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TAC:M95529, TSTF-11, TSTF-12, TSTF-01 (Approved, Closed) TAC:M95530, TSTF-11, TSTF-12, TSTF-01 (Approved, Closed) |
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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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The Light '
cHouston o mpLighting a nySouth& Power Texas Project Electric Generating Station P.O. Box 289 Wadsworth, Texas 77483 February 11,1997 ST-HL-AE-5571 File No.:G20.01,
. G20.02 10 CFR 50.90 STI: 30176464 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 South Texas Project Unit I and Unit 2 Docket Nos. STN 50-498 and 50-499 Supplementary Information re South Texas Proiect Proposed Improved Technical Specifications
Reference:
Letter dated November 27,1996 from William D. Beckner (NRC) to William T.
Cottle (HL&P) entitled " Staff Comments on the South Texas Application for Conversion to the Improved Standard Technical Specifications (TAC Nos.
M95529 and M95530)"
Representatives of the South Texas Project met with the Nuclear Regulatory ( 'ommission staff on December 12,1996 to discuss the review of the South Texas Project proposco Improved Technical Specifications. The meeting was successful in determining a plan for the South Texas Project to supplement the original submittal to facilitate the review and approval by the NRC i staff. Attached to this supplement are the following items, as discussed in the December 12 meeting:
A description of the STP philosophy for adapting the Standard Westinghouse 1.
Improved Technical Specifications (NUREG 1431) to the STP three train //
Engineered Safety Feature configuration.
- 2. A " pilot" revision of the STP Improved Technical Specifications Section 3.5, ECCS, showing changes to address the comments made by the NRC in the
[86/
referenced letter.
9702190266 970211 PDR ADOCK 05000498 P PDR c:\wp\nlinrc-wk\ misc.97\$571. doc Project Manager on Behalf of the Participants in the South Texas Project
t S T-HL-AE-5571 File No.:G20.01, G20.02 Page 2 In support of a planned implementation of the Improved Technical Specifications in the first quarter of 1998, the South Texas Project plans to submit a second, comprehensive supplement by June 30,1997. This comprehensive supplement will address NRC comments and issues identified in the referenced letter and this " pilot" supplement. It will also include the incorporation of amendments to the current technical specifications, a Relocation Matrix describing where information relocated from the technical specifications was placed, a disposition of proposed generic changes (TSTFs), and a list of pending and planned changes to l the STP Technical Specifications. i Following resolution of any remaining NRC comments, STP will submit a certified Proof and Review version of the Improved Technical Specifications targeted to support NRC approval of the proposed amendment by the end of 1997.
If you have any questions, please contact Mr. A. W. Harrison at 512-972-7298 or Mr. M. A. McBurnett at 512-972-7206.
( W '
' Lawerence E. Marti W
General Manager, I
Nuclear Assurance and Licensing AWH/ !
Attachments:
- 1. South Texas Project Philosophy for Incorporating Three Train Design into Improved Technical Specifications
- 2. Proposed Revisions to STP Improved Technical Specifications Section 3.5, ECCS 4
c:\wpW\nrc.uk\ misc-975571. doc
Houston Lighting & Power Company ST-HL-AE-5571 South Texas Project Electric Generating Station File No.: G20.01 G20.02 Page 3 Leonard J. Callan Rufus S. Scott Regional Administrator, Region IV Associate General Counsel U. S. Nuclear Regulatory Commission Houston Lighting & Power Company 611 Ryan Plaza Drive, Suite 400 P. O. Box 61%7 Arlington, TX 76011-8064 Houston, TX 77208 Thomas W. Alexion Institute of Nuclear Power Project Manager, Mail Code 13H3 Operations - Records Center U. S. Nuclear Regulatory Commission 700 Galleria Parkway Washington, DC 20555-0001 Atlanta, GA 30339-5957 David P. Loveless Dr. Bertram Wolfe Sr. Resident Inspector 15453 Via Vaquero c/o U. S. Nuclear Regulatory Comm. Monte Sereno, CA 95030 P. O. Box 910 Bay City, TX 77404-0910 Richard A. Ratliff Bureau of Radiation Control J. R. Newman, Esquire Texas Depanment of Health
. Morgan, Lewis & Bockius 1100 West 49th Street 1800 M Street, N.W. Austin, TX 78756-3189 Washington, DC 20036-5869 J. R. Egan, Esquire M. T. Hardt/W. C. Gunst Egan & Associates, P.C.
City Public Service 2300 N Street, N.W.
P. O. Box 1771 Washington, D.C. 20037 San Antonio, TX 78296 J. C. Lanier/M. B. Lee *U. S. Nuclear Regulatory Commission City of Austin . Attention: Document Control Desk Electric Utility Department Washington, D.C. 20555-0001 721 Banon Springs Road Austin, TX 78704 Central Power and Light Company J. W. Beck l ATTN: G. E. Vaughn/C. A. Johnson Little Harbor Consultants, Inc.
P. O. Box 289, Mail Code: N5012 44 Nichols Road Wadswonh, TX 77483 Cohassett, MA 02025-1166
- Above copies distributed without Attachments, except as noted by asterisk.
l ST-HL-AE-5571 Attachment 1 j Page1 l South Texas Project Philosophy for Incorporating Three Train Design into Improved ,
Technical Specifications The Standard Improved Technical Specifications were written for standard plants with !
two trains of Engineered Safety Feature (ESF) equipment. For such standard plant designs, the !
I safety functions are degraded (loss of single failure protection) when a single train of an ESF function is inoperable, and there is a loss of safety function when two trains of an ESF function are inoperable. Consequently, there is generally no allowed outage tirre in the standard technical ;
specifications for situations where two trains of an ESF function are inoperable.
l The South Texas Project has three trains of ESF equipment and ESF support equipment.
STP does not experience a complete loss of safety function when two of three trains of an ESF l function are inoperable. The three train design basis is predicated on each train being capable of mitigating a design basis accident assuming a loss of off-site power and single failure. In almost all cases, the safety systems powered from any one of the three available trains of onsite AC power are capable of mitigating the consequences of design basis events. For a very few cases, !
proper and timely operator actions would be required to assure that selected safety systems :
performed their function. In the event two of the three trains are unavailable, with no accident ;
considerations, safe shutdown can be achieved with any single train. When two of three ESF l trains are operable, STP retains a high degree of redundancy which is substantially greater than !
that which forms the basis for standard two train technical specifications for conditions where one of two ESF trains are available. Thus it is appropriate for STP to have a reasonable allowed )
outage time for conditions where two of three trains are inoperable in addition to the current allowances for when one of three trains is inoperable. The limitations of the STP three train design were more fully described in letters dated January 4,1996 and January 23,1996 in support of the STP application to amend the STP Technical Specifications to extend the allowed outage times for the Standby Diesel Generators and supporting systems. The amendment was approved by the NRC in Amendments 85 & 72 to the STP license.
1 Generally, the conversion of a two train Standard Improved Technical Specifications to Improved Technical Specifications suitable for a three train plant involves application of the three concepts described below. These concepts are generally applied throughout the South Texas ITS submittal with some adjustment for specific system designs and redundancies. In each case, the deterministic conclusion is tested with the Probabilistic Safety Assessment (PSA) to account for integrated effects and to ensure there is appropriate probabilistic justification.
l l
ST-HL-AE-5571 Attachment 1 Page 2 Concepts for Converting Two Train Technical Specifications to Three Train Technical Specifications:
- 1. Two train specifications have action statements that cover the progression from all trains available to no trains available. To convert froia two train specifications to three train specifications, it is necessary to add action statements to cover the progression from three trains available to no trains available.
- 2. The three train plant has substantially more capability to mitigate design basis i events (including single failures) with one train out of service as compared to a i two train plant which has lost capability to mitigate design basis events with one l train out of service and a single failure. The allowed outage times (AOTs) associated with the loss of one train are increased based on the additional capability.
- 3. The three train plant has capability to mitigate most design basis events without a single failure if two trains are out of service where the two train plant has no capability with two trains out of service. This additional capability warrants provision of short AOTs in lieu ofimmediate shutdown requirements.
Consequently, AOTs are provided for two trains out of service.
STP has structured its application for Improved Technical Specifications to incorporate the three train design concepts described above. Table 1 below outlines the comparison between the philosophy of a typical two train plant and a three train plant such as STP. The time allowed to be in a condition with less than three trains operable is based on a reasonable time to restore operability and the capability of the remaining operable equipment. The proposed Improved Technical Specifications implicitly recognize the very low likelihood oflimiting events mentioned above in that the three train allowed outage time for most situations with one train i
operable is relatively short when compared to two train plants with one train operable (i.e. 24 !
hours vs. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />). In addition, the STP Probabilistic Safety Assessment (PSA) shows that the risk incurred is acceptable and consistent with guidance contained in the NEI PSA Application Guide. It is also important to note that two of three trains inoperable would be an unexpected, involuntary condition since STP would not plan to remove two trains from service. (A detailed discussion of the application of the STP PSA for establishing a technical basis for extended allowed outage times in the STP Improved Technical Specifications is provided in the Topical Report that accompanied the original STP application for the Improved Technical Specifications.)
l
, ST-HL-AE-5571 Attachment 1 Page 3 1
Table 1 No Operable Train One Operable Two Operable Three Operable Train Trains Trains Two No capability Loss of redundancy to Full Design Basis NA Train mitigate single failure Redundancy Plant Standard Tech. Spec.
(STSW 2 (typ. 72 TS 3.0.3 or hr.) ' Unlimited operation equivalent STP No capability Loss of redundancy to Redundancy for most Full Design Basis mitigate single failure design basis events Redundancy and loss of capability to mitigate cenain very low probability design basis events 7 days (typ. with some 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (typ. with exceptions; e.g.
l TS 3.0.3 or equivalent some exceptions) SDG I4 days) (Jnlimited Operation Table 2 below describes the changes to the alloweu v.itage times that are being proposed in the STP Improved Technical Specification submittal. The values in bolditalics denote proposed changes to the current technical specification requirements. The Auxiliary Feed Water System (AFW)is included for completeness, although it is a four train system at STP, The general philosophy is still applicable since AFW is usually a three train system at a " standard" plant. It can be seen that the philosophy described for Table I has been incorporated in the proposed changes. In some cases, the proposed changes are more restrictive than the current Technical Specifications, which reflects the incorporation of risk informed elements used to develop the technical basis for the proposed allowed outage times. (Note that Table 2 is for illustrative purposes and does not include all the detail of the requirements of the specifications.)
, ST-HL-AE-5571 ;
Attachment 1 l Page 4 1
Table 2 System / Condition Proposed STP Current STP Standard Two Three Train Three Train Train Specification Specification Specification l Safety injection (ITS 3.5.2) (CTf,3.5.2) (STS 3.5.2) l 0 Trains Operable TS 3.0.3 TS 3.0..'. TS 3.0.3 l
1 Train Operable 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> TS 3.0.3 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> i l 2 Trains Operaole 7 days 7 days unlimited I 3 Trains Operable unlimited unlimited NA 1 j Containment Spray (ITS 3.6.6) (CTS 3.6.2) f 3STS 3.6.6A) 0 Trains Operable TS 3.0.3 TS 3.0.3 TS 3.0.3 1 Train Operable 24 houn' TS 3.0.3 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 2 Trains Operable 28 days # 7 days unlimited 3 Trains Operable unlimited unlimited NA 4
RHR(not actually an ECCS at (ITS 3.5.2) (CTS 3.5.6) (STS 3.5.2, treated as STP) ECCS) 0 Trains Operable immediatel immediately TS 3.0.3 1 Train Operable 24 houn' y 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> l 2 Trains Operable 14 days # 7 days unlimited I 3 Trains Operable unlimited unlimited NA Reactor Containment Fan (ITS 3.6.6) (CTS 3.6.2.3) (STS 3.6.6A) l l Coolers 4
0 Trains Operable TS 3.0.3 TS 3.0.3 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> t
1 Train Operable 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />' TS 3.0.3 7 days l 2 Trains Operable 28 days # 7 days unlimited 4 3 Trains Operable unlimited unlimited NA Component Cooling Water: (ITS 3.7.7) (CTS 3.7.3) (STS 3.7.7) 0 Traira Operable TS 3.0.3 TS 3.0.3 TS 3.0.'
s 1 Train Operable 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> TS 3.0.3 72 hou.a 2 Trains Operable 14 days # 7 days unlim!.ed 3 Trains Operable unlimited unlimited NA Essential Cooling Water: (ITS 3.7.8) (CTS 3.7.4) (STS 3.7.8) 0 Trains Operable TS 3.0.3 TS 3.0.3 TS 3.0.3 1 Train Operable 24 Aours TS 3.0.3 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 2 Trains Operable 7 days 7 days unlimited 3 Trains Operable unlimited unlimited NA
\
, ST-HL-AE-5571 Attachment 1 l l
Page 5 ;
l l
1 System / Condition Proposed STP Current STP Standard Two Three Train Three Train Train l Specification Specification Specification Essential Chilled Water: (ITS 3.7.10) (CTS 3.7.14) (STS no spec) 1 l
0 Trains Operable TS 3.0.3 TS 3.0.3 j 1 Train Operable 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br /> TS 3.0.3 2 Trains Operable 7 days 7 days 3 Trains Operable unlimited unlimited Standby Diesel Generators: (ITS 3.8.1) (CTS 3.8.1) (STS 3.8.1) 0 Trains Operable 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 1 Train Operable 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 1 Train Inoperable with inoperable component on 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />
- 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> another train 2 Trains Operable 14 days
- 14 days unlimited 3 Trains Operable unlimited unlimited NA
- ITS submittal will be revised to reflect the new CTS time.
Control Room Envelope IIVAC (ITS 3.7.11) (CTS 3.7.7) (STS 3.7.10)
(MODE l-4) 0 Trains Operable TS 3.0.3 TS 3.0.3 TS 3.0.3 1 Train Operable 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 7 days 2 Trains Operable 7 days 7 days unlimited 3 Trains Operable unlimited unlimited NA Auxiliary Feed Water (ITS 3.7.5) (CTS 3.7.1.2) (STS 3.7.5) 0 Trains Operable immediately immediately immediately 1 Train Operable 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 2 Trains Operable 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />' 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />
- 3 Trains Operable 7 days 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> unlimited 4 Trains Operable unlimited unlimited NA (no distinction between
- 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> if the combination
- 7 days if the steam supply motor driven and turbine includes the A train motor to the turbine driven train is driven trains) driven AFW inoperable Note 1: T he proposed S I P 11 S currently show 7 days for i tram operable, which is a risk-informed time. STP expects to change the proposed time to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> tc be consistent with the required actions of Specification 3.8.1 for one diesel inoperable with an inoperable component on another train. The planned change to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> is for consistency and is not due to insights from a risk-informed review Note 2: These extended times for two operable trains reflect STP specific capabilities, redundancy. and PSA insig; hts.
. ST-HL-AE-5571 Attachment 1 Page 6 Staggered Test Basis:
The South Texas Project (STP) also requires adjustment in the intervals for staggered testing to accommodate the surveillance testing of three Engineered Safety Feature (ESF) trains instead of the standard two ESF trains. Two safety train plants can use a nine week rolling schedule to perform the required maintenance and testing. However, to manage the three safety train design, STP uses a rolling 12 week maintenance and testing program to facilitate safe and effective plant operation. The surveillance testing intervals specified in the Standard Improved
- Technical Specifications were formulated for a two safety train design with a nine week rolling schedule; however an adjustment is necessary to accommodate the three safety train design, twelve week rolling schedule used at STP.
STP has three ESF trains (described here as Trains A, B, and C) and a " fourth train" (Train D) comprised of safety related components such as Reactor Protection System and
. Engineered Safety Feature actuation logics. The twelve week rolling schedule is the method STP uses to anow the performance of all preventive maintenance and surveillance testing. This
- twelve week schedule is one of the primary administrative controls that prevents planned cross-train events and organizes work into a logical, planned configuration. Each week of the schedule is designated for a specific train, (e.g. week 1-Train A, week 2-Train B, week 3-Train C, week 4-Train D, week 5-Train A, week 6-Train B, etc). The table on the following page provides an i!!ustration of twelve week schedule being used to stagger the three component system. i i
The definition in the current Technical Specifications provides enough flexibility to adapt !
to the three safety train design, while the definition in the Improved Standard Technical Specifications (ISTS) does not provide that flexibility. The ISTS definition of A STAGGERED TEST BASIS states it shall consist of the testing of one of the systems, subsystems, channels, or
- other designated components during the interval specified by the Surveillance Frequency, so that all systems, subsystems, channels, or other designated components are tested during n Surveillance Frequency intervals, where n is the total number of systems, subsystems, channels, !
or other designated components in the associated function. While this definition coupled with !
the surveillance intervals found in the Standard Improved Technical Specification will work for l a two safety train plant, the surveillance intervals found in the Standard Improved Technical Specification would require STP to perform surveillance testing on one train during the week another train is scheduled to be out of sersice for maintenance. Based on this design difference, STP will be requesting stagger intervals that differ from the Standard Improved Technical Specification stagger intervals to allow the testing of staggeted components within the normal scheduled train week and prevent any cross-train surveillance testing. The small change in the stagger interval will not impact the stagger testing benefit.
~ - _ -. _ _ _ __ _ __ _ _ _ _ _ _ _ _
I*.
, ST-HL-AE-5571 Attachment 1 i Page 7 l As the table shows, a standard plant design typically has two safety trains (A and B), and a .nird " train" (C) of other components which must be tested. Surveillance testing is performed l for all components, (two, three or four trains) on a nine week nominal 28 day cycle between
! tests, thereby complying with a 31 day frequency used in ITS for any three train equipment that requires staggered testing. However, as the table also shows, the STP design of three safety train j plant requires performance of surveillance testing on a twelve week, nominal 35 day cycle l
between tests to accommodate the fourth train ofinstrumentation and equipment.
l STAGGERED TESTING FOR A TWO TRAIN PLANT WEEK 1 2 3 4 5 6 7 8 9 10 11 12 1 TRAIN A B C A B C A B C A B C A TEST X X X X l---- 28 DAYS ----l---- 28 DAYS ----l----28 DAYS ------l STAGGERED TESTING FOR A THREE TRAIN PLANT J WEEK 1 2 3 4 5 6 7 8 9 10 11 12 1 TRAIN A B C D A B C D A B C D A l l
l TEST X X X X l-------- 3 5 DAYS -------l----- 3 5 DAYS -------l-l 4 DAYS-l l l
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1
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ST-HL-AE-5571 !
ATTACHMENT 2 STP IMPROVED TECHNICAL SPECIFICATIONS SUPPLEMENT FOR SECTION 3.5, ECCS l The attached supplement for STP ITS Section 3.5 consists of the following information: !
! 1. ITS SUPPLEMENT
SUMMARY
SHEET l l
Provides summary information about the changes made to the submittal. The data is listed i under headings that are self explanatory.
- 2. STP CTS /ITS CROSS REFERENCE Provides a cross reference between the current technical specification and the ITS. The data is listed under headings that are self explanatory.
- 3. ITS SUBMITTAL SUPPLEMENT The ITS submittal supplement consists of the following elements:
- a. Improved Technical Specifications (ITS)
- b. ITS Bases
- c. CTS Markup and Discussion of Change (DOC)
- d. No Significant Hazards Considerations
- c. NUREG Markup (Speci,ications and Bases) and Justification for Deviations (JFDs)
Each of these elements are changed as necessary to implement NRC guidance. Each change is made to allow a quick review of only those elements that have changed. For ITS non-markup elements (a,b, & d), changes are provided in a strike through (e.g.,
di: $ ce;;h) and underline (e.g., underline) format. The strike through shows deletions from the submittal and underline shows additions to the submittal. Revision bars are provided to help reviewers in locating the changes as easily as possible.
For the markup elements (c & e) of the ITS submittal, changes are shown with bold markings and revision bars.
Furthermore pages with revision bars are pink for quick identification of changes.
This also allows the reviewer to place these pages into their submittal copy to assist in their previous review efforts.
l
. . -- .- -- . - _ - . . . - _ = _ . - - -_-. -.
l l
ITS SUPPLEMENT
SUMMARY
SHEET i
, SECTION:
3.5 l CHAMES T/' SPECIFICATIONS:
- DESIGNATOR: ' CHANGE DESCRIPTION: , I SR 3.5.1.5 Changed pressure from 1000 to 2000 psig for verify power is removed l
'from accumulator isolation valve operator. )
- ;3.5.2 Actions' Removed requirement to enter LC0 3.0.3 to match requirements in 'CTSi
~
l E&F and NUREG. I SR 3.5.2.2 Changed SR Frequency frt 2 to 31 days to match CTS and NUREG.
iSR 3.5.3.1 'Added wofds to note-in SR to match NUREG.
SR 3.5.3.2 Changed s to < to match CTS for temperature requirements for HHSI pump breaker alignment in MODE 4.
CHAMES TO BASES:
i DESIGNATOR CHANGE DESCRIPTION-3.5.1 Changes made to incorporate changes to the specs.
- 3.5.2 Changes-inade to' correct wording problem with PSA description.
] ;0ther changes made to' incorporate changes ~to'the' specs'..
3.5.3 Alternate method provided in LC0 section for isolating a HHSI pump from the RCS when filling the accumulators. Other changes made to 4 incorporate changes to the specs.
- 3.5.4l Minor l changes GENERIC CHAMES INVOLVED
- l TSTF 1 ' STATUS- ComENT 90 R.1 TSTF to revise Not incorporated i CHAMES TO CTS:
DOC COMENT' 4 3.5.1 Changes made to incorporate changes to the specs or to match the I specs.
- 3.5.2 - Changes.made
- to incorporate changes _to the. specs.
3.5.3 Changes made to incorporate changes to the specs or to match the specs.
3.5.4 . Changes made'to. match the specs.
Page 1 of 2
ITS SUPPLEMENT SUMARY SHEET SECTIM:
i3.5:
CHAMES TO DCCs:
DOC . COMENT , ,
A.2,3,4,5,7,8, Modified 10,11,12,15 and 16
' A.6 - :Dsleted A.13 Deleted. Note deleted that allowed flexibility for RHR operating when needed for ECCS because it did not apply to STP design.
~' ~
LM.1L&l3l l lMo'dified ,,
M.2 Deleted
'Lil2i4,6,7,9,'Modifie'd'
~
110 & 11 L.8 Deleted i Li12.13,14;15b fNew- ,
~~ & :16 I LA.1,4,5,6,7 & Modified 8
LLA.2'& 3' Deleted ARC CMCERNS:
.NRC' CONCERN RESOLUTION
' Change in Note to SR 3.5.3.1 to This Note has been deleted due to; operations
-take credit for RHR HX for ECCS comment.
purposes when RHR is in RHR mode was not an A change since it was not in the CTS.
- DOCS do not explain removing 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.iAdded more' description in D00 L.9' allowance infCTS for HHSI pump
' breaker' rack in.
BEnnt7 SC@E ISSUES:
iSee 3.5.2 Actions.E & F.above iSee SR'3.5'.2.2~above'
~;See SR 3.5.3.1 above Page 2 of 2
STP CTS /ITS CROSS REFERENCE' 31-Jan-97 CIS CTS TYPE CTS CTS COMMENTS ITS ITS TYPE ITS ITS COMMENTS ,
SECTION PAR SECTION PAR 3.5.1 ACTION a 3.5.1 CONDmON B 3.5.1 ACTION a 3.5.1 CONDmON C '
3.5.1 ACTION b 3.5.1 CONDmON B 3.5.1 ACTION b 3.5.1 CONDITION C ,
3.5.1 ACTION c 3.5.1 CONDmON A 3.5.1 ACTION c 3.5.1 CONDITION C.
3.5.1 LCO 3.5.1 LCO 3.5.1 LCO a 3.5.1.1 SR 3.5.1 LCO a 3.5.1.5 SR 3.5.1 LCO b 3.5.1.2 SR 3.5.1 LCO c 3.5.1.4 SR 3.5.1 LCO d 3.5.1.3 SR l
3.5.1 N/A N/A 3.5.1 CONDmON D 3.5.2 ACTION a 3.5.2 CONDmON E 3.5.2 ACTION a 3.5.2 CONDmON B 1 .
i
[
CTS CTS TYPE CIS CTS COMMENTS ITS ITS TYPE ITS TIS COMMENT 3 SECTION PAR SECTION PAR 3.5.2 ACTION a MOVED TO BASES 3.5.2 N/A N/A 3.5.2 ACTION b MOVED - 10 CFR 50.73 3.5 N/A N/A (aX2Xiv) 3.5.2 LCO 3.5.2 LCO 3.5.2 LCO a MOVED TO BASES 3.5 N/A N/A 3.5.2 LCO b MOVED TO BASES 3.5 N/A N/A 3.5.2 LCO c MOVED TO BASES 3.5.2 N/A N/A 3.5.2 LCO d MOVED TO BASES 3.5 N/A N/A 3.5.2 N/A N/A 3.5.2 CONDmON F 3.5.2 N/A N/A 3.5.2 CONDmON D 3.5.2 N/A N/A 3.5.2 CONDmON E 3.5.2 NOTE APP MODIFIED 3.5.2 NOTE APP 3.5.3.1 ACTION a 3.5.3 CONDmON C 3.5.3.1 ACTION a 3.5.3 CONDmON A 3.5.3.1 ACTION b 3.5.3 CONDmON C 3.5.3.1 ACTION b 3.5.3 CONDmON B 3.5.3.1 ACTION c MOVED - 10 CFR 50.73 3.5 N/A N/A (aX2Xiv) 2
t i
s C13 CTS TYPE Cb CTS COMMENTS ITS ITS TYPE ITS ITS COMMENTS SECTION PAR SECTION PAR i
3.53.1 LCO 3.53 LCO 1 3.53.1 LCO a MOVED'ID BASES 3.5 N/A N/A 3.53.1 LCO b MOVED TD BASES 3.5 N/A N/A 3.53.1 LCO c MOVED TO BASES 3.5 N/A N/A 3.53.1 LCO NOTE 3.53 LCO NOTE i
3.53.1 LCO NOTE 3.53 LCO NOTE ,
3.5.3.2 LCO MOVED TD SECTION 3.4 3.5.4 LCO NOT USED 3.5.5 ACTION 3.5.4 CONDITION C 3.5.5 ACTION 3.5.4 CONDITION B 3.5.5 LCO 3.5.4 LCO
.4.5.5 LCO a 3.5.4.1 SR 3.5.5 LCO b 3.5.4.2 SR 3.5.5 N/A N/A 3.5.4 CONDITION A ,
3.5.6 ACrlON a 3.5.2 CONDITION E
~
3.5.6 ACTION a 3.5.2 CONDITION A 3.5.6 ACTION b 3.5.2 CONDITION E
. - . . . = _ . _ - . _ . - . . - . . - . . . . .- .. - .
CTS CTS TYPE CTS CTS COMMENTS ITS ITS TYPE I13 15 COMMENTS SECTION PAR PAR SECTI.]i 3.5.6 ACTION b 3.5.2 CONDITION C 3.5.6 A CI'lO N c 3.5.2 CONDITION G 3.5.6 LCO 3.5.2 LCO 3.5.6 LCO a MOVED TO BASES 3.0.2 N/A N/A 3.5.6 LCO b MOVED TD BASES 3.5.2 N/A N/A 3.5.6 LCO c MOVED TD BASES 3.5.2 N/A N/A 3/4.5.1 LCO ACCUMULATORS 3.5.1 LCO Accumulators 3/4.5.2 SR ECCS SUBSYSTEMS - 3.5.2 LCO ECCS - Operating Tavg > OR EQUAL TO 350 i degrees F 3/4.5.3 LCO 3.5.3 LCO ECCS - Shutdown i 3/4.5.5 LCO REFUELING WATER 3.5.4 LCO Refueling Water Storage Tank (RWST)
S1DRAGE TANK 4.5.1.1 SR a.1 35.1.3 SR 4.5.1.1 SR a.1 3.5.1.2 SR 4.5.1.1 SR a.2 3.5.1.1 SR 4.5.1.1 SR b 3.5.1.4 SR 4.5.1.1 SR c 3.5.1.5 SR ;
4.5.1.1 SR d.1 DELEIED 3.5 N/A N/A !
4 i
CTS- CIS TYPE CTS CTS COMMENu .ITS ITS TYPE ITS ITS COMMENU SECrlON PAR SECTION PAR 4.5.1.1 SR d.2 DELETED 3.5 N/A N/A 4.5.1.2 SR a DELETED 3.5 N/A N/A 4.5.1.2 SR b DELETED 3.5 N/A N/A 4.5.2 SR a DELETED 3.5 N/A N/A 4.5.2 SR b.I 3.5.2.2 SR 4.5.2 SR b.2 3.5.2.1 SR 4.5.2 SR c.1 DELETED 3.5 N/A N/A 4.5.2 SR c.2 DELETED 3.5 N/A N/A 4.5.2 SR d 3.5.2.6 SR 4.5.2 SR e.1 3.5.2.4 SR 4.5.2 SR e.2.a 3.5.2.5 SR 4.5.2 SR e.2.b 3.5.2.5 SR 4.5.2 SR f 3.5.2.3 SR 4.5.2 SR f.1 MOVED TO IST 3.5 N/A N/A PROGRAM ;
4.5.2 SR f.2 MOVED TO IST 3.5 N/A N/A PROGRAM ;
4.5.2 SR g.1 DELETIu> 3.5 N/A N/A ,
w 5
. . . ... . .- -.. ~..... -.. .-- .. - .- - .. - ..~ ..- - . .. .. .. . . . . . . . . - .. - . . . . - . - , - . ..
4 I r
CTS CTS TYPE CTS CTS COMMENTS ITS ITSTYPE ITS . I13 COMMENTS !
SEC110N PAR SECTION PAR i
4.5.2 SR g.2 DELETED 3.5 N/A N/A '
4.53.1.1 SR 3.5.3.1 SR i
4.53.1.2 SR 3.53 LCO NOTE ;
4.53.1.2 SR 3.5.3.2 SR 4.53.1.2 SR NOTE 3.53 LCO NOTE 433 SR a 33.4.1 SR ;
1 4.5.5 SR b 3.5.4.2 SR 4.5.6.1 SR 3.5.23 SR 1
4.5.6.2 SR 3.4.15.2 SR i
i t
i 3
9 R
F 6
1 e
_ _ _ , _ . -. . , _ . _ - - . , _ _ , .m_, _. . -..-. . . _ _ _ . . _ .
- , _ >: