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Category:CORRESPONDENCE-LETTERS
MONTHYEARNOC-AE-000675, Forwards Clarification on Items Included in 990531 Response to RAI Re Proposed License Amend Associated with Operator Action for Sbloca,As Requested1999-10-21021 October 1999 Forwards Clarification on Items Included in 990531 Response to RAI Re Proposed License Amend Associated with Operator Action for Sbloca,As Requested NOC-AE-000680, Forwards Rev 5 to 0PGP03-ZV-0001, Severe Weather Plan1999-10-20020 October 1999 Forwards Rev 5 to 0PGP03-ZV-0001, Severe Weather Plan NOC-AE-000683, Forwards 30-day Rept Concerning Significant Changes to Accepted Large Break Loss of Coolant Accident ECCS Evaluation Model for South Tx Project,Units 1 & 2,IAW 10CFR50.46(a)(3)(ii)1999-10-19019 October 1999 Forwards 30-day Rept Concerning Significant Changes to Accepted Large Break Loss of Coolant Accident ECCS Evaluation Model for South Tx Project,Units 1 & 2,IAW 10CFR50.46(a)(3)(ii) ML20217K9341999-10-15015 October 1999 Forwards SER Accepting Util 990609 Relief Request RR-ENG-2-4 for Relief from ASME Code,Section XI, Nondestructive Exam Requirements Applicable to Stp,Units 1 & 2,reactor Vessel Closure Head Nuts ML20217K9091999-10-15015 October 1999 Forwards SER Accepting Util 990609 Relief Request RR-ENG-2-3 from ASME Code,Section Xi,Nondestructive Exam Requirements Applicable to South Texas Project,Units 1 & 2, Pressurizer Support Attachment Welds 05000498/LER-1999-008, Forwards LER 99-008-00 Re Turbine Trip That Occurred While Performing Main Turbine Emergency Trip Test.Commitments Made by Licensee Are Listed in Corrective Actions Section of LER1999-10-12012 October 1999 Forwards LER 99-008-00 Re Turbine Trip That Occurred While Performing Main Turbine Emergency Trip Test.Commitments Made by Licensee Are Listed in Corrective Actions Section of LER NOC-AE-000674, Forwards Requested Estimates of Needs for Operator Licensing Exams,Per AL-99-03, Operator Licensing National Exam Schedule1999-10-12012 October 1999 Forwards Requested Estimates of Needs for Operator Licensing Exams,Per AL-99-03, Operator Licensing National Exam Schedule NOC-AE-000625, Requests Partial Relief from ASME Section XI Visual Exam Requirements of IWA-5242(a).Relief Request Is Based on Provisions of Draft ASME Section XI Code Case N-616,which Is Expected to Be Published in Near Future1999-10-0707 October 1999 Requests Partial Relief from ASME Section XI Visual Exam Requirements of IWA-5242(a).Relief Request Is Based on Provisions of Draft ASME Section XI Code Case N-616,which Is Expected to Be Published in Near Future NOC-AE-000610, Requests Relief from ASME Section XI Code Nondestructive Exam Requirements of IWA-5250(a)(2) for Second Inservice Insp Interval,Per Provisions of 10CFR50.55a(3)(i)1999-10-0707 October 1999 Requests Relief from ASME Section XI Code Nondestructive Exam Requirements of IWA-5250(a)(2) for Second Inservice Insp Interval,Per Provisions of 10CFR50.55a(3)(i) NOC-AE-000653, Requests Relief from ASME Section XI Code Requirements of Table IWE-2500-1 for VT-3 Visual Exam of Seals & Gaskets on Airlocks,Hatches & Other Devices Required to Assure Containment leak-tight Integrity,Per 10CFR50.55a(a)(3)(i)1999-10-0707 October 1999 Requests Relief from ASME Section XI Code Requirements of Table IWE-2500-1 for VT-3 Visual Exam of Seals & Gaskets on Airlocks,Hatches & Other Devices Required to Assure Containment leak-tight Integrity,Per 10CFR50.55a(a)(3)(i) ML20217C3221999-10-0707 October 1999 Forwards Insp Repts 50-498/99-16 & 50-499/99-16 on 990808-0918.No Violations Noted.Insp Generally Characterized by safety-conscious Operations,Sound Engineering & Maint Practices & Careful Radiological Work Controls 05000499/LER-1999-006, Forwards LER 99-006-00,re Entry Into TS 3.0.3.Licensee Commitments Listed in Corrective Actions Section of Attachment1999-09-30030 September 1999 Forwards LER 99-006-00,re Entry Into TS 3.0.3.Licensee Commitments Listed in Corrective Actions Section of Attachment ML20212L1651999-09-30030 September 1999 Responds to STP Nuclear Operating Co 981012 & s Which Provided Update to TS Bases Pages B 3/4 8-14 Through B 3/4 8-17.NRC Staff Found Change Consistent with TS 3/4.8.2 DC Sources. Staff Found & Deleted Typographical Error NOC-AE-000664, Forwards Rev 1 to STP Electric Generating Station Unit 1 Cycle 9 COLR & Rev 1 to STP Electric Generating Station Unit 2 Cycle 7 Colr1999-09-30030 September 1999 Forwards Rev 1 to STP Electric Generating Station Unit 1 Cycle 9 COLR & Rev 1 to STP Electric Generating Station Unit 2 Cycle 7 Colr ML20212J7141999-09-29029 September 1999 Forwards Insp Repts 50-498/99-15 & 50-499/99-15 on 990920-24 at South Texas Project Electric Generating Station.No Violations Noted.Insp Covered Requalification Training Program & Observation of Requalification Activities NOC-AE-000646, Informs NRC That STP Nuclear Operating Co Is Y2K Ready IAW Nei/Nusmg 97-07 Guidelines & Also Provides Response to NRC Ltr1999-09-28028 September 1999 Informs NRC That STP Nuclear Operating Co Is Y2K Ready IAW Nei/Nusmg 97-07 Guidelines & Also Provides Response to NRC Ltr ML20212J0651999-09-27027 September 1999 Discusses Licensee 980330 Response to GL 97-06, Degradation of SG Internals. Concludes That Response to GL Provides Reasonable Assurance That Condition of SG Internals in Compliance with Current Licensing Bases for Facility ML20212F1791999-09-24024 September 1999 Discusses 990923 Meeting Conducted in Region IV Ofc Re Status of Activities to Support Confirmatory Order, ,modifying OL & to Introduce New Director,Safety Quality Concerns Program.List of Attendees Encl ML20212E9091999-09-23023 September 1999 Discusses GL 98-01, Year 2000 Readiness of Computer Sys at Npps, Supplement 1 & STP Nuclear Operating Co Response for STP Dtd 990629.Understands That at Least One Sys or Component Listed May Have Potential to Cause Transient ML20212F2111999-09-22022 September 1999 Forwards Review of SG 90-day Rept, South Texas Unit-2 Cycle 7 Voltage-Based Repair Criteria Rept, Submitted by Util on 990119 NOC-AE-000633, Forwards Rev 3 to SG-99-04-005, STP 1RE08 Outage Condition Monitoring Rept & Final Operational Assessment. Rept Satisfies Reporting Requirements of NEI 97-06,dtd Dec 19971999-09-21021 September 1999 Forwards Rev 3 to SG-99-04-005, STP 1RE08 Outage Condition Monitoring Rept & Final Operational Assessment. Rept Satisfies Reporting Requirements of NEI 97-06,dtd Dec 1997 NOC-AE-000634, Forwards Addl Info Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Povs. MOV design-basis Review Checklist,Encl1999-09-21021 September 1999 Forwards Addl Info Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Povs. MOV design-basis Review Checklist,Encl NOC-AE-000649, Forwards Current Annual Financial Data for STP Electric Generating Station Per 10CFR50.71(b),acting on Behalf of Central Power & Light Co,City of Austin,Tx,City Public Svc Board of San Antonio & Hl&P1999-09-21021 September 1999 Forwards Current Annual Financial Data for STP Electric Generating Station Per 10CFR50.71(b),acting on Behalf of Central Power & Light Co,City of Austin,Tx,City Public Svc Board of San Antonio & Hl&P 05000499/LER-1999-005, Forwards LER 99-005-00,re Esfa Following Loss of Power to Standby Transformer 2 Due to Electrical Fault.Licensee Commitments Are Listed in Corrective Actions Section of LER1999-09-20020 September 1999 Forwards LER 99-005-00,re Esfa Following Loss of Power to Standby Transformer 2 Due to Electrical Fault.Licensee Commitments Are Listed in Corrective Actions Section of LER ML20212D9171999-09-16016 September 1999 Informs That on 990818,NRC Completed Midcycle PPR of South Texas Project & Identified No Areas in Which Performance Warranted Insp Beyond Core Insp Program.Details of Insp Plan Through Mar 2000 & Historical Listing of Plant Issues,Encl ML20216F5471999-09-15015 September 1999 Discusses 990914 Meeting Conducted at Region Iv.Meeting Was Requested by Staff to Introduce New Management Organization to Region IV & to Discuss General Plant Performance & Mgt Challenges IR 05000498/19990121999-09-14014 September 1999 Forwards Insp Repts 50-498/99-12 & 50-499/99-12 on 990816-19.Three Violations Occurred & Being Treated as Ncvs. Areas Examined During Insp Included Portions of Access Authorization & Physical Security Programs 05000498/LER-1999-007, Forwards LER 99-007-00 Re Train 'B' CR Makeup & Cleanup Filtration Sys Being Inoperable for Greater than Aot.Util Intends to Append Addl Info Section of LER with Brief Description of Test Results,Rather than Submit Separate LER1999-09-13013 September 1999 Forwards LER 99-007-00 Re Train 'B' CR Makeup & Cleanup Filtration Sys Being Inoperable for Greater than Aot.Util Intends to Append Addl Info Section of LER with Brief Description of Test Results,Rather than Submit Separate LER ML20211P8201999-09-0909 September 1999 Forwards SE Authorizing 990224 Submittal of First 10-year Interval ISI Program Plan - Relief Request RR-ENG-24,from ASME Section XI Code,Table IWC-2500-1 NOC-AE-000638, Forwards License Renewal Applications & Certifications of Medical Exam for Seven Listed Licensed Operators at Stp,Per 10CFR55.57.Encl Withheld,Per 10CFR2.790(a)(6)1999-09-0909 September 1999 Forwards License Renewal Applications & Certifications of Medical Exam for Seven Listed Licensed Operators at Stp,Per 10CFR55.57.Encl Withheld,Per 10CFR2.790(a)(6) ML20211P7671999-09-0909 September 1999 Forwards SER Authorizing Licensee 990517 Alternative Proposed in Relief Request RR-ENG-2-8 to Code Case N-491-2 for Second 10-year Insp Interval of South Texas Project, Units 1 & 2,pursuant to 10CFR50.55a(a)(3)(i) ML20211P7871999-09-0909 September 1999 Forwards Safety Evaluation Re First 10-yr Interval Inservice Insp Program Plan Request for Relief RR-ENG-31 IR 05000498/19990141999-09-0303 September 1999 Forwards Insp Repts 50-498/99-14 & 50-499/99-14 on 990627-0807.Apparent Violations Identified & Being Treated as Noncited Violations Consistent with App C of Enforcement Policy NOC-AE-000562, Requests Relief from Contruction Code non-destructive Exam Requirements for Repair/Replacement Activities During Second Inservice Insp Interval of Units 1 & 2,IAW Provisions of 10CFR50.55a(a)(3)(i)1999-08-31031 August 1999 Requests Relief from Contruction Code non-destructive Exam Requirements for Repair/Replacement Activities During Second Inservice Insp Interval of Units 1 & 2,IAW Provisions of 10CFR50.55a(a)(3)(i) ML20212A4351999-08-27027 August 1999 Discusses Investigation Rept OI-4-1999-009 Re Activites at South Texas Project.Oi Investigation Initiated in Response to Alleged Employment Discrimination Complaint. Allegation Not Substantiated.No Further Action Planned NOC-AE-000617, Forwards semi-annual Fitness for Duty Program Performance Rept for 990101-990630,IAW 10CFR26.71(d)1999-08-26026 August 1999 Forwards semi-annual Fitness for Duty Program Performance Rept for 990101-990630,IAW 10CFR26.71(d) ML20211J2511999-08-26026 August 1999 Discusses Proposed TS Change on Replacement SG Water Level Trip Setpoint for Plant,Units 1 & 2 NOC-AE-000585, Provides Notification That South Texas Project Has Completed Integrity Evaluation of Units 1 & 2 Reactor Coolant Pump Casings Required by Paragraph (D) of Code Case N-4811999-08-25025 August 1999 Provides Notification That South Texas Project Has Completed Integrity Evaluation of Units 1 & 2 Reactor Coolant Pump Casings Required by Paragraph (D) of Code Case N-481 ML20211F4421999-08-24024 August 1999 Forwards SE Authorizing Licensee 990513 Request for Relief RR-ENG-2-13,seeking Relief from ASME B&PV Code Section Xi,Exam Vessel shell-to-flange Welds for Second ISI Intervals ML20211F5031999-08-23023 August 1999 Forwards SE Authorizing Licensee 990315 Request for Relief RR-ENG-30,seeking Relief from ASME B&PV Code,Section Xi,Nde Requirements Applicable to Stp,Unit 2 SG Welds ML20212A4391999-08-17017 August 1999 Discusses Investigation Rept OI-4-1999-023 Re Activities at South Texas Project.Oi Investigation Initiated in Response to Alleged Employment Discrimination for Initiating Condition Report to Document Unauthorized Work Practices ML20210U1271999-08-16016 August 1999 Forwards Insp Repts 50-498/99-08 & 50-499/99-08 on 990517-21 & 0607-10.No Violations Noted.Corrective Action Program Was Reviewed ML20211A9501999-08-12012 August 1999 Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl ML20211B7881999-08-10010 August 1999 Transmits Summary of Two Meetings with Risk-Informed TS Task Force in Rockville,Md on 990514 & 0714 ML20210L1461999-08-0303 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams NOC-AE-000603, Informs of Addition of Restriction to SRO License 42658, for KM Espinoza,Effective 990721,per 10CFR50.74.Encl Info Withheld,Per 10CFR2.790(a)(6)1999-07-29029 July 1999 Informs of Addition of Restriction to SRO License 42658, for KM Espinoza,Effective 990721,per 10CFR50.74.Encl Info Withheld,Per 10CFR2.790(a)(6) NOC-AE-000470, Forwards Amend 12 to STP Fire Hazards Analysis Rept. Summary of Changes Made Under Provision of 10CFR50.59 Also Encl1999-07-28028 July 1999 Forwards Amend 12 to STP Fire Hazards Analysis Rept. Summary of Changes Made Under Provision of 10CFR50.59 Also Encl NOC-AE-000599, Forwards STP Unit 1,Cycle 9 Startup Testing Summary Rept. No New Licensing Commitments Contained in Ltr1999-07-28028 July 1999 Forwards STP Unit 1,Cycle 9 Startup Testing Summary Rept. No New Licensing Commitments Contained in Ltr NOC-AE-000589, Forwards Rev to 1RE08 ISI Summary Repts for Repairs & Replacements & for Sys Pressure Tests,Corecting Date of End of Insp Interval Provided in Item 9 of from NIS-1 from 09/24/99 to 09/24/20001999-07-26026 July 1999 Forwards Rev to 1RE08 ISI Summary Repts for Repairs & Replacements & for Sys Pressure Tests,Corecting Date of End of Insp Interval Provided in Item 9 of from NIS-1 from 09/24/99 to 09/24/2000 ML20210F3851999-07-26026 July 1999 Forwards Exam Repts 50-498/99-301 & 50-499/99-301 on 990706- 15.Exam Included Evaluation of 9 Applicants for SO Licenses & 8 Applicants for RO Licenses 1999-09-09
[Table view] Category: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
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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
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The Light Company n,-,,,, usini,g u,,,, 4 m u ,,a = > n, - ,,,i. m ..a m o a o m s m n August 26, 1985 ST-HL-AE-1338 File No.: G2.4 M22.3 Q17.1.1 P11.1 Mr. Robert D. Martin Regional Administrator, Region IV Nuclear Regulatory Commission E
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South Texas Project i~*'
Units 1 & 2 :
Occket Nos. STN 50-498, STN 50-499 Response to Notice of Violation 50-498/8507-01 and 8507-02 50-499/8507-01 and 8507-02
Dear Mr. Martin:
Houston Lightin9 & Power Company (HL&P) has reviewed the Notice of Violations 59-498/8507-01, 50-499/8507-01 and 50-498/8507-02, 50-499/
8507-02 dated July 25, 1985 and submits the attached response pursuant to 10CFR2.201.
If you should have any questions on this matter, please contact Ms. Frostie A. White at (512) 972-8392.
V y truly yours, J. H. Goldberg I Group Vice President, Nuclear JHG/FAW/kc
Attachment:
Response to Notices of Violations (8507-01)
(8507-02) g 0510000595 050930 l W2/NRC2/r PDR ADOCK 05000490 l 0 PDR
... J
.' ST-HL-AE-1338 File No.: G2.4 0M22.3 Houston Lighting & Power Company Page 2 cc:
Hugh L. Thompson, Jr., Director Brian E. Berwick, Esquire Division of Licensing Assistant Attorney General for Office of Nuclear Reactor Regulation the State of Texas U.S. Nuclear Regulatory Commission P. O. Box 12548, Capitol Station Washington, DC 20555 Austin, TX 78711 N. Prasad Kadambi, Project Manager Lanny A. Sinkin U.S. Nuclear Regulatory Commission 3022 Porter Street, N.W. #304 7920 Norfolk Avenue Washington, D.C. 20008 Bethesda, MD 20814 Oreste R. Pirfo, Esquire Claude E. Johnson Hearing Attorney Senior Resident Inspector /STP Office of the Executive Legal Director c/o U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission P. O. Box 910 Washington, DC 20555 Bay City, TX 77414 Charles Bechhoefer, Esquire M. D. Schwarz, Jr. , Esquire Chairman, Atomic Safety & Licensing Board Baker & Botts U.S. Nuclear Regulatory Commission One Shell Plaza Washington, DC 20555 Houston, TX 77002 Dr. James C. Lamb, III J. R. Newman, Esquire 313 Woodhaven Road Newman & Holtzinger, P.C. Chapel Hill, NC 27514 1615 L Street N.W.
Washington, DC 20036 Judge Frederick J. Shon Atomic Safety and Licensing Board Director, Office of Inspection U. S. Nuclear Regulatory Commission and Enforcement Washington, D. C. 20555 U.S. Nuclear Regulatory Commission Washington, DC 20555 Mr. Ray Goldstein, Esquire 1001 Vaughn Building E. R. Brooks /R. L. Range 807 Brazos Central Power & Light Company Austin, TX 78701 P. O. Box 2121 Corpus Christi, TX 78403 Citizens for Equitable Utilities, Inc.
c/o Ms. Peggy Buchorn H. L. Peterson/G. Pokorny Route 1, Box 1684 City of Austin Brazoria, TX 77422 P. O. Box 1088 Austin, TX 78767 Docketing & Service Section Office of the Secretary J. B. Poston/A. vonRosenberg U.S. Nuclear Regulatory Commission City Public Service Board Washington, DC 20555 P. O. Box 1771 San Antonio, TX 78296 l
l W2/NRC2/r Revised 5/22/85 L >
{ .
Attachtrant 1 l
' ST-HL-AE-1338 ,
l File No.: G2.4, M22.3 i Page 1 of 4
- South Teras Project
! Response to .40tice of Violation j 50-498/8507-01 l 50-499/8507-01 I. Statement of Violation I Based on the results of an NRC inspection conducted during the i period of May 13-24, 1985 and May 28-31, 1985, and in accordance with the NRC Enforcement Policy (10 CFR Part 2, Appendix C), the l following violation was identified:
l Failure to Properly Follow Procedure 4
l Criterion V of Appendix B to 10 CFR Part 50 required that i activities affecting quality be prescribed by and accomplished in
- accordance with appropriate instructions, procedures, or drawings.
l This requirement is part of the approved QAPD (Quality Assurance Plan Description) for South Texas Project, Section 5.
i Procedures PGP3-ZM-1, ASP-23 and QCP 12.1 require " recording of the j identification and dates of all items inspected or tested with M&TE j be recorded on the " Tool Data Issue / Record Card" - to provide traceability. .
! Contrary to the above, the NRC inspector observed instances when no information was recorded or improperly noted in the record section, t
- Procedure PGP3-ZM-1 requires test equipment returned prior to being j recalled to have the calibration sticker removed and a white dot attached, f Contrary to the above, the NRC inspector observed the laboratory
- M&TE calibration clerk attaching a Form 5 to all items ir-
! respective of whether the item was recalled, damaged or returned i prior to recall.
Procedures ASP-23 and QCP-12.1 require M&TE be returned to the l calibration laboratory prior to expiration of calibration period or i if sticker indicates equipment period has expired, equipment will l be immediately returned to the calibration laboratory.
i Contrary to the above, M&TE ST-CC-3173 and ST-CC-3174 were not i returned until 8 days and 12 days after their respective dates, i
i Procedure PGP3-ZM-1 required that equipment requiring calibration be listed in the calibration schedule.
l W2/NRC2/r
Attachment 1 ST-HL-AE-1338 File No.: G2.4, M22.3 Page 2 of 4 II. Reply In the four situations that are identified in the inspection report,1) improper recording of usage on " Tool Data Issue / Record Card", 2) not attaching a white dot to returned test equipment, 3) test equipment not being returr.ad on calibration due date and 4) test equipment not being listed in the calibration schedule occurred due to failure to follow established procedures. The investigation indicates that there has been no adverse effect on quality or hardware resulting from these failures to follow procedure.
III. Corrective Steps Taken or To Be Taken An appropriate investigation has been performed by Bechtel and Ebasco representatives to determine the cause of the Tool Data Issue / Record Cards not being properly completed. These investigations have confirmed that the column labeled "Value" did not always contain proper information or was not completed. The Tool Data Issue / Record Card "Value" column is utilized for evaluation of test equipment found out of tolerance to limit the amount of retest required. However, the Tool Data Issue / Record Card is not the official record which identifies the results of the test or inspection being performed for acceptability. The appropriate Quality Control Inspection Reports generated in accordance with applicable procedures are the documents required to indicate test or inspection results and acceptability. The investigation indicated that failure to record values on the Tool Data Issue / Record Card have had no adverse effect on hardware.
In regard to the application of a white dot to the test equipment after the test equipment has been recalled and the calibration sticker removed, the issue clerks had requested clarification of the procedural requirements for application of the white dots when test equipment is returned to the issue area. A senior metrology laboratory technician proceeded to direct the personnel to apply the Form 5 instead of the white dot for all test equipment returned to the issue area, since the white dot and the Form 5 serve the same purpose. The purpose of the white dot and the Form 5 was to easily identify test equipment which requires calibration before it can be reissued. Previously PGP3-ZM-01 allowed the use of the Form 5 for all M&TE equipment prior to the implementation of the white dot identification. The white dot was specifically designed for construction-oriented M&TE. The Form 5 provides the mechanism to identify additional information that could be useful if test equipment has been damaged or is suspected of being damaged. The senior metrology laboratory technician interpreted the procedural M2/NRC2/r
Attachment 1 ST-HL-AE-1338 File No.: G2.4, M22.3 Page 1 of 4 South Texas Project Response to Notice of Violation 50-498/8507-01 50-499/8507-01
- 1. Statement of Violation Based on the results of an NRC inspection conducted during the period of May 13-24, 1985 and May 28-31, 1985, and in accordance with the NRC Enforcement Policy (10 CFR Part 2. Appendix C), the following violation was identified:
Failure to Properly Follow Procedure Criterion V of Appendix B to 10 CFR Part 50 required that activities affecting quality be prescribed by and accomplished in accordance with appropriate instructions, procedures, or drawings.
This requirement is part of the approved QAPD (Quality Assurance Plan Description) for South Texas Project, Section 5.
Procedures PGP3-ZM-1, ASP-23 and QCP 12.1 require " recording of the identification and dates of all items inspected or tested with MATE be recorded on the " Tool Data Issue / Record Card" - to provide traceability.
Contrary to the above, the NRC inspector observed instances when no information was recorded or improperly noted in the record section.
Procedure PGP3-ZM-1 requires test equipment returned prior to being recalled to have the calibration sticker removed and a white dot attached.
Contrary to the above, the NRC inspector observed the laboratory M&TE calibration clerk attaching a Form 5 to all items f r-respective of whether the item was recalled, damaged or returned prior to recall.
Procedures ASP-23 and QCP-12.1 require M&TE be returned to the calibration laboratory prior to expiration of calibration period or if sticker indicates equipment period has expired, equipment will be immediately returned to the calibration laboratory.
Contrary to the above, M&TE ST-CC-3173 and ST-CC-3174 were not returned until 8 days and 12 days after their respective dates.
Procedure PGP3-ZM-1 required that equipment requiring calibration be listed in the calibration schedule.
Contrary to the above, test equipment ST-CC-3173 was not listed in the calibration schedule.
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Attachment 1 ST-HL-AE-1338
! File No.: G2.4, M22.3 Page 3 of 4 requirements to allow the use of the Form 5 instead of the white 1 dot inasmuch as the Form 5 covers all M&TE equipment. The application of the white dot for construction-oriented M&TE was to i be used in lieu of the Form 5 to expedite the calibration process for equipment that was not damaged. The immediate actions taken were to place the white dots on the test equipment as required and to conduct retraining of the personnel to ensure adherence to procedural requirements. The personnel training was completed May I' 30, 1985. Subsequently, procedure PGP3-ZM-01 was revised to clarify the use of the Form 5 and to delete the requirements for j the white dot. The procedure revision was effective June 27, 1985.
! Although the white dot was not placed on the returned test equipment, adequate controls were in place to ensure that no test j equipment was reissued to the field without recalibration. This is l considered to be an isolated case and no recurrence control is 3
required.
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Investigative actions have been performed by Bechtel and Ebasco representatives in regard to the M&TE being returned late to the 4 calibration laboratory. The two pieces of test equipment, ST-CC-3173 and ST-CC-3174, have been returned to the netrology i laboratory. The recalibration of the test equipment and j investigative actions indicate that there has been no adverse i effect on hardware. A review of the record of issued test 1 equipment resulted in HL&P QA issuing SDR's H-125 and H-126 which
! identify eighty additional pieces of test equipment which had been j recalled by procedure, but not returned by the calibration due l l date. l I Immediate actions were taken to notify the users to return the test l i equipment. When test equipment is returned to the metrology '
- laboratory, it is recalibrated to verify the test equipment is !
l still in tolerance. If test equipment is found to be out of ,
i tolerance, an out-of calibration evaluation is performed and i j appropriate corrective action is taken. If test equipment is damaged and cannot be recalibrated or is lost, the test equipment is assumed to be out of tolerance and an out of calibration j evaluation is also performed. Therefore, when test equipment is i
returned to the metrology laboratory even though it might be af ter its calibration due date, the validity of the data that has been l taken is verified by recalibration. If equipment is found to be
- out of tolerance, an out-of-calibration evaluation is performed and ;
- appropriate corrective action is taken to ensure that no adverse -
! effect on hardware has occurred.
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Attachment 1 1 ST-HL-AE-1338 i File No.: G2.4, M22.3 Page 4 of 4 Test equipment ST-CC-3173 was not listed in the calibration
, schedule because the completed calibration data sheet was
- inadvertently filed in the history file before the necessary information was entered into the calibration schedule program.
l Test equipment ST-CC-3174 was also determined not to have been entered into the calibration schedule program for the above reason.
Recall notices had not been issued for either ST-CC-3173 or l- ST-CC-3174, since they were not statused in the calibration schedule. The cctions taken were to notify the user to return ST-CC-3173 and ST-CC-3174. The user returned ST-CC-3173 and ST-CC-3174. Review of the M&TE files did not reveal any additional i l items that were not entered into the calibration schedule.
l Therefore, the inadvertent filing of the completed calibration data ,
sheets before the calibration information was updated in the schedule is considered to be an isolated occurrence. Retraining was provided to the clerical personnel, data entry personnel, and the metrology technicians on the importance of handling of the calibration data sheets. Separate in/out routing baskets have been established to ensure that the calibration data sheets are properly handled, routed, and filed. The review action indicates that there has been no adverse effect on hardware. These actions were completed July 16, 1985. This is considered to be an isolated
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case and no recurrence control is required.
! IV. Corrective Action Which Will Be Taken to Avoid Further Violations t
Procedure ASP-23 has been revised (on July 31,1985) to provide enchanced details and instructions for completion of the Tool Data l Issue / Record Card. Appropriate construction personnel will be s instructed to the above revision and construction personnel will be j reinstructed to strictly adhere to the procedural requirements.
- Quality Control supervisors have been reinstructed on the proper j comnletion of the Tool Data Issue / Record Card and on the late return of test equipment. In addition, the Quality Control l Supervisors will be required to assure that these requirements are j understood by all inspectors.
V. Date When Full Compliance Will Be Achieved l
I full ccmpliance will be achieved by September 6,1985.
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Attachment 2 ST-HL-AE-1338 File No.: G2.4, M22.3 Page 2 of 2 The fool Data Issue / Record Card, which is used to check out M&TE, does contain the signature and badge number of the user and is the governing document used to control and return equipment. Should the spelling be difficult to determine, the badge number could be used to determine the individual's name by contacting the payroll personnel or the authorized user's file. This " check-in/out" log was an informal log that was used for convenience, its use or non-use did not and would not have any effect on the iscuance or recall of test equipment. The use of the log has been discontinued.
The use of the "past due tracking log" had previously been identified as an enhancement to the overall metrology laboratory program. This enhancement was being used to quickly determine the status of M&TE that had been recalled, if recall notices had been issued or if M&TE had been returned, instead of researching the individual files each time the information was needed.
The information that was contained on the log was available from the calibration schedule or the files. The use or non-use of the log would not have any effect on the determination of the status of the M&TE since procedural requirements were contained in PGP3-ZM-01 that governed the recall of M&TE and the responsibilities and actions to be taken. Revisions to the procedure were being drafted to enhance the overall Measuring and Test Equipment Program which would utilize this log. The "past due tracking log" was being utilized, by verbal instructions, before the procedure was revised.
PGP3-ZM-01 was revised on June 27, 1985 and training of the personnel has been completed.
III. Corrective Steps Which Have Been Taken and the Results Achieved The " check in/out" log has been discontinued and procedure PGP3-ZM-01 has been revised to incorporate use of the recall log.
HL&P will avoid introducing verbal enhancements to programs governed by written procedures.
IV. Date When Full Compliance Will Be Achieved HL&P is in compliance with 10CFR50, Appendix B. Criterion V and applicable site procedures.
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Attachment 2 ST-HL-AE-1338 File No.: G2.4, M22.3 Page 1 of 2
! South Texas Project Response to Notice of Violation 50-498/8507-02
, 50-499/8507-02 J
1 I. Statement of Violation Based on the results of an NRC inspection conducted during the period of May 13-24, 1985 and May 28-31, 1985, and in accordance with the NRC Enforcement Policy (10CFR Part 2, Appendix C), the following violation was identified:
Failure to Have Approved Procedures Criterion V of Appendix 8 to 10 CFR Part 50 requires that activities affecting quality be prescribed by and accomplished in accordance with appropriate instructions, procedures, or drawings.
This requirement is part of the approved QAPD (Quality Assurance r Plan Description) of South Texas Project, Section 5.
Contrary to the above, the Metrology and Test Equipment Laboratory is using a " check-in/out" log and a "past due tracking log". Neither of these logs are addressed in approved procedures which explains their purpose, responsibilities or actions to be taken in the use of these logs.
II. Reply Adequate provisions have been contained in procedures PGP3-ZM-01, ASP-23 and QCP-12.1, through the use of the Calibration Schedule, Tool Data Issue / Record Card, and the M&TE History Files, to ensure proper calibration, issuance and retrieval of M&TE equipment.
In December 1984, the HL&P and Ebasco metrology laboratory programs were consolidated into one program with HL&P having the responsibility for operation of the metrology laboratory.
The " check in/out" log that was being used by the issue clerks was a log that was used during the time that the Ebasco organization had responsibility for the metrology laboratory. This log was a carryover from the previous program and was being used by the issue clerks as a convenience.
The log had a space for users to print their name and the clerks would use the log to help determine the spelling of the user's name.
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