|
---|
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
fq w'! a . !, ,; ; 'i**
.~
Wpy."w The Light u : co mp a nySuth Temas Project Electric Generating P. O.Station Box 289 - Wadworth, Texas m83 -
. Houston Lighting & Power
.a (jl, -
b* ,
ST-HL-AE-3320 m,'* File No,'; G4 '. 2 ,
J41.3,- C9.17-
,W # '10CFR50
[M U..S.. Nuclear Regulatory Commission h (Attention: Document Control Desk
- Washington, DC
~
( 20555 e w
'O .g South Texas Project Electric Generating Station -!
l Units 1 and 2
, Docket Nos. STN 50-498, STN 50 499 Completion of Modifications to the Safety Parameter-
.Disolav System (SPDS) for the First Refuelinn Outane-
, (g.
Reference:
A. Issuance of Facility License No. NPF-71, South Texas Project Unit 1;--D. M. Crutchfield, NRC; Letter to J. H. Goldberg, 4 ,
HL&P; August 21,.1987.
, ,3 B. Safety Evaluation Report Related to the Operation of South i1 . Texas Project Units 1 and 2, NUREG-0781, Supplement No. 4, 4
July 1987.
3 C. Safety Parameter Display System (SPDS); M. A. McBurnett, HL&P; Letter to the NRC; March'18, 1988; ST-HL- AE- 25 89.
D. Safety Evaluation Report Related to the Operation of South j g Texas Project Units 1 and 2 NUREG-0781, Supplement No. 6, '
C December 1988.
E. Modifications to the Safety Parameter Display System (SPDS); :j M. A. McBurnett, HL&P; Letter to the NRC; February 2, 1989; -1 ST-HL-AE-2962. !
5 4 ;
I' :- i THC/SPDS1289.LTR 9001120032 900105 1 PDR p
ADOCK 0500C498 FDC M.3 J A Subsidiary of Houston Industries incorporated ' I l
$$ 1- 1
~-
,- . s.
. Houston Lighting & Power Company South Texas Project Electric Generating Station sT-n-a-332o File No.: 04.2 J41.3, 09.17 Fase 2 of 4 4
F. Submittal of Safety Parameter Display System (SPDS) Safety Analysis Report; M. ' R. Wisenburg, HL&P; Letter to Vincent S.
Noonan, NRC; December 23, 1986; ST-HL AE-1861.
The Safety Parameter Display System (SPDS) provides a display-of plant parameters from which the safety status of the plant may be assessed both
.during normal / abnormal operation and emergency conditions. The primary function of the SPDS is to help operating personnel in the Control Room make quick assessments of plant safety status. The SPDS displays are designed in accordance with NUREG-0696 and NUREG-0700.
In Reference A, the NRC identified a license condition regarding the SPDS that HL&P was required to satisfy prier to startup after the first refueling outage. ~ This license condition referenced five actions which are shown on page 18-9 of-SSER 4 (Reference B). In Reference C, HL&P provided detailed descriptions of actions taken to resolve items 2 through 5, SSER-6
-(Reference D) subsequently closed these four items.
Item 1 required modification of tne critical safety function displays to provide the status of the radioactivity control safety function and to continuously display the status boxes that summarize plant safety status.
These modifications were completed on Unit 1 prior to startup from its first-refueling outage.
Attachment I provides a detailed description of the SPDS modifications ,
which added two displays for Radioactivity Status. This attachment also describes the additional modifications required to other displays as a result of the new radioactivity status displays. Attachment II provides a description of SPDS keyboard and keypad modifications required as a result of the addition of the two new Radioactivity Status SPDS displays.
Attachments I and II also contain a description of the modifications to the SPDS software and keyboards to provide continuous display of the safety status indicators on a dedicated SPDS CRT.
The completion of'these modifications fullfills HL&P's previous commitments outlined in Reference E and provides the final closcout for the license conditions, for Unit 1, associated with the NRC audit of the SPDS.
These same modifications will be performed on Unit 2 during its first refueling outage.
As a result of various observations by the NRC, HL&P Engineering, HL&P Operations, and the SPDS Man-in-the Loop Validation Testing, several Human Engineering Discrepancies (HEDs) have been identified against the SPDS
' displays. An extensive review of the SPDS displays, considering these HEDs, the STP CRDR criteria, and technical correctness, has recently been completed.
The SPDS revisions to address these HEDs and the results of this review are TliC/SPDS1289.LTR
c- y i!l l
Houston Lighting & Power Company
- South Texas Project Electric Generating Station 37.uL- a -as2o File No.
- . G4.2 J41.3, C9.17 Page 3 of 4 being treated as Category C HEDs, and are scheduled to be completed prior to startup from the third refueling outage of Unit 1 and the second refueling ,
outage of Unit 2. The SPDS Safety Analysis Report (originally provided by' Reference F) .will be updated and submitted to the NRC upon completion of these modifications.
If you should have any questions on this matter, please contact Mr. A.
'W.-Harrison at (512) 972-7298.
cB nett Manager, Licensing THC/
Attachments: I. Description of New Displays and other SPDS Display Modifications II. Description of Keyboard Modifications l
l.
l l
l L
l THC/SPDS1289.LTR l-.
l l
- = c,
. ST-HLoAE 3320'
, ' Houston Lighting & Power Company File No.: G4.2
- South Texas Project Electric Generating Station J41,3, G9.17 Page 4 of 4 cc
Regional Administrator, Region IV Rufus S. Scott Nuclear Regulatory Cormission Associate General Counsel
.611 Ryan Plaza Drive, Suite 1000 Houston Lighting & Power Company I Arlington, TX 76011 P. 0. Box 61867 Houston, TX 77208 George Dick, Project Manager U.S. Nuclear Regulatory Commission INPO l
-Washington, DC 20555 Records Center 1 1100 circle 75 Parkway
'J.'I. Tapia Atlanta, GA 30339-3064
. Senior Resident Inspector ,
c/o U. S. Nuclear Regulatory; Dr. Joseph M. Hendrie l Commission 50 Be11 port Lane P. O. Box 910 Be11 port, NY. 11713 Bay City, TX 77414-D. K. Lacker J. R. Newman, Esquire Bureau of Radiation Control Newman & Holtzinger, P.C. Texas Department of Health 1615 L Street, N.W. 1100 West 49th Street Washington, DC 20036 Austin, TX 78704 D. E. Ward /R. P. Verret ;
Central' Power & Light Company 'i P. O. Box 2121 Corpus Christi, TX 78403 J. C. Lanier Director of Generation City of Austin Electric Utility 721 Barton Springs Road Austin, TX .78704 R. J. Costello/M. T. Hardt ,
City Public Service Board j P. O. Box 1771 i San Antonio, TX 78296 i
l l
l-1 Revised 12/15/89 L4/NRC/
p
-[-, IU
- p. r -
li Attachment I ST-HL-AE-3320 Page 1 of 3-DESCRIPTION OF NEW DISPLAYS AND OTHER'SPDS DISPLAY MODIFICATIONS Addition of Radioactivity Status Safety Function Display to the Safety Parameter _ Display System !
.Two new displays were added to the Safety Parameter Display System (SPDS)'to provide the radioactivity control status safety function, to address the NRC concerns with the requirements of Supplement 1 to NUREG 0737. The two new displays are identical and are titled Radioactivity Status. The names for [
these two displays are NRAD (Normal Radioactivity Status) and CRAD.(Critical
,, Radioactivity Status).
To develop these displays, a review was performed by Engineering and l
, Operations' personnel to determine which radiation monitors provided the most useful information relative to the plant radioactivity status. This review
. also considered uses of radiation monitors in accident type determination.
The following radiation monitors were selected for these displays:
- 1. RCB-Purge I 2, Control Room /EAB Vent
- 3. Spent Fuel Pool Exhaust
- 4. Unit Vent. Exhaust l
- 5. RCB Atmosphere :
6, Containment High Range Area Radiation I
- 7. Condenser Vacuum Pump Exhaust
- 8. Main Steam Line
'9. -Steam' Generator Blowdown The_ normal radioactivity [NRAD) and critical radioactivity (CRAD) }
displays are shown in Figures I-1 and I-2, respectively. These displays have ;
a'similar layout to the other SPDS displays. The top left box of each display j contains the display mnemonic, the display number, and South Texas Project '[
(STP) unit number. The top middle box of each display contains the display
'name. The top right box of each display contains the date, time, and the l plant operational mode. !
The bottom left section of the displays contains the status indicators ;
for the Normal Safety Functions (NSF) and Critical Safety Functions (CSF) . l The computer displays the NSF or CSF indicators based on the position of the reactor trip breakers. The NSF indicators are displayed if the reactor trip breakers are closed. The CSF indicators are displayed if the reactor trip breakers are open.
The center bottom section of each display is reserved for the system detail function. The bottom right section displays the Emergency Response THC/SPDS1289 I
)
=' 9/t
_;l > ' )
~*
- h. ,
n.
E
l ST-HL-AE-3320 .j Page 2 of 3 t (
d' ,
f 2Fac111 ties Data Acquisition and Display System (ERFDADS) computer operational '
L" health" via .an alpha / color-cued . indicator.
The middle section.of the Radioactivity Status displays provides the readings of the nine: radiation monitors listed above in three rows of three, based on similarity-of information provided and type of accident and/or-_ ,
g; release for which they provide a response or information. The overall format
- of these displays was coordinated with the Operations Department and reviewed ,
in accordance with the'STPEGS Control Room Design-Review (CRDR) program. '
L-L The top three radiation monitors on the NRAD and CRAD displays,-RCB PURGE, CR/EAB VENT, and SFP EXHAUST, are ESF actuation monitors and provide automatic responses to accidents.
L" The middle three. radiation monitors, UNIT VENT, RCB ATMOSPHERE, and CNTMT HI RANGE, are release / containment monitors. These monitors provide- -
information.regarding~ breaches of the reactor coolant system boundary and
~
regarding releases from the plant to offsite.
^ The bottom three radiation monitors, COND VAC PUMP, MAIN STM LINE, and- '
SG BLOWDOWN, provide information useful in identifying-a steam generator, tube = ,
rupture accident. [
t Modifications to Other Displays The addition of the radioactivity control safety function also required the revision of the other SPDS and ERFDADS displays.
t Both. the Top Level Normal Safety Function (TOP-N) and Top Level Critical L Safety Function (TOP-C) displays previously contained six status bars, one for each.of the six safety functions, Suberiticality '[S), Core Cooling [C), Heat ,
Sink [H).. Integrity [P),-Containment [Z), and Inventory [1]. A status bar for Radioactivity (R) has been added to both the TOP-N and TOP-C displays. This status bar is located at the right of the display, separated from the other six safety function bars. It.is identified underneath with an "R", a solid triangle status indicator, and " RAD". ' Figures I 3 and I-4 show the revised TOP-N AND TOP-C displays, respectively.
All SPDS and ERFDADS displays containing the safety status boxes were also revised to include the Radioactivity [R) status indicator. This status indicator was added in the bottom left section, as a solid triangle to the right of the six safety function boxes with the letter "R" to the right of the triangle. Figure I-5 shows a typical display with the addition of the radioactivity safety status indicator.
THC/SPDS1289.I
- l. : z..'.
- fi E. .
.I, i V
Attactment I r.
sT-E+M
.Page 3 of 3 I n e
E ' Modification to ERFDADS Software for Determination of Radioactivity Status Bar'
. Height and Status Indicator Color-The color of. the radioactivity status triangle and the color and height I of'the status bar are determined in a manner similar to.the NSF-status bars-and colors.- For each of the radiation monitors on'the Radioactivity Status displays, the reading is' compared to predetermined normal, alert, and alarm values-for that monitor,'and a " normalized"~ reading is generated.
The bar' length for the top level radioactivity. status normal safety I e function' is calculated by the sof tware as the largest " normalized" difference of-the radiation monitor value from its predetermined normal value. The color-of the radioactivity status bar and the status triangle changes as a function.
of the highest alarm level-reached by any.of the radiation monitors. ,
Modification to ERFDADS for Continuous Display of Safety Function Status p.
The ERFDADS'has been modified so.that one display CRT, identified as the.
SPDS Dicplay,'can only bring up displays which have the safety function status
-indication as part of the display. Appropriate keyboard modifications were-c i -- also.made as a result of this change (See Attachment 11).
l t
i l~
i
.]
1.
l TIIC/SPDS1289.I
.x ' HA'S CIPY . ~~
- . C..
s ..
.f '. '
I R:0 25 AUG 89 -
~
. l'5"! RADI0 ACTIVITY STATUS. .lR1 **:3y,'L,y, :
UNIT 1 MODE gggggggy, RCB PURGE CR/ ERB YENT SFP EXHRUST H5iK2TiiH51 H5iR5 K G 51 L15iR 5 N G 5]
uti/cc- uCi/cc uCi/cc
l ^l UMIT YENT RCB RTHOSPHERE CMTMT HI RAM 6E z !
(RT-8010) (RT-80114 TNRY tetic) $2 oo I
uti/cc uCi/cc -R/HR o.5 ;
PARTICULATE 9.50E-103 PARTICULATE '9.50E-103 RT-8050 9.50E-1GB 5
- IDDINE 9.50E-103 10BINE 9.50E-tOB RT-8051 9.50E-103 EY NOBLE GA5 9.50E-1GB NOBLE GA5 9.50E-tOB k uCi/sec '
'I RELEASE RATE 9.50E-103 i l
COMD VAC PUMP MRIM STM LINE. SG BLOMBONM (RT-8027) (RT-8946 THRU 8049) (RT-8022 THRV #625) -
uCi/cc uti/cc uCi/cc MOBLE GA5 9.50E-103 SG A 9.50E-103 5G A 9.50E-103 !
UCi/sec OG B 9.50E-tGB SG B 9.50E-tGB y--
RELEASE RATE 9.50E-1GB SG C 9.50E-t93- 5G C 9.50E-1GB 15 0 SG B 9.50E-10B SG B 9.50E-105 N
.E O
S-C.H . P 2Y I: AR 'N
- f: ,,~
e 3,
1 3
a' Attachment I SI-tiL*AE 3320
\ s O
FIGURE I-2 CRAD DISPLAY-J .
. t Om HR gu
.mm m.
e8== ,e m e.
- u. . .
.. Et e.
u_
aa.
. e . sa a.
u.
..m:
=_ m
.5 W W E W W. .5WWWW v
a W - 3w m. m. W W m. m. 3 m. m. m. m. -
' A mm @' mm a mmmm 2:! e--
E =
=
E a,
em E.-
ER E- gg = *3 se E, =g w- .* .-
w
...e..
h i-s=- =. e,
amum m aM W EE M 5 mmmm j
" a se se a en a a a en eo eee eoeo v __ v . l v . . . u . . . u v.- _ .,. ., .,. ~
M *
'O
- O e D- U W eoee p 3 m. W. 3 . m. m. m. W 3 m ... m m m.
q mm y_ mee emem .,
H M H
$5 z 2' wa E
x a. , Y .a Z
~ ~
no nn R- d 8 5 5-
=
w me == uWW H % e e an 3. > = .J m a en zg amum U- m >> vn aCC eg uew. I C w. um ac , m. ~ E m ,- meme O
M mm amm a e a "
, C:s ee eoe uo euo l
c E
u==
v e e u
u 8 4 I
.. s=
bt .
u == = =
u4 Ut t 4 ,
1
.% uW 3e u
l U
W WWWe o.%.o3 .%. e W.%. W e ,. i 3 m. m. 3 m. m. m. U 3 m. W3 m.3 W m. e= l ee mmm
,, m m m E~
' l E
W %
=
g
=
%=
.g-w . e = m = m 1.D - g .J S U S
== J.f v Ch m
N 99
=. w a 3 uW W W m
C a W W m
A C ** *
O f" m ee pS *a s E W G lll> S W G
- lEll a to pg F s== W sm W m
UE z 3
.J .J - ) **
-2 on i i . m a en : m a
[ U 6- M E *- GCC W Cg C W U g . 6g ce: at a :D 5 a. *-= E a v- E m y i.
4
HX'J CCPY ' ~
t 1
R:4 58 SEP 89 -t I?56" . NORMAL SAFETY PARAMETERS '8: 35: zi 1 unit i noBE gggI8 .
gglh
unentns i w -
on a yH l zem '
Um i M ri nonnat 50" rw-
- = ;
S C
H P Z I R
_ i
_ E E E _ E A MSF-5 MSF-C MSF-H MSF-P MSF-2 NSF- RAD
\
RX TRP BRK ' E8 i R S E gg;mwggag,g ,,. .
M E- liGiEI4 FHB ) kRAD EB Ms 4 fi SG LO LC i: : [ABtI'RRD '
IX TRP g:] $g
~
Sv5 8"
': OM t
6
MAIS CCPY - '
I?S' UNIT 1 CRITICAL SAFETY PARAMETERS N:'!I:"I4is AtJM NOBE assassses i
at.nRN
)
I t MnRNING i
O *Ti
,~
. m ;
nc 27 i NORMNt. o svi '
s MM I j
a, F" Sh .
! D S C H P Z I R <
a l
m - ._
a a a A
-. i; I
CSF-5 CSF-C CSF-H CSF-P C5F-Z CSF-I Ras RX TRP BRK g , e Ls= g%,,,,, [ Ell **"NA.MMB 5V5 g'
G:t i I
fi .
'g'
'd fif' !; :
3 J
[ 1. - ( -
._ , CT-HL AE 3320
- s. ,
l FIGURE I-5 -
- TYPICAL MID-LEVEL DISPLAY 1
\
- o. p:e .
.a.
_t;= .o
.e, . .
s..g
- w. .
g
M Eg me m:3 .a
.. g .n s a I . : v
~- .: . .- . l 3
1
= i . . .
'E g ;
=
W e .
4
- . y x
M i
w .s..
W.M E
=#
+
Z
% =. S UdI
=
$z- .
=
. a .=
- l. ,
y .
.. . w#.=
=
s>R.
ow I
kh M
- g 4.
j-j GM
[ . i N,
1 .
b W N
=E wmW N
g gy z
. a.s v- . =
m L'E A ll3 J C b.J g u~5 m t.rs A. >.s:
= H- iJ t: i-g D cn
^1
- ff
+ f , -
t_
p2 % -
o iM ? %, g -;a V
, Attachment II i M. ST-HL-AE 3320 Page 1 of 2 1 E.p ,
g DESCRIPTION OF KEYBOARD MODIFICATIONS ;
?
Keyboard Modifications for. Radioactivity Status Safety Function Displays
.The addition of the. two radioactivity status displays, normal radioactivity status [NRAD) and critical radioactivity status [CRAD),
discuss'ed in Attachment I,-~resulted in modifications to the' keyboards and .!
keypads' associated with the Emergency Response Facilities Data Acquisition and Display System (ERFDADS) cathode ray tubes (CRT).
The function keys on the keyboards and keypads are. closely linked to the: ,
alsplays. The normal safety functions (NSF) and critical safety functions ,
.(CSIT have one-top level display each. The operator.can select the top, level displsy via a single keystroke by pressing the-" TOP" key. The computer .,
selecr.s the NSF or CSF top level display based on the status of the renctor '
trip _1reakers. In a similar-manner, the operator can select the mid level >
1 displeys via a single-keystroke. The function' keys are labeled "S" for'
- .H Suberiticality, "C" for Core Cooling, "H" for Heat Sink, "P" for Integrity, '
"Z"..for Containment, and "I" for Inventory. Again the computer selects the appropriate NSF or CSF display based on the status of the reactor trip 4 breakers. A< seventh mid-level function key, "R" for Radioactivity, has been '
-added to both the keyboards and keypads. This function key allows the .
. operator to call-up the appropriate Radioactivity-Status display by single keystroke. access. 1 The revised keyboard and keypad layouts are sh'own on Figures 11-1 and II-2, respectively.
i The mid-level function key "R" is located on the keyboards to the right of function key "I".. The seven mid-level function keys are located together
.at the top left of the keyboards. 'l .
~
'The mid level function key "R" is located on the keypads to the right of j function key-"I". The seven mid-level function keys are located within the top two rows of the left face of the keypads. -!
Keyboard Modifications for Permanent Display of Safety Status Indication The SPDS has also been modified to permanently display the safety status boxes on one of the SPDS consoles. There are six ERFDADS CRTs in the Control Room (See Figure 11-3). Software and hardware changes have been implemented to allow the continuous display of information from which the safety status of the plant can be assessed. The left ERFDADS CRT located on the front of THC/SPDS1289.II
.n,
2: ,
- 1 eg . - - .
b-ye 4
+
A) .j A
Attachment 11 .
'~
ST*HL M -3320-s Page 2 of 2 :
u)
(':0 10perator. Console CC020 has been designated as-the SPDS Display;and has been.
[ 'restrictedLto access only displays'containing the safety _ status _ indicators. '
f" .These safety status-indicators are- provided in the left bottom corner of each-
[I -display (See Attachment 1). I l 4 Access to this_CRT is'possible via,the two keyboards.provided on the two. <
- consoles . ; Keys:on these keyboards have been color-coded.to show.the-keys that:
are' operational ~when_ accessing this dedicated CRT.
If a display not .
containing the safetycstatus-indicators 11s requested on'this CRT, .the CRT will'- ,
not' respond and will maintain-the current display until:an allowed display ,
~(i . e a , ERFDADS: display containing safety status indicators) is requested'.
I f
b k
?
i k
5 V, '
THC/SPDS1289.II
~
"7' 4
}
{l , ,
7 L > Attachment, II. l t
' ST E-AE-3320 J
/_ / ' , . . ,e*-
L i )
u y . -
go t- :.
t a >
E.'. - .
4_
c b l-I E
s-II s T 8 y y z- pl en E. m-- -
a.
lEl Wa 5"- ** go 5 9
DI y- n t- l
~ s .
2 2: f
~
f e
$ ilt . 2I -- 'N $ E$
EE -$ gb or is
-- x gt se .. -
s
. -s . .
F I. o, K. m ..
$2 E io A e u O "Y
Y W M 8 d w (O r
3 m ' ;p T M E \b
.g Z E uw (D
5
& MT (J
W z == Q em 3
u H D e N N
O e - 4
/
h I E
- y a m oiD-2 5
f i O$5 FIGURE II-l ASCII KEYBOARD
+
-} '
,, t :- 9,l; -i
- At.tCchment II- li BT BL-AE-3320 -1
.,4 -
i e s P 9 % y e.- gg. p. j.
1 w~ 95= [. ir.
a E
a s s 0 0 S % T
W 5 -
i
+
1 9 9 y 71 s
v.
s V.I+ VI
.at s s s
% y y J P 4E . 3-e W
- S.- Ws4 s -
s 9 1 y 1 a . . -
s s
% ! % 1 1 W N 4
E Wd' e
~ f , , - ~
% 9 ? f h% fI !!8 E W~ m W  5 FIGURE II-2 FUNCTION KEYPAD k _
. .,.e Atttchment II
,. ,,- ST-RI.- AE* 3320 m
1 h UNIT - "I CP913
$UPERvl10R5 0F FICg CPOtt CP012 RICORDER PAktL A A CP024 ENGINitRED SAFliY FEATURES y ..g : :
?WifliP4865" (L E CTRIC AL CPB18 AUXILIARY f. . . . .K .V. 8 0. A. .R.DS. .!!. !Di POWER.
- . ".:.: AU Xill ARY CIRCUL ATINI. :: CONSOLE CP90s WATER :: ::::: . CC4lt CP002 Fit 0 WATER &
CP004 -
CONDENSAIt i:i .i:i O!$ PLAY :j f
TURRINE "^-
CP007 GENERATOR ., O PE R A"T' O'R '
- CON 50Lt CCO20 CP801 ii HVAC li CP012 g,,,,- ,
i:r". m. ::
$ TEAM GENERATOR '.......-.:
19" 5P03 :: .
';f::
- :: C,Ris W/F K
/ -
2s]
C,,,, . . . ..
HVAC CP994 CP022 Rt ACTOR CbdTROL CHEMICAL & VOLUME CONTROL SYSTtu l CP014 l
1 l 7 CP011- NUCLE ARINSTR. PANEL @ihs!!!{- CROR EVALUAfl0N ARIA CP012- FLUX MAT'ING CPt15- LOOSE P ART 3 MONITORING CP013. M0710N SE11M:C MONITOR 6NG' CPtit- FIRE PROTECTION PAktL CP014- Vl8AAf t0N M04 10 RIN G A - COMPUTER TYPERS CP022 RA01Atlok MONITORING
- UNIT 1 DNLY FK - F UNCTION KEYBOARD liGURE II-3 CONTROL ROOM LAYOUT t-