minute ML20043A3271990-05-10010 May 1990 Forwards Endorsements 7 & 6 to Maelu Certificates M-113 & M-116,respectively & Endorsement 6 to Nelia Certificates N-113 & N-116 ML20042G8641990-05-0909 May 1990 Comments on SALP Repts 50-498/90-06 & 50-499/90-06 for Jan 1989 to Jan 1990.Util Working on Areas Identified During SALP Rept & Mgt Meeting on 900425 ML20042F9571990-05-0707 May 1990 Responds to NRC 900405 Ltr Re Violations Noted in Insp Repts 50-498/90-05 & 50-499/90-05.Corrective Actions:Surveillances of Emergency Response Equipment in Technical Support Ctrs Performed to Ensure That Emergency Requirements Satisfied ML20042F1171990-05-0101 May 1990 Submits Special Rept Re Evaluation of third-yr Containment Tendon Surveillance.Tendons Which Had Voids Have Been Filled & No Evidence of Grease Leakage from Sheathing Exists ML20042F3631990-04-30030 April 1990 Provides Summary of Expected Sequence of Events for Updates to Prompt Notification Sys ML20042E6361990-04-20020 April 1990 Forwards Revised Organization Chart,Correcting Postion Titles Reflected in 900326 Submittal ML20042E5421990-04-12012 April 1990 Responds to 900316 Notice of Violation for Insp Repts 50-498/90-08 & 50-499/90-08.Violation Addressed in LER 90-003 Re Failure to Perform Tech Spec Required Surveillance Due to Deficient Procedure ML20042E1591990-04-0505 April 1990 Provides Listed Guidelines for Development of Operating Procedures Re Ac Power Restoration to Respond to Station Blackout Event,Per 10CFR50.63, Loss of All AC Power. ML20012F2881990-04-0202 April 1990 Provides Rept of Nuclear Insurance Protection,Per 10CFR50.54(w)(2).NEIL-II Decontamination Liability & Excess Property Policy Increased Effective 891115 ML20012F2831990-04-0202 April 1990 Informs of Deferral of Facility Mods to Install Permanent RHR Pump Motor Current Indication.Mod Will Be Completed Before Next Reduced RCS Inventory Conditions on Unit ML20012D8731990-03-19019 March 1990 Forwards Revised Correspondence Distribution List of Designated Recipients ML20012C6121990-03-16016 March 1990 Forwards NRC Regulatory Impact Survey Questionnaire Sheets in Response to Generic Ltr 90-01, Request for Voluntary Participation in NRC Regulatory Impact Survey. Brief Summary Table of Questionnaire Data Also Encl ML20012C6171990-03-16016 March 1990 Forwards Status of Actions Committed to Re NRC Bulletin 88-004 in Response to G Dick Request ML20012C2811990-03-12012 March 1990 Forwards Suppl 3 to Qualified Display Processing Sys (Qdps) Verification & Validation Process Final Rept & Summary of Qualified Display Processing Sys (Qdps) Recurring Component Failure Data. ML20012C0641990-03-12012 March 1990 Forwards Rev 15 to Physical Security Plan.Rev Withheld (Ref 10CFR73.21) ML20012B7651990-03-0909 March 1990 Responds to Generic Ltr 88-17, Loss of Dhr. Util Will Revise Appropriate Procedures to Require Entering Reduced Inventory Operation at 3 Ft Below Reactor Vessel Flange ML20042D6701990-03-0808 March 1990 Responds to NRC Generic Ltr 89-19, Resolution of USI A-47,Safety Implication of Control Sys in LWR Nuclear Power Plants. Plant Design Meets Criteria of Generic Ltr 89-19 for Automatic Steam Generator Overfill Protection ML20012A1291990-03-0101 March 1990 Forwards Responses to Questions Raised by Sandia During Review of Plant PRA Covering Steam Generator Dryout ML20012A3001990-02-28028 February 1990 Forwards Nonproprietary & Proprietary Rev 1,Suppl 2 to WCAP-12087 & WCAP-12067, Reconciliation of Fatigue Crack Growth Results for South Texas Project Unit 1 Surge..., Per NRC Bulletin 88-011.WCAP-12067 Withheld (Ref 10CFR2.790) ML20011F1921990-02-22022 February 1990 Responds to NRC 900123 Ltr Re Violations Noted in Insp Repts 50-498/89-47 & 50-499/89-47.Corrective Actions:Heat Trace Circuit Temp Controllers Calibr & Analog Indication Checked & Found within Tolerance on All But Three Channels ML20011E9061990-02-16016 February 1990 Responds to NRC IE Bulletin 89-003, Potential Loss of Required Shutdown Margin During Refueling Operations. Util Concluded That Sufficient Precautions Will Be in Place to Ensure Against Loss of Required Shutdown Margin ML20006D9121990-02-0707 February 1990 Forwards Updated Schedule of Responses to NRC Generic Ltrs 83-28,88-17,88-20,89-05,89-06,89-07,89-08,89-10,89-12,89-13, 89-17,89-19 & 89-21 & Bulletins 88-001,88-008,88-010,88-011, 89-001,89-002,89-003,88-008,Suppl 1 & 88-010,Suppl 1 ML20011E8251990-02-0505 February 1990 Requests Consideration of Scenario Manual for 900404 Graded Emergency Preparedness Exercise as Proprietary Info Until After Graded Exercise ML20006B8801990-01-31031 January 1990 Forwards Comparison of Instrusion Detection Sys Proposed for Various Physical Security Upgrade.Encl Withheld (10CFR73.21) ML20011E1831990-01-30030 January 1990 Requests Approval of Schedular Exemption from 10CFR50,App J, Type C Local Leak Rate Testing Requirements by 900301,based on Interval Between Completion of Unit 1 First Refueling Outage & Second Refueling Outage Start of Only 6 Months ML20011E1361990-01-29029 January 1990 Responds to Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment. Three Bays of Essential Cooling Water Intake Structure Will Be Inspected Once Every 18 Months for Macroscopic Biological Fouling Organisms ML20006A9791990-01-26026 January 1990 Provides Addl Info Re Surge Line Stratification at Facility, Per NRC Bulletin 88-011.W/exception of One Heatup Cycle, Stratification Observed in Surge Line Determined to Be within Bounds of WCAP-12067,Rev 1 ML20006A7981990-01-26026 January 1990 Forwards Response to Violations Noted in Insp Repts 50-498/89-39 & 50-499/89-39.Response Withheld ML20006B3551990-01-23023 January 1990 Forwards Rev 4 to Pump & Valve Inservice Test Plan. Rev Includes Addition of Component Cooling Water Valves FV-0864,FV-0862 & FV-0863 & Containment Sys Valves FV-1025, FV-1026,FV-1027 & FV-1028 1990-09-20
[Table view] |
Text
n -
a h
The Light company P.O.11ox 1700 llouston, Texa 77001 (713) 228 9211 llouston Lighting & Power April 8, 1988 ST-HL-AE-2608 File No.i G2.4 10CFR2.201 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 South Texas Project Electric Generating Station Unit 1 Docket No. STN 50-498 Response to Violations 8809-04 through 8809-06 Houston Lighting & Power Company has reviewed the Notices of Violation included in Inspection Report 88-09 and submits the attached responses pursuant to 10CFR2.201.
The response provided to Notice of Violation 8809-04 was previously submitted to the NRC by Licensee Event Reports88-010, 88-011,88-012, and 88-013. The response provided to Notice of Violation 8809-05 was previously submitted by Licensee Event Report 88-015.
If you should have any questions, please contact Mr. M. A. McBurnett at (512) 972-8530.
bibs M g /
G. E. Vaughn Vice President Nuclear Plant Operations GEV/RAF/ae
Attachment:
Responses to Notices of Violation 8804150360 000400 PDR ADOCK 05000498 \
G PDR O h
\ \
NL.88.085.P2
1 1
llouston Lighting & Power Company ST-HL-AE-2608 File No.: G2.4 ,
Page 2 '
CCt Regional Administrator, Region IV Rufus S. Scott Nuclear Regulatory Commission Associate General Counsel 611 Ryan Plaza Drive, Suite 1000 Houston Lighting &' Power Company Arlington, TX 76011 P. O. Box 1700 Houston, TX 77001 N. Prasad Kadambi~, Project Manager U. S. Nuclear Regulatory Commission Dr. Joseph H. Hendrie 1 White Flint North 50 Be11 port Lane 11555 Rockville Pike Be11 port, NY 11713 Rockville, MD 20859 Dan R. Carpenter Senior Resident Inspector / Operations c/o U. S. Nuclear Regulatory Commission P. O. Box 910 Bay City TX 77414 Don L. Garrison Resident Inspector / Construction c/o U. S. Nuclear Regulatory Commission P. O. Box 910 Bay City TX 77414 J. R. Newman, Esquire Newman & Holtzinger, P.C.
1615 L Street, N.W.
Washington, DC 20036 i
i R. L. Range /R. P. Verret
- Central Power & Light Company j P. O. Box 2121 Corpus Christi, TX 78403 R. John Miner (2 copies)
! Chief Operating Officer l City of Austin Electric Utility 721 Barton Springs Road Austin, TX 78704 R. J. Costello/M. T. Hardt City Public Service Board P. O. Box 1771 San Antonio, TX 78296 i
Revised 03/18/88 NL. DISTR.1
Attachment ST-HL-AE-2608 Page 1 of 10 South Texas Project Electric Generating Station :
Unit 1 !
Docket No. STN 50-498 Response to Notice of Violation 8809-04 t I. Statement of Violation Implementation of Technical Specification Surveillance Requirements Technical Specification 4.0 states, in part, that surveillance !
requirements shall be met during the operational modes or other 2 conditions specified for individual limiting conditions for operation. l and that there are surveillance requirements applicable for inservice inspection and testing of ASME Code Class 1, 2, and 3 components.
Contrary to the above, the licensee identified four more cases where technical specification surveillance requirements were not met in spite of efforts to prevent recurrences of similar incidents identified prior to this inspection period in Licensee Event Reports87-009, 87-019,87-026, and 88-006. On January 26, 1988, the licensee discovered that k
no periodic surveillance tests had been implemented for the charging header pressure transmitter CV-PT-204, thus rendering the containment isolation capability associated with the charging header inoperable. On January 27, 1988, the licensee discovered that the 11B Essential Chilled i Water Pump inservice test was not accomplished within the required ,
frequency. On January 29, 1988, the licensee discovered that the STP ;
Unit 1 Pump and Valve Inservice Test Plan, Revision 2, f ailed to list -
the required stroke time limits for Valve CV-FCV-0205. On February 4, i 1988, the lic.nsee discovered that the time delay relays in all of the feedwater isolation / turbine trip logic channels had never been ;
j surveillance tested. j 4 <
II. Houston Lighting and Power Position Houston Lighting and Power does not contest the violation. ,
III. Reason for Violation e
A. No Periodic Surveillance Test for CV-PT-204 i A surveillance procedure was not developed for this instrument because it was not addressed in the STP Technical Specifications.
This occurred because the STP Technical Specifications were developed using the Standard Technical Specifications for ,
Westinghouse plants which do not use this particular instrument loop and was inadvertently overlooked during subsequent reviews for STP unique functions.
i I
This event was reported to the NRC by Licensee Event Report 88-010
. dated February 25, 1988 based upon the instrument loop being 1
. inoperable because pressure transmitter PT-204 could not be ,
calibrated and that this condition was not recognized by the Shift 2 >
i NL.88.085.P2 i
l Attachment :
ST-HL-AE-2608 Page 2 of 10 Supervisor during his review of the Maintenance Work Request I resulting in required actions not being taken. j The program for generation and approval of Maintenance Work Requests was not effective in that sufficient guidance for making decisions ,
relative to equipment operability was not provided to the shift supervisor.
- 3. Missed Surveillance Test on 11B Essential Chill Water Pump The cause of the event was determined to be inadequate control of the surveillance test package. After the surveillance test package was prepared by the Surveillance Program Scheduler, it was lost during the routing of the package to the main control room. A l l contributing f actor to the event was that the missed surveillance test did not appear on the Overdue Report. The method used by the l Surveillance Coordinator to change the test f requency was flawed.
The method for performing this action was not documented in the ;
Surveillance Scheduling Procedure.
Another contributing factor to the event was the mode change report
, used to support the January 25, 1988 mode change showed the wrong l due date for this surveillance requirement. The surveillance ;
coordinator had changed the due date without realizing that the past [
due date was in fact valid. The method for controlling the changing ;
of due dates was not documented in the Surveillance Scheduling Procedure. .
l' This event was reported to the NRC by Licensee Event Report 88-011, dated February 26, 1988. ;
) C. Missing Stroke Time in Pump and Valve Inservice Test Plan i
The cause of this occurrence was the failure to incorporate revisions to the Pump and Valve Inservice Test (IST) Plan into implementing procedures. This occurred because there was no ,
administrative requirement in procedure OPGP03-ZE-0021, Inservice i Testing Program for Valves, to review implementing procedures when
- the IST Plan is revised. Procedure 1 PSP 03-CV-0011 was not verified to be compatible with revision 1 of the IST Plan when it was issued.
l This event was reported to the NRC by Licensee Event Report 088-012,
- dated February 29, 1988.
i I
D. No Periodic Surveillance Testing of Feedwater Isolation / Turbine Trip Logic Channel Time Delay Relays .
I l
The cause of this event was personnel error because during the preparation and subsequent review of the affected surveillance I procedures the procedure writers and reviewers believed that the ,
testing procedure described in the vendor technical manual would e i include the testing of the low flow time delay relays. This l
I NL.88.085.P2
Attachment ST-HL-AE-2608 Page 3 of 10 assumption was made based upon the following statement made in the Periodic Testing section of the vendor manual concerning the low flow test: "The following is a self sufficient test procedure for an individual logic train." If further research had been conducted it would have revealed that the low flow time delay relays were not addressed.
This event was reported to the NRC by Licensee Event Report 88-013, dated March 4, 1988.
IV. Corrective actions that have been taken Item A - An evaluation of the Maintenance Work Request generation and approval process has been performed. Recommendations resulting from this evaluation are under consideration for incorporation into Station procedures.
Item B - Other cases where the testing frequency was changed based on the tests last performance were verified to have been performed successfully or correctly scheduled. No other problems were found.
On November 23, 1987, Procedure OPGP03-ZE-0004 which describes the Plant Surveillance Program was revised to create the position of divisional Surveillance Coordinators and to give them the responsibility for following surveillance test packages assigned to their divisions. If these controls would have been in place at the time of the November 6, 1987 test, it would have prevented the missed surveillance.
The methodology for changing the test frequency based upon the performance of a previous surveillance as well as the method for approving changes to surveillance due dates have been added to procedure OPGP03-ZA-0055.
Item C - A temporary procedure, 1 TSP 03-CV-0001, correcting the deficient condition was generated and performed satisfactorily, allowing the valve to be declared operable.
The review of revision 2 of the IST Plan was completed no other discrepancies were identified.
Two independent reviews of other pump and valve inservice surveillance tests were performed to ensure agreement of the implementing procedures with the IST Plan. No other discrepancies were identified.
The stroke time limiting value for CV-FCV-0205 was incorporated into revision 3 of the IST Plan which was submitted to NRC on February 5, 1988.
NL.88.085.P2
Attachment ST-HL-AE-2608 Page 4 of 10 An independent review of revision 3 of the IST Plan was performed prior to its submittal to the NRC.
IPSP03-CV-0011, Chemical and Volume Control System Operability Text (Cold Shutdown), has been revised to include provisions for obtaining the open stroke time for CV-FCV-0205.
Item D - Surveillance test procedures were revised, reviewed and approved to test the SSPS actuation train low flow time delay relays.
Other surveillance procedures have been reviewed for similar omissions of testing requirements.
STPEGS procedure OPGP03-ZA-0002, "Plant Procedures," has been revised to require a second, independent, technical review of procedures when written or reviced to ensure accuracy and adequacy.
V. Corrective Actions that will be taken Item A - Program enhancements, recommended by the program evaluation, including more detailed guidance to operating personnel relative to determination of equipment operability will be implemented by April 15, 1988.
A proposed Technical Specification amendment is being developed to add the low charging header pressure instrument loop operability for Limiting Condition for Operation and Surveillance Requirements. This proposed amendment was scheduled for submission to the NRC by April 4, 1988, however because of external influences it is now anticipated that it will be transmitted by May 30, 1988.
A surveillance procedure is being developed to test this actuation function consistent with other Engineered Safety Features (EST) functions and to meet the proposed Technical Specification requirements. It is anticipated that this change can be made by May 15, 1988. The surveillance f requency is
- once per 18 months or each refueling.
Item B - Procedure OPGP03-ZE-0004, Plant Surveillance Program, will be further enhanced to require that the divisional Surveillance Coordinators periodically review upcoming tests and ensure that test packages are received by the start date. Thit action will be complete by April 12, 1988.
Item C - OPGP03-ZE-0021. Inservice Testing Program for Valves, will be revised by June 1, 1988 to include controls to review l
implementing procedures when new revisions to the STPEGS Pump l
and Valve Inservice Test (IST) Plan are issued. No new revisions are expected to the IST program before revision to l
this procedure is made.
1 NL.88.085.P2
[
6 Attachment ST-HL-AE-2608 Page 5 of 10 Item D - The STPEGS procedure OPGP03-ZE-0005, "Plant Surveillance Procedure Preparation," will be revised to require che writer to ensure that available information used to document the entire circuit is reviewed to ensure that the circuit being tested by the procedure is physically the circuit req' aired to be tested by the surveillance requirements. This revision will be completed by April 15, 1988.
HL&P believes the added requirement of second independent technical reviews of surveillance procedures and the addition of divisional surveillance coordinators will greatly enhance the effectiveness of the surveillance program.
VI. Full Compliance.
The plant is in full compliance.
NL.88.085.P2
Attachment ST-HL-AE-2608 Page 6 of 10 South Texas Project Electric Generating Station Unit 1 Docket No. STN 50-498 Response to Notice of Violation 8809-05 I. Statement of Violation 8809-05 Implementation of Technical Specification Action Requirements Technical Specification 3.7.1.5 requires the licensee to initiate a cooldown in one hour to reach Hode 4 in the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> in accordance with Technical Specification 3.0.3 in the event more than one main steam isolation valve becomes inoperable when the plant is in Mode 3.
Contrary to the above, at about 9 a.m. on February 5,1988, the packing glands on two main steam isolation valves were tightened rendering the valves inoperable while the plant was in Mode 3. The licensee failed to initiate a cooldown to Mode 4 by 10 a.m. and did not meet the requirement to be in Mode 4 until 2:58 a.m. on February 6,1988, when the plant was cooled down for other, unrelated reasons. Consequently the plant was in a condition prohibited by Technical Specification 3.7.1.5 from about 4 p.m. on February 5, 1988, un'il 2:58 a.m. on February 6, 1988.
II. Houston Lighting and Power Position Houston Lighting and Power does not contest the violation.
III. Reason for Violation The root causes of this event were Failure of the Unit Supervisor to recognize that the HSIV's were inoperable due to insufficient familiarity with Technical Specification 3.7.1.5.
Failure of the Unit Supervisor to involve his supervisors in deciding the operability of the valves.
NL.88.085.P2
Atcachment ST-HL-AE-2608 Page 7 of 10 IV. Corrective actions that have been taken The Unit 1 Operations Manager has issued a memo to the Shift Supervi-ors which discusses this event.
Nuclear Plant Operations has implemented a procedure which requires a three party review by the Shif t Supervisor, Unit Supervisor and Shif t Technical Advisor of all LCO actions.
V. Corrective actions that will be taken Intermediate corrective action for this event will be to review the operability requirements for containment isolation valves with Licensed Operators between March 28 and April 29, 1988 during requalification training.
Long Term corrective action will be the evaluation and revision as necessary to the Licensed Operator Training Program to ensure thAt Technical Specifications are taught with emphasis on practical applications. This will be completed by August 31, 1988.
VI. Full Compliance The plant is in full compliance.
I I
l I
l t
l l
l l
NL.88.085.P2 l
1
Attachment ST-HL-AE-2608 -
Page 8 of 10 South Texas Project Electric Generating Station Unit 1 Docket No STN 50-498 Response to Notice of Violation 8809-06 I Statement of Violation Test Procedure Adequacy and Implementation Technical Specifications 6.8.1 states, in part, that written procedures shall be established, implemented, and maintained as recommended in Appendix A of Regulatory Guide 1.33, Revision 2. February 1978.
Contrary to the above, on January 26, 1988, the licensee failed to reestablish the proper testing configuration as required by the note in Section 4.7 of Station Procedure ITEP07-AF-0010 Revision 0, "Auxiliary Feedwater Proof Test," after interrupting the test to feed steam generators. This resulted in obtaining improper test results requiring a repeat of the test. On February 5,1988, the licensee implemented an inadequate procedure. Station Procedure 1 PEPO 4-ZL-0024, Revision 3, "Rod Drop Time Measurement" did not provide for closing the reactor trip breakers, nor did the procedure provide controls to ensure that the same breakers were opened upon recovering from the test.
II. Houston Lighting and Power Position Houston Lighting & Power does not contest the violation associated with the performance of procedure 1 PEPO 4-ZL-0024 Rod Drop Time Hessurement, but does take exception to the citation relating to the performance of procedure iTEP07-AF-0010, Auxiliary Feedwater Proof Test. The following information is provided in support of this position.
Test procedure 1TEP07-AF-0010, Auxiliary Feedwater Proof Test, was performed to show that modifications to the AFW Flow Control Valves (FCV's) had removed the source of the 24Hz excitation which was respons'ble for system resonant vibration discovered during November 1987. Step 4.7 is an initial condition requiring manually closing of each train's FCV against the mechanical stop. The Single-Train portions of the test then consist of opening the Outside Containment Isolation Valve (OCIV) to esteblish flow to a train's steam generator and observing temporary instrumentation for resonant vibrations while incrementally opening the handwheel of the FCV one turn at a time.
Plant conditions during the testing necessitated that the test be suspended periodically to blowdown to maintain proper steam generator level. This was recognized during the writing of the test procedure, and the following r.ote was added to the Initial Conditions section addressing this need:
NL.88.085.P2
m 4 M;;, @ g -
w,A Qff m.3
- g Attachment "l g
- p
'~
ST-HL-AE-2608 Page 9 of 10 3
s' NOTE The test may be suspended and flow to the Steam Generators terminated by closing the respective Stop-Check OCIV at any time while ATW Pump 12 is operating to prevent exceeding the steam generator high level setpoint (87.5%). The test may start assin at the point of suspension providad the Test Coordinator ensures that appropriate AFW conditions are re-established.
During the test the NRC inspector noticed that the Test Coordinator did not require the FCV of the train being tested to be manually closed against its manual stop prior to restarting the test. The note had been intended to allow the action taken by the Test Coordinator, however the NRC inspector present at the time of test did not agree with this interpretation. To prevent further testing delays the test sequence was exited and started over utilizing the additional actions of manually closirg the FCV and reopenir.g it to its previous position following each test suspe..sion. Contrary to the statement of violation, performing the
, test using the original interpretation did not, and would not result in invalid test data, for the following reasons:
- 1. The FCV's in the trains not being tested were isolated from the train undergoing tests, by a closed crosstie valve.
j 2. The FCV in the train being tested romained in the position it was in at the time of the test suspensions only the stopcheck Outside Containment Isolation Valvo was repositioned. This action allowed the steam generator to be blown down to appropriate levels to resume testing.
- 3. Closing the FCV during this process was not necessary for proper system operation, nor was it necessary for personnel protection.
- 4. The action of closing and reopening of the FCV after each test suspension was also undesirable because it unnecessarily lengthened the te'*iSg process.
In summary, Houston Lighting & Power decided to reperform the test in order to eliminate the possibility that the test results would be subject to questions. We do not agree that a proceduran viol. tion occurred.
NL 88.085.P2
Attachment ST-HL-AE-2608 Page 10 of 10 III. Reason for Violation As stated in section II of this response Houston Lighting & Power does not agree that a violation occurred with respect to procedure ITEP07-AF-0010. The following information is provided nagarding procedure 1 PEPO 4-ZL-0024.
The lack of control associated with the reactor trip breakers in procedure IPEPO4-ZL-0024 Rod Drop Time Measurement, was caused by an inadequate review during the generation and approval cycle, in that it was believed that the reactor trip breakers were operated as part of the procedure for starting / securing the Rod Control System Motor Generator sets. If this had been true the prerequisite section would have ensured the breakers closed and the breakers would have been opened when the Shift Supervisors secured the M/G set after being informed that the testing had been completed.
IV. Corrective actions that have been taken Procedure ITEP07-AF-0010, Auxiliary Fe^dwater Proof Test, was suspended when questioned by the NRC inspector and was reperformed utilizing the inspectors interpretation of the Note preceeding step 4.7.
Procedure 1 PEPO 4-ZL-0024, Rod Drop Time Measurement, was changed to incorporate specific steps to control the position of the reactor trip breakers. This was done to provide consistency betwaen various plant procedures.
V. Corrective actions that will be taken No further corrective actions are deemed necessary.
VI Full Compliance The plant is in full compliance.
1 NL.88.085.P2
- - - __ _ _ _ __ _ ,