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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
[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
r-The Light NE f Ifouston 1.ighting & Power P.O. Ika 1700 Ilouston, 'Icxas e dH)I (713) 228-921I June 17 1986 ST-HL-A$-1684 File No.: G9.18/C36.04 Mr. Vincent S. Noonan, Project Director PWR Project Directorate #5 U. S. Nuclear Regulatory Commission Washington, DC 20555 South Texas Project Units 1 and 2 Docket Nos. STN 50-498, STN 50-499 Response To Safety Evaluation Report, NUREG-0781 Open Item #2 Internal Missile Analysis
Dear Mr. Noonan:
Attached are annotated changes to the South Texas Project (STP) Final Safety Analysis Report (FSAR) Section 3.5 and responses to NRC Questions which provide the results of the internal missile analysis / evaluations for the STP.
l These changes are being submitted in response to the Safety Evaluation Report (SER), NUREG-0781 open item number 2 (Table 1.1-4 of the SER).
As a result of the analysis, no modifications to the plant design were required.
If you should hav+ .ny questions on this matter, please contact Mr. M. E. Powell at ',71 ; ) 993-1328.
Very truly yours, M. R. Wi n g Manager,1(uclearLi ns ng MEP/yd
Attachment:
Annotated FSAR Pages to Section 3.5 8606230128 860617 PDR ADOCK 00000498 0 E
Ll/NRC/fr PDR -
i t i
flouston Lighting & Power Company ST-HL-AE-1684 File No.: G9.18/C36.04 Page 2 cc:
Hugh L. Thompson, Jr. , Director Brian E. Berwick, Esquire Division of PWR Licensing - A Assistant Attorney General for Office of Nuclear Reactor Regulation the State of Texas U.S. Nuclear Regulatory Commission P.O. Box 12548, Capitol Station Washington, DC 20555 Austin, TX 78711 Robert D. Martin Lanny A. Sinkin Regional Administrator, Region IV Christic Institute Nuclear Regulatory Commission 1324 North Capitol Street 611 Ryan Plaza Drive, Suite 1000 Washington, D.C. 20002 Arlington, TX 76011 Oreste R. Pirfo, Esquire N. Prasad Kadambi, Project Manager Hearing Attorney U.S. Nuclear Regulatory Commission Office of the Executive Legal Director 7920 Norfolk Avenue U.S. Nuclear Regulatory Commission Bethesda, MD 20814 Washington, DC 20555 Claude E. Johnson Charles Bechhoefer, Esquire Senior Resident Inspector /STP Chairman, Atomic Safety &
c/o U.S. Nuclear Regulatory Licensing Board Commission U.S. Nuclear Regulatory Commission P.O. Box 910 Washington, DC 20555 Bay City, TX 77414 Dr. James C. Lamb, III M.D. Schwarz, Jr., Esquire 313 Woodhaven Road Baker & Botts Chapel Hill, NC 27514 One Shell Plaza Houston, TX 77002 Judge Frederick J. Shon Atomic Safety and Licensing Board J.R. Newman, Esquire U.S. Nuclear Regulatory Commission Newman & Holtzinger, P.C. Washington, DC 20555 1615 L Street, N.W.
Washington, DC 20036 Citizens for Equitable Utilities, Inc, c/o Ms. Peggy Buchorn Director, Office of Inspection Route 1, Box 1684 and Enforcement Brazoria, TX 77422 U.S. Nuclear Regulatory Commission Washington, DC 20555 Docketing & Service Section Office of the Secretary T.V. Shockley/R.L. Range U.S. Nuclear Regulatory Commission Central Power & Light Company Washington, DC 20555 P.O. Box 2121 (3 Copies)
Corpus Christi, TX 78403 Advisory Committee on Reactor Safeguards H.L. Peterson/G. Pokorny U.S. Nuclear Regulatory Commission City of Austin 1717 H Street l P.O. Box 1088 Washington, DC 20555 l Austin, TX 78767 l 1
J.B. Poston/A. vonRosenberg City Public Service Board P.O. Box 1771 San Antonio, TX 78296 Ll/NRC/fr Revised 5/22/86
3.5 MISSILE PROTECTION
- This section describes the missile protection design bases for Seismic Cate-I gory I structures, systems, and components. Seismic Category I structures, systems, and components and their safety classifications are identified in Section 3.2. Missiles considered are those which could result from: a plant-related failure / incident, including failures within and outside of the Reactor Containment Building (RCB), environmentally generated missiles, and site proximity missiles. Included in this section are descriptions of the structures, shields, and barriers which are designed to withstand missile
} effects, the possible missile loadings, and the procedures by which each
- barrier is designed to resist missile impact.
To reduce the probability of unacceptable consequences related to missile 36 impact, key backup and/or redundant components and systems have been physi-cally separated and shielded so that a single missile is incapable of negating the redundant functions. In addition, essentially all Seismic Category I components are housed in Seismic Category I structures or analysis is 36
! performed to demonstrate that external missiles have an acceptably low proba-
) bility of striking them.
The following criteria were adopted for assessing the plant's capability to withstand the missiles postulated in Sections 3.5.1.1 and 3.5.1.2:
- 1. No perforation of the RCB (i.e., no loss of leaktightness) 4kue. uk
- 2. Assurance that the plant cangbe maintained-in-a safe shutdown condition Win coald 3
( 3. Offsite exposure vithin 10CFR100 guidelines for missile damagegresult 6es.
in activity release
- 3.5.1 Missile Selection and Description Wherever possible, component and system design precludes the generation of l
missiles. This is achieved by suitable choice of materials, use of normal and l
faulted stress levels, and system and component characteristics which avoid For exam
- b ""* issi(egrguj[ingeffectsevenungr,faultedconditions.adeptses fe*alissDes he precluded b
- h,with bk f'*valves Wherever possible, systems and componeq,t,s i n ified as potential missile sources are arranged end eri;;;:' so tNe3 m ss e would impact on am-;;i;;i g structure or component capable of withstanding the impact. S.;;; : criti- '
..... : ' rinik ee..;e she.. . .. ..... ..y.... 7..,----- -
r-- ; -- -- 36 p ;;f' ' by ::h ;;;ing :: ::::i:: ing ith:: c'- 0:rg:: :: th: ;i;;il; : _:;;; '
Ba e s are provided for missiles which cannot be orie g take advantage o structures and which could cause failure o a ety'-related struc-tures or compon ese bar rs d i d to contain or deflect the missiles from t ety-relate .E: y es gne: : -without generating any secondary missiles. 36 Wherever possible. :d:::::g: i: ::h:2 cf ::11; :: ;;;.;;.:;; :: icing f r-
> . . a a . a .. . .
s... . , a . , .....a --.... .g ..-.>2....> -. t
,.u.. a..a,.~.ni Q T[ T , M f.' % - "ts % 6' L ,2 Q s d O
~
1;;;;;~ C .'3 21.4- .Z l ,
g awk irNr skyscNd(.frev is rneit ohw' hs.+. cad vup M.-e M M seyarate e.nednal cowyone.ks fp> yobft;al vnM\c so w t.es.
3.5-1 Amendment 36
l ['
u, u
~ A ]% CMode STP FSAR %M NA%f'S N y
Vor scdthUdaM _
. . , y -
c.o9esh ,
s Table 3.5-2 lists and describes the barriers utilized for missile protection.
~
3.5.1.1 Internally Generated Missiles outside the containment. Seismic Category I structures, systems, and components outside the Containment whose failure could result in radiological consequences in excess of 10CFR100 guidelines or which are required for attaining and maintaining a safe shutdown during normal or accident conditions are listed in Table 3.5-1.Y External missile protection provisions anc roterences to applicante system descriptions and drawings that demonstrate separation and independence are listed in Table 53 3.5-1. !niti:*'{nternalmissileprotectionAp;;cizi:2 are indicated in Table 3.5-1. Tinel intun 1-missi4+-design-proteeti n p;ccici:::, 1.-1 Ming -
Wi-it-reconciliatim. -ill h pravid d in T61: 3.5-1 prier te f= 1 1;;i Vretea m repch ah hon ink M minilc- tourted arc describui below
- etential-sources-of-miss11 s ase+ ON McWiM PhnM MMMc souytcM f Coer vA er/ a.s c 14c6 are c;the- 1 o High-pressure systems se.wvahtd SA W fc. Ateck C omPenenh N e Rotating machinery CM) or hW%NA MO N 6 N Ynd IocMel wt h %e.sh doyca Wh:nk e Gravitational missiles houw.sait og $hs or -theq Yl36 k ^ Y' "- I" E - I e cenp e nek ec.r/ cd:du5 Systems outside the ontainment were reviewed to determine sources of q211.1 missiles.4The results of this review are discussed in the following section.
ggg 3.5.1.1.1 High-Pressure Systems: Valve bonnets and stems,and thermo-wells'are the potential missiles associated with high-pressure systems outside l36 the Containment.
Temperature or other detectors installed on piping or in wells are evaluated as potential missiles if a failure of a single circumferential weld would cause their ejection. This is highly improbable, since a complete and sudden failure of a circumferential veld is needed for a detector to become a 36 missile. In addition, because of the spatial separation of redundant refe-l ty-related equipment, a small missile such as a detector, assuming the circum-j ferential weld fails completely, is not likely to hit redundant safety-related equipment.
Two types of valve components, valve stems and valve bonnets, are potential missiles. Valves in high-pressure systems have bsen reviewed as potential missile sources. The provisions that valves have bolted bonnets or secondary retention devices, and that they be designed to ASME III requirements effec-tively eliminates credible sources of valve component missiles.
Valves of ANSI 900 psig rating and above, constructed in accordance with Section III of the ASME Boiler and Pressure Vessel Code, are pressure seal I
bonnet type valves. For pressure seal bonnet valves, valve bonnets are prevented from becoming missiles by the retaining ring, which would have to 36 fail in shear, and by the yoke, which would capture the bonnet or reduce bonnet energy.
Because of the highly conservative design of the retaining ring of these valves (safety factors in excess of 8 may be used), bonnet ejection is highly improbable and hence bonnets are not considered credible missiles.
Most valves of ANSI rating 600 psig and below are valves with bolted bonnets. n Valve bonnets are prevented from becoming missiles by limiting stresses in the 3.5-2 Amendment 53 O
STP FSAR bonnet-to-body bolting material by rules set forth in the ASME Boiler and j~ - Pressure Vessel Code,Section III, and by designing flanges in accordance with applicable code requirements. Even if bolt failure were to occur, the like-lihood of all bolts experiencing a simultaneous complete severance failure is very remote. The widespread use of valves with bolted bonnets, and the low historical incidence of complete severance valve bonnet failures confirm that bolted valve bonnets need not be considered as credible missiles.
Valve stems were not considered as potential missiles if at least one feature, in addition to the stem threads, is included in their design to prevent ejec- l tion. Valves with backseats are prevented from becoming missiles by this fea-ture. In addition, air- or motor-operated valve stems will be effectively 36 ,
4 restrained by the valve operators.
Nuts, bolts, nut and bolt combinations, and nut and stud combinations have only a small amount of stored energy and thus are of no concern as potential missiles.
! Valves with threaded bonnet studs are not utilized in high energy piping and thus are of no concern as potential missiles.
l h45EM A >
3.5.1.1.2 Rotating Machinery: Potential missile sources associated with rotating machinery were identified as:
e Motor-driven pumps and compressors e Turbine-driven pumps e Heating, ventilating, and air conditioning (HVAC) fans e Diesel generator turbocharger rotors e Motor generator set flywheels
! NSED 6 Missile selection was based on the following considerations:
Ape.# -
operated during normal plant conditions;35 ase-l 1. Rotatin g ; : rt that capable of b a-* - missiles,.
0"N 4 W A kgb em. ssh
- 2. The energy of a rotating partrassociated th 20 percent overspeed is assumed - "i + -~ for component failure unless analysis is performed to indicate otherwise. Fw whic. e,wem sp% a.a\ Joe ue- 36 basci on vnmih p cm.h.kke.A to oct.e # woM S Pe.c15.
- 3. Determination of whether the energy of the missile is sufficient to per-forate the protective housing. For example, electrical motors are not considered potential missile sources due to their cast iron housing. The housing itself is capable of withstanding internal faults such as cooling fan break down or armature disintegration. "i::il:: .:::::ted 5 ; :: - .
1 tro f:ih::: :f p__p; e..d !.... ... d m y m ... ;f icir: cr '"-*=A 912 :: 10: Of th::: 21::11 : rill ;,; . m idad L. e f a .ae -- ad= _.. p The
! following are not potential missile sources:
l[ a. There are four turbine-driven pumps, of two types: the tur-bine-driven auxiliary feedvater pump and the three turbine-driven 3.5-3 Amendment 36
(
7 . _ _ _ . _ _ _ _ _ . _ . . _ _ _ _ _ _ _ _ . - _ _ _ _ _ _ __ _ _ __ _ _ __ _ _ _ ._ _. _ ._
Insert A Valves in high pressure systems have been reviewed. As a result of this review it has been determined that no failure associated with a single valve part can result in the generation of a missile.
Pressurized tanks in high pressure systems are either not located within the structures which house safety-related systems or.they are separated from safety-related components in cubicles or subcompartments within the structure.
Insert B Rotating equipment evaluated as potential sources of missiles were either determined incredible (based on supplier certifications) as missile sources, evaluated using the formulas given in FSAR Section 3.5.3, or the effect of loss of the potential missile impactees on the ability to shutdown safely was reviewed. A summary of rotating equipment considered as potential missile sources is given in Table 3.5-16.
Ll/NRC/fr
STP FSAR steam generator (SG) main feed pumps. The main feed pumps and their drive turbines are protected from overspeed by redundant overspeed
. trips. A single overspeed trip is provided on the auxiliary feed- 51 water pump drive turbine. These pumps are not considered to be a i source of missiles.
b7' -HYAC and chiller fans were reviewed. Chillers have very low r fans'which are not a credible source of missiles. Near of the l HVAC fans are' separated from safety-related equi and cable {
trays to the extent that postulated miss o not pose a safety i hazard. The supply subsyst'em-f _
e only fan which might be a l source of missiles and is ed in echanical-Electrical Aux- l l iliaries Buildin at El. 60.0 ft. es of this fan are i made of a and are postulated to impact the ho at 26.7 ft . The housing is 1/4-in.-thick steel and would conta ha missile.
! h. -ee The diesel generators (DCs) are designed to withstand overspeeds of 125 percent; redundant mechanical and electrical overspeed trips operate at 110 percent overspeed. The only portion of the diesels considered to be a credible source for postulated missiles is the turbocharger, which is not speed controlled and operates at high rpm. The turbocharger rotors weigh 270 pounds and are mounted on the diesels. In the event of failure, only one DG unit would be affected since each is separated from adjacent units by 2-ft-thick i
reinforced concrete walls which would contain any turbocharger missile.
CL -dv Motor generator (MG) set flywheels were reviewed to determine mis- ,
! sile generation potential. The fabrication specifications of the MG i set flywheels control the material to meet American Society for f Testing and Materials (ASTM) A533-70s, Grade B, Class I, with inspec- h4 i
tions in accordance with MIL-I-45208A and flame-cutting and machin-ing operations governed to prevent flaws in the material. Non-destructive testing for nil-ductility (ASTM-E-208), Charpy V-notch (ASTM A593-69), ultrasonic (ASTM A578-71b and A577-70s), and magne-tic particles (ASME Eaction III, NB2545) has been performed on each 44 flywheel material lot. In addition to these requirements, stress calculations have been performed consistent with guidelines of American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code,Section III, Appendix A to show the combined primary stresses due to centrifugal forces and to show that the shaft interference fit does not exceed one-third of the yield strength at normal operating speeds (1,800 rpm) and does not exceed two-thirds of the yield strength at 25 percent overspeed. However, no overspeed is expected for the following reason: The flywheel weighs approximately 1,300 lbs and is 35.26 in. in diameter by 4.76 in, wide. The flywheel mounted on the generator shaft, which is directly coupled to the motor shaft, is driven by a 200-hp, 1,800-rpm synchronous motor. The torque developed by the motor is insufficient for overspeed. Therefore, there are no credible mis-siles from the MG sets.
I N SE- Q_-( C_ -
3.5-4 Amendment 51
-x?
Insert C.
- 4. Some equipment configurations provide an unprotected aspect of the rotating component most likely to eject a missile, .i.e. , they may provide an opportunity for a missile to be released without impacting the component housing. For' example, centrifugal fans may have'an open discharge scroll without a ducted exhaust. The connected ductwork on other centrifugal fans may not be as thick as the evaluation shows is needed to prevent perforation by an oblique or perpendicular missile impact.
- 5. Single failure considerations are similar.to those used in the pipe rupture analysis. See Section 3.6.1-1.
L1/NRC/fr
STP FSAR l t l are administrative 1y controlled so that missiles resulting from dropped loads l36 are not considered further. In addition, missiles could result from a crane derailing and falling. However, overhead cranes were designed with clamping devices to prevent derailing. Therefore, no generation of missiles is a expected from derailment of an overhead crane. Appropriate p::::: 1 r pn M eh ,
measures (such as interlocks, special slings, etc.) have been 4 dent 444ed3 to l prevent accidental drop of a heavy load that could impact nuclear fuel, safe-ty-related equipment, or components whose failure could result in radiological 36
, )l6 6 M g consequences : exceeding 10CFR100.
3.5.1.2 Internally Generated Missiles Inside the containment. Systems and components inside the Containment whose failure could result in radiologi-cal consequences in excess of 10CFR100 guidelines or which are required for attaining and maintaining a safe shutdown during normal or accident conditions are listed in Table.3.5-1. No missile protection provision is necessary for the postulated missiles described in the following sections.
Potential sources of missiles are: 36 e High-pressure systems e Rotating machinery e Gravitational missiles l2 e Secondary missiles Q211.
(
Com$(2.1.cweb 3.5.1 Ak/ I
( ta dc6 36 High-PrkA3ssure kystems - Catastrophic failure of the reactor g l vessel, SGs, pressuriser, reactor coolant pump (RCP) casings,Kand piping g i
leading to generation of missiles is not considered credible. Massive and rapid failure of these components is incredible because of the material char- gN l acteristics, inspections, quality control during fabrication, erection and operation, conservative design, and prudent operation as applied to the parti-cular component.
l Components that nevertheless are considered to have a potential for missile generation inside the Containment are:
l 1. Control rod drive mechanism (CRDM) housing plug, drive shaft, and drive
! shaft and drive mechanism latched together ,
- 2. Valves
- 3. Temperature and pressure sensor assemblies i 4. Pressuriser heaters These potential missile sources are discussed in the following sections.
3.5.1.2.1.1. Control Rod Drive Mechanism Missiles - Gross failure of a CRDM housing sufficient to allow a control rod to be rapidly ejected from the j, core was not considered credible for the following reasons:
1-1 1. The CRDMs are shop tested at 4,105 psig.
4 3.5-5 Amendment 36 4
7* .
- _ ._._____m_
Insert D 3.5.1.1.4 Compressed Air / Gas Cylinders: Compressed air or compressed gas cylinders not part of a connected system have been evaluated for their ;
potential to damage essential safety-related equipment by ejecting missiles.
Most pressurized cylinders are located in areas outside structures housing safety-related equipment. Some are located in cubicles or compartments which
. separate them from safety-related equipment. Two types of high pressure compressed gas cylinders may be located in areas which contain essential safety-related equipment: portable carbon dioxide fire extinguishers and miscellaneous gas cylinders used to support chemical analyses. These cylinders will be secured as appropriate, in vehicle-type brackets or seismically designed racks and oriented so that an ejected fitting could not strike an essential safety-related component.
f L1/NRC/fr
STP FSAR
- 2. The CRDM housings are individually hydrotested to 3,107 psig after they are installed on the reactor vessel to the head adapters and are checked 3 again during the hydrotest of the completed Reactor Coolant System (RCS).
- 3. The CRDM housings are made of type 304 stainless steel. This material )
exhibits excellent notch toughness at all temperatures that will be encountered. l
- l
- However, it was postulated that the top plug on the CRDM will become loose and 2 it will be forced upward by the water jet. The following sequence of events ecs assumed
- The drive shaft and rod cluster control (RCC) are forced out of
- the core by a differential pressure of 2,500 psi across the drive shaft. The drive shaft and RCC, latched together, are assumed fully inserted when the
'j cecident starts. After approximately 14 ft of travel, the RCC spider hits the underside of the upper support plate. Upon impact, the flexure arms in the crupling joining the drive shaf t and RCC fracture, completely freeing the drive shaft from the RCC. The RCC would be completely stopped by the upper cupport plate; however, the drive shaft would continue to be accelerated upward to hit the missile shield provided.
i The CRDM missiles are summarized in Table 3.5-3. The velocity of the missiles l36 ccs calculated by balancing the forces due to the water jet. No spreading of the water jet was assumed.
3.5.1.2.1.2 Valves - Valve bonnets and stems have been eliminated on the came basis as valve missiles outside Containment. Refer to Section 3.5.1.1.1.
3.5.1.2.1.3 Temperature and Pressure Sensor Assemblies - Temperature and 36 i
pressure sensor assembly (inside Containment) missiles are treated in the same cenner as those outside Containment. Refer to Section 3.5.1.1.1.
i 3.5.1.2.1.4 Pressurizer Heaters - It was assumed that the pressurizer l36 hasters could become loose and become jet-propelled missiles. The missile characteristics of the pressurizer heaters are given in Table 3.5-4. A l36 10-degree-expansion, half-angle water jet was assumed.
! 3.5.1.2.2 Rotating Machinery - The RCP flywheel was not considered a l36 l cource of missiles for the reasons discussed in Section 5.4.1.
l hw.\c, 4.c\st,b is Wel ow-Ws. cam:).sent.m 4.ruuwd.M. s edtvw. 3. 5.l. l. 2. .
"f elle na......>.-
- ted by
.e
- tel
- :d feil ::: Of p ,: ;;d f>-.a.......
.t.__ >__n, - _s.. +_ us
- ::: bef= e el^ >s. /
,ca. ---
.menv. A u m m rt d rote 6:[.[e [ cec dea [ p. h b f (c. .S- M. 36 Yht%N scurtc5Gravitational b 8lWex iAMissiles - The consequences of a load drop have 3.5.1.2.3 been studied. The drop of the most critical load lifted by the polar crane does not have unacceptable consequences. Clamping devices prevent the crane from derailing and generating missiles. Appropriate preventive measures (such
! cs interlocks, special slings, etc.) have been identified to prevent acci-j dental drop of a heavy load that could impact nuclear fuel, safety-related i
equipment, or components whose failure could result in radiological conse-( quences exceeding 10CFR100.
3.5.1.2.4 Secondary Missiles - Orientation of the possible missile 2 L cources and the design of the barriers is such that there is no possibility of a211.1 l
3.5-6 Amendment 36 l
1
-e .-
STP FSAR The only externally generated cissiles for which prst:cti n is requir d cro ternado missiles, as discussed ir. Section 3.5.1.4. .
B:rriers used for missile protection are listed in Table 3.5-2.
w 3.5.3 Barrier Design Procedures p riers ate designed to withstand the effects of missila impact. The bar-riers are designed or checked to assure that a missile strike does not cause 36 ccabbing. The overall effects are evaluated by the response of the structure er target and portions thereof to missile impact. Missiles are assumed to strike the barriers normal to the surface, and the axis of each missile is ccsumed to be parallel to the line of flight. These assumptions result in a c:nservative estimate of missile effect to barriers.
3.5.3.1 Local Damage Prediction. Prediction of local damage, i.e.,
damage in the immediate vicinity of the impact area, includes estimating the d:pth of penetration, minimum thickness required to prevent perforation, and cinimum thickness required to preclude spalling.
l 3.5.3.1.1 Reinforced Concrete Barriers: The depth of penetration of a
- tissile (excluding turbine-generated missiles) into a reinforced concrete bar- 36 rier is calculated by the modified Petry formula, as set forth in Reference '
3.5-13. Depending upon the slab thickness penetration depth ratio, a', the following expressions are used:
12KAP log 10 * # "'
, 215,000 ,
D=
12KAP log 10 l [# \ [ + *[-4(a' -2))\
Il I ' # -
215,000j ( ) . .
f where:
I . I I D = penetration depth,-44. >
3,200
- K = 0.00476 gy ,,p) f, = material parameter A = W/A = sectional pressure, Ib/ft 8 P c I
V = impact velocity, ft/sec W = missile weight, Ib
"#'"' t*
Ac " "II1' * "**""
i e' = t/D = vall thickness / penetration depth 3.5-18 Amendment 36 i
3 '
STP FSAR l
TABLE 3.5-1 SAFETY CLASS SYSTEMS AND COMPONENTS AND SEISMIC CATEGORY I STRUCTURES TO BE PROTECTED External Internal System, Component, Missile Missile FSAR l
or Structure Location Protection
- Reference Structures Section 4
3.8 Containment Building N/A A N/A Mechanical-Electrical Aux 11- N/A A N/A l iaries Building, including control room Fuel-Handling Building N/A A N/A Diesel-Generator Building N/A A N/A I Essential Cooling Water Intake N/A A N/A !
and Discharge Structures s
- Essential Cooling Pond N/A A N/A 36 j MSIV structure (IVC) N/A A N/A I FW valve structure (IVC) N/A A N/A 7
i Class 1E Underground Elec- N/A A N/A q trical Raceway System 312 I .23
- Auxiliary Feedwater Storage Tank N/A A N/A Containment Isolation Valves and RCB, IVC, B D Section I
Pipina -- FEB, MAB 6.2.4 Reactor Coolant System Chapter 5
l Reactor vessel & supports RCB B B CRDM assembly RCB B B f Thermal barrier RCB B 9&
Steam generator & supports F.,5 3 D Reactor Coolant pumps & supports RCB B D Pressuriser & supports RCB B D i
- See notes at the end of this table for code meanings.
f 3.5-24 Amendment 36
- 3. ,. - . . __
STP FSAR TABLE 3.5-1 (Continued)
(.-
SAFETY CLASS SYSTEMS AND COMPONENTS AND SEISMIC CATEGORY I STRUCTURES TO BE PROTECTED External Internal System, Component, Missile Missile FSAR or Structure Location Protection Protection Reference Reactor Coolant System (Continued)
- Other RCS piping, supports valves RCB B D
& fittings required to maintain RC pressure boundary
!!.;. _1 i; . .-ie. 3C0 - .
Reactor Vessel head vent system RCB B D Reactor Head Degassing System RCB/MAB B D Chemical and Volume Control System Section 9.3.4.1 Regenerative HX RCB B D
(.,~ Centrifugal charging pump MAB B D 36 Positive displacement pump MAB B D Seal water injection filter MAB B D Seal water return filter MAB B D Boric acid transfer pump MAB B D Boric acid filter MAB B D RC purification pump MAB B D Boric acid tanks MAB B D Pulsation dampener MAB B D Piping and Valves RCB/MAB B C#
Emergency Core Coolina System Section 6.3 Accumulators RCB B D NHSI pumps FHB B D LHSI pumps FHB B D 3.5-25 Amendment 36 3 .. . .
STP PSAR r TABLE 3.5-1 (Continued)
SAFETY CLASS SYSTEMS AND COMPONENTS AND SEISMIC CATEGORY I STRUCTURES TO BE PROTECTED External Internal System, Component, Missile Missile PSAR or Structure Location Protection Protection Reference Sampling System Section 9.3.2 Sample delay coil RCB/MAB B D Piping and Valves RCB/MAB B D Steam Generator Blowdown System Section 10.4.8 Piping from SG out to and RCB/ IVC B D including the isolation valves Diesel Generator Lube Oil System DGB B D Diesel Generator Fuel Storage and Transfer System Section
(~ , . 9.5.4 Diesel oil storage tanks DGB B D Valves DGB B D 36 Piping except vent and fill DGB B D piping downstream of last valve in the line Diesel Generator Cooling Water DGB B D Section System 9.5.5 Diesel Generator Air Starting System Section 9.5.6 Air receivers DGB B D Piping and Valves DGB B D Containment Combustible Gas Control System Section 6.2.5 Electric hydrogen RCB B JD'Ce recombiner Containment Hydrogen Monitorina System Section 6.2.5 Hydrogen analyzer package MAB B .D* C.,
3.5-29 Amendment 36 7
. f. -
SAFETY CLASS SYSTEMS AND COMPONENTS AND SEISMIC CATEGORY I STRUCTURES TO BE PROTECTED External Internal System, Component, Missile Missile FSAR Location Protection Protection Reference or Structure Containment Hydromen Monitorina System (Continued)
Piping and valves inside the RCB/MAB B JW" 0' Containment to and including the analyzer package isolation valves B ;5 C-Remaining piping and valves MAB Heatina Ventilatina, and Air Conditionina System
- 1. Containment building HVAC RCB B D Section RCFCs including ductwork, 9.4.5 MS isolation valve structure ductwork containment cubicle fans, exhaust fans, ductwork.
C.-' dampera Containment purge isolation RCB/FHB B D 36 valves and penetrations MAB
- 2. Mechanical Auxiliary Section Building HVAC 9.4.3 Supplementary coolers MAB B W'C-subsystem
- 3. Control Room and Electrical Section Auxiliary Building HVAC 9.4.1 Air handling unit EAB B D Fans, ductwork, and dampers EAR R D Battery room exhaust fans EAR B D Filters EAR B D Chiller MAB B D Chilled water pump, piping ete NAB B D C
3.5-30 Amendment 36 z
STP FSAR TABLE 3.5-1 (Continued) 4 SAFETY CLASS SYSTEMS AND COMPONENTS AND SEISMIC j CATEGORY I STRUCTURES TO BE PROTECTED External Internal System, Component, Missile Missile FSAR or Structure Location Protection Protection Reference Class IE Electrical System Components (Continued)
! 480 vac/125 vde battery EAR B D chargers (for vital de bus) 125 vde panels (vital de power EAB B D distribution)
- Voltage regulators (backup for EAR B D instrumentation inverters) 120 vac instrument bus panels EAB B D 1
(vital instrumentation ac power distribution) 1
(,'
- Containment penetration assemblies EAB/RCB B D 36 Main control board EAB B D
, ESF Load sequencer EAR B D l Diesel generator and DGB B D accessories i Diesel generator control panels O B D t Relay boards and racks EAB B D 1
Wire and cable raceway I/O B C system i
! Underground electrical duct 0 B D l bank system l Cable system (power, control, I/O B C and instrumentation) l Blectrical supports I/O B D l : Motors (1E) I/O B D Valve operators I/O B 4[ (/
3.5-32 Amendment 36 eg ,. . .
STP FSAR TABLE 3.5-1 (Continued)
C, SAFETY CLASS SYSTEMS AND COMPONENTS AND SEISMIC CATEGORY I STRUCTURES TO BE PROTECTED External Internal System, Component. Missile Missile FSAR or Structure Location Protection Protection Reference Instrumentation and Control System Components Chapter
'7 Radiation monitoring system I/O B .FC (safety-related components)
Reactor Trip System I/O B D Engineered Safety Feature EAB B D (EST) Actuation System Systems required for safe RCB/MAB/ B M shutdown FHB/TGB B D Fost accident monitoring system 0 B &C, Safety-related instruments, I/0 B 9C C~.* ' tubing, and fittings 36 Safety-related process instruments I/O B BL C.
Fuel-Handlina System Section 9.1 Fuel transfer tube RCB/FHB B D and flange Spent fuel racks FHB B D Incore Instrumentation Chapter 7
Seal table assembly RCB B D Flux thimble tubing RCB B D Flux thimble fittings RCB B D Flux guide tubing RCB B D 3.5-33 Amendment 36 3
STP FSAR TABLE 3.5-1 (Continued)
SAFETY CLASS SYSTEMS AND COMPONENTS AND SEISMIC CATEGORY I STRUCTURES TO BE PROTECTED Notes Location l 1 - Inside Containment f 1
0 - Outside Containment N/A - Not applicable RCB - Reactor Containment Building FHB - Fuel Handling Building MAB - Mechanical Auxiliary Building EAR - Electrical Auxiliary Building 36 DGB - Diesel Generator Building IVC - Isolation Valve Cubicle TCB - Turbine Building ECWIS - Essential Cooling Water Intake Structure External Missile Protection A - Designed to withstand the impact of an external missile l
B - Housed in a structure designed to withstand the impact of an external missile 1
j Internal Missile Protection f A - Designed to withstand the impact of internal missiles d hA. m q N SYfiko ht, la Meud B - Protected from the impact of internal missiles by shield walls or the equivalent C c y- wek rtqWyt. A. 40 1
- Protection frwebs b not required W.hg46 %due to component c.ngsun e%' %,redundancy vw;w. \* er e ubig,gg{t,$hdks A D - Protection not required because no missiles strike the component N/A - Not applicable 3.5-34 Amendment 36
\
g ..
Table 3.5-16 -
Rotating Equipment Missile Sources
-Outside Containment Equipment Identification Location Casing Perforation Calculated Thickness to Remarks (Yes/No) -Prevent Concrete Spalling ECW Pumps ECW Intake Yes - Assumed -
.. ( A) ~
Structure Centrifugal Charging MAB No - --
Pumps lA,1B ,
-Boric Acid Transfer MAB No - -
Pumps CCW Pumps MAB No -- -
Reactor Maketp MAB No - -
Water Pumps ECW Screen Wash ECWIS No - -
Booster Pumps Essential Chilled
~
MAB No - -
Water Pumps Feedwater Isolation IVC Yes - Assumed -
(A)
Valves Hydraulic Pump Modules
-Refueling Water MAB No - - -j Purification Punp
_q Table 3.5-16 Rotating Equipment Missile Sources Outside Containment Equipment Identification Location Casing Perforation Calculated Thickness to ' Remarks (Yes/No) Prevent Concrete Spalling MAB Chilled Water MAB No - -
Ptmps Waste Evaporator MAB Yes - Assumed -
(A)
Recirculation Pumps Low Activity _ Spent MAB Yes - Assumed -
(A).
Resin Sluice Ptnp Waste Concentrates MAB Yes - Assumed -
(A)
Transfer Pump Condensate Polishing MAB Yes - Assumed - 3 (A)
Waste Collection Tank Transfer Pump LWPS Evaporator MAB Yes - Assumed -
(A)
Distillate Pump ERS Evaporator MAB Yes - Assumed -
(A)~
Ptaps LWPS Seal Water MAB Yes - Assumed -
(A)
Ptnps
-Tabla 3.5-16 Rotatina Equipment Missile Sources Outside Containment Equipment Identification Location Casing Perforation Calculated Thickness to Remarks (Yes/No) Prevent Concrete Spallina Resin Dewatering MAB Yes - Assumed -
(A).
Pug Spent Resin Transfer MAB Yes - Assumed - (A)
Pug LWPS Evaporator MAB Yes - Assumed - (A)
Condensate Return Pump Spent Fuel Cask F}E Yes - Assumed -
(A)
Pool Pump Waste Holdup Tank MAB Yes - Assumed - (A)-
Pump LWPS Surge Tank FIE Yes - Assumed - (A)
Ptaps Waste Condensate MAB Yes - Assumed - (A)
Tank Pumps ,
Waste Monitor MAB Yes - Assumed -
(A)
Tank Ptnps 4
Table 3.5-16.
Rotating Equipment Missile Sources Outside Contairraent Equipment Identification Location Casing Perforation Calculated Thickness to- Remarks (Yes/No) Prevent Concrete Spalling Floor Drain Tank MAB Yes - Assumed -
(A)
Pumps Spent Fuel Pool FH3 No - -
Cooling Punps lA,1B Reactor Coolant MAB No - -
l Purification Pump BTRS Criiller -MAB No - -
i Punps lA; IB Spent Fuel Pool FM3 No - -
Skinner Pump RCFC Chilled Water MAB No - -
l Ptrp l LWPS Auxiliary MAB Yes - Assumed -
.(A)
Feed Pung Laundry and Hot MAB Yes - Assumed -
(A)
Shower Tank Pump BRS Evaporator MAB Yes - Assumed -
(A)
Feed Pumps
Tabla 3.5-16
~
Rotating Equipment Missile Sources Outside Containment EqJipment Identification Location Casing Perforation Calculated Thickness to Remarks (Yes/No) Prevent Concrete Spalling Auxiliary Feedwater IVC No - -
Pumps BRS Condensate MAS Yes - Assumed -
(D)
Return Ptsps TSC Chilled Water EAB No - -
Pumps ,
FHB Main Exhaust FHB No -
(C)
Fans q I
MAB Main Supply Fans MAB No -
(C)
MAB Supplemental MAS No -
(C) l i
Exhaust Fans i
Penetration Space MAS No -
(C)
Exhaust Fans Tendon Gallery Tendon No - - l Fans Gallery MAB Main Exhaust MAS Yes <2 inches (B)
Fan RCB Normal Purge MAB No - -
Supply Fan
- q
.l Table 3.5-16 ..
Rotatirx3 Equipment Missile Sources Outside Containment-Equipment Identification Location Casing Perforation Calculated Thickness to- Remarks (Yes/No) Prevent Concrete Spallino RC8 Normal Purge Exhaust MAB No - -
' Fan Electrical Penetration EAB No -
(C)
Area M U Fans EAB Air Handling EAB No - -
thit Fans Low Pressure Breathing MAB- No - -
Air Compressor BTRS Chiller MAB No - -
Compressor RCB Supplementary MAB No -
(C)
Purge Supply Fans RCB Stoplementary MAB No -
(C)
Purge Exhaust Fans CCW Ptap Supplementary MAB No - -
Cooler M U Fans
Table 3.5-16 _
Rotating Equipment Missile Sources :3- ~
. Outside Containment Etpipment Identification Location Casing Perforation Calculated Thickness to Remarks (Yes/No) Prevent Concrete Spalling -
Centrifugal Charging MAB No - -
Pump Stpplementary Cooler 4tJ Fans PD Charging Ptsup MAB No - -
S q lementary Cooler AttJ Fan MAB Supplewental Fan MAB No -
(C)
Coil Unit Fans EAB Return Fans EAB No - -
EAB ANJ Supply Fans EAB No - -
FHB Exhaust Booster Fle No - -
Fans FHB Supply Fans Fle No - -
(C)'
DGB 011 Tank Room DGB No -
Exhaust Fan Control Room Kitchen EAB No - -
and Toilet Exhaust Fan Tablo 3.5-16 Rotating Equipment Missile Sources Outside Containment Equipment Identification Location Casing Perforation Calculated Thickness to Remarks (Yes/No) Prevent Concrete Spalling PASS Facility AFU Fan FHB No -
(C)
FHB Elevator Exhaust FHB No - -
Fans Computer Room AHU EAB No -
(C)
Fans TSC Computer Room EAB Yes - Assumed -
(A)
ALU Fans Control Room AHU EAB No -
(C)
Supply Fans TSC Makeup Air Fan EAB Yes - Assumed -
(A)
TSC Supply Fans EAB Yes - Assumed -
(A)
TSC Return Fans EAB Yes - Assumed -
(A)
TSC Exhaust Fans EAS Yes - Assumed -
(A)
TSC HVAC Equipment Room EAB Yes - Assumed -
(A)
Exhaust Fan l
! -8
s Tablo 3.5
- Rotatina Equipment Missile Sources.
Outside Containment Ecpipment Identification Location Casing Perforation Calculated Thickness to Remrks
'(Yes/No) Prevent Concrete Spallina
~
TSC Chiller EAB Yes - Assumed -
(A)
Locker Room / Office MAB Yes - Assumed -
(A)
Supply Fan Radwaste Counting MAB Yes - Assumed -
(A)
Room AHJ Fan Spent Fuel Pool Cooling FHB No - -
Pump Rooms AHU Fans l
<*Iable 3.5-16 Kotating Equipment Missile Sources Outside Containment Notes (A) Potential missiles from this source.are separated from other essential systems by adequate barriers.
(B) Missiles from this source which might penetrata the housing or casing'will'not interact with any. equipment necessary to support safe shutdown or prevent uncontrolled releases of radioactivity.
(C) Missiles which might exit the scroll of this centrifugal fan will not cause interactions which might prevent safe shutdown of the plant or result in an uncontrolled release of radioactivity.
(D) Missiles which might penetrate the casing of this component will not cause interactions which could prevent safe shutdown of the plant or result in an uncontrolled release of radioactivity.
4 L1/NRC/fr t
A'
Table 3.5-17-- ,
Rotating Equipment Missile Sources Inside Containment-Equipment Identification Location Casing Perforation Calculated Thickness to Remarks (Yes/No) Prevent Concrete Spalling RER Pumps El.-(-)4' 6" No - -
t Reactor Coolant El. (-) 9' 1" No - -
Drain Tank Pumps 4
RCFC Supply Fans El. (-) 2' 0" No - -
.; Containment Cubicle El. 68' 0" No - -
Exhaust Fans Reactor Cavlty El. (-) 11' 3"- Yes <2 Inches (A)
Vent Fans 4
Containment Carbon El. 52' No <12 inches (B)
Unit Supply Fans
,' Reactor Supports. El. 11' No - -
Exhaust Fans CROM Cooling El. 65' No - -
Fans RC8 Elevator 'El. 93' 8" No - -
Vcnt Fan Table 3.5-17
' Rotating Equipment Missile Sources Inside Containment Notes (A) Missiles from this source which might penetrate the housing or-casing will not interact with any equipment necessary to support safe shutdown or prevent uncontrolled releases of radioactivity.
(B) The containment carbon unit fans have a wire screen over the discharge which may not stop a postulated missile from leaving the scroll. The containment liner might be impacted by such a missile from two of the fans, but the liner would not be perforated. The loss of other equipment which might be damaged by missile impact would not prevent safe shutdown of the plant nor result in uncontrolled release or radioactivity.
b I
2-l l
l I
L1/NRC/fr i
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_ -.,__.--,r,.-_,., . - - - . - . - . _ _ _ _ . , , . . . _ . - - _ . . . - - , _ . _ - . _ , . . _ - _ _ . _ _ _ .
STP FSAR Ouestion 410.01N The FSAR states that the auxiliary and main feedwater pump turbines are protected from overspeed by redundant overspeed trips and that neither turbine is considered to be a source of missiles. Regardless, provide the results of an analysis which shows safe shutdown will not be affected by such missiles.
Response
(hcldt C.u frent re5 on5t.)
IE 5 e$!c*' 'b & v<ersped -b;p en ha. u y;/. ,,y a s w E'c w k p g - k .-s ,u n 7, b,,y,,.2,,c, here a re- have ,- 4ke len s a ff:ci n-4~ % m m -b pro 4cA~ <sae t.,/ ms, t %
p kla k4 -bu<b,w fnyunt ,nisodes,3 u;p/fiwh> a risisg k a psk k M hwch,ue la6 <e d flw anihary fae d wa 4, pay ukael due h 120% onc woatl xd kw tuoj gy -A pelre/c,xedLu3,,x$kedw*oLr-
- c -44,w . /m aduro~ , eaa. +re,x d m.x o k ,
Ibo Niho% ~
heeds /afi, - e.} v:fruss'l' ju ele.
LJ Au f fra
~ We, c a retc ( x L.Lwy 4te a -t;/, 5 4,d
- 4. y+ % k-
)
p sepaled k ha o her % by % he
, caserele- walls. Tv bi>w b[a4e> &le M h k c)cc1 4 fr.~ he_ w R,w /ted wak, 7m j%-t hdA dec/ d*e k povo ovmysed at -h p h. % h e k. 9 wo.IL m k kan. o u % f k y n n . >, 9 h a6nt~
o <- oyall % sden- x (11 f e d y o g r S & p& a. ,
beb, m a aility 6 3L% t v m/13.+5 g7>e the %br~es, ofe&L by ye,%Idet wrasile, hr
STP FSAR l
ouestion 410.02N Provide the results of an analysis, as per commitment in the FSAR, which provides information relating to missiles generated by postulated failures of pumps and fans. Note that your response should include single failure ,
criterion.
Response
kde. (R((M (C5 Ob $c Sec revud Fskt 5"t;" 3 T l' '
(-
Vol. 2 @R 3.5-5N
. r-
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I l
l
~ 1 STP FSAR I
, Ouestion 410.03N Verify that missiles produced from pressurized tanks and compressed air / gas cylinders have been evaluated and that they will not affect safe shutdown equipment.
Resnonse
- ~
.JLe-ous or m.
missile analysis, including nre==iirin d tanks and
~
compressed air / gas evlindere ns,iwill~be provided during the Fourth l__@ :::: ef luus 3.u
1 I
l Vol. 2 Q6R 3.5-6N Amendment 51 i
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