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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] |
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l 1
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The Light !
@OE f flouston Lighting & Power P.O. Ilox 1700 llouston, Texas 77001 (713)228-9211 r
April 29, 1987 i ST-HL-AE-2073 File No.: G9.17 10CFR50 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 South Texas Project Units 1 and 2 Docket Nos. STN 50-498, STN 50-499 FSAR Revisions Concerning Section 9.5.1; Fire Protection Systems Attached is revised FSAR Section 9.5.1, " Fire Protection Systems". These changes are being incorporated for consistency with the Fire Hazards Analysis Report and other STP design documents.
HIAP believes that conclusions previously reached in the SER remain valid. If you should have any questions on this matter, please contact Mr. J. S. Phelps at (713) 993-1367.
9 M. R. W senburg Deputy P oject Mana JSP/yd
Attachment:
Revised FSAR section 9.5.1 00 Ll/NRC/fd 8705050104 870429 PDR F
ADOCK 05000498 PDR.
l-
~
'*- ST'-HL-AE-2073 Houston Lighting & Power Company f.: 17 j cc:
~
i: Regional Administrator, Region IV M.B. Lee /J.E. Malaski i Nuclear Regulatory Commission . City of Austin 611 Ryan Plaza Drive,. Suite 1000 P.O. Box 1088
-Arlington, TX 76011 Austin,-TX 78767-8814.
I ~ N. Prasad Kadambi, Project Manager. A. von'Rosenberg/M.T. Hardt
- ' U.S. Nuclear Regulatory Commission City Public Service Board 7920 Norfolk Avenue P.O. Box 1771'
. Bethesda, MD .20814- San Antonio, TX 78296 Robert L. Perch, Project Manager Advisory Committee _ on Reactor Safeguards U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue- 1717 H Street
'Bethesda, MD 20814 Washington, DC 20555 Dan R.' Carpenter Senior Resident Inspector / Operations c/o U.S. Nuclear Regulatory Commission-i .. P.O. Box 910' '
' Bay City, TX 77414
'Claude E. Johnson Senior Resident Inspector /STP
- c/o U.S. Nuclear Regulatory a Commission i P.O. Box 910 Bay City, TX 77414 .
M.D. Schwarz , Jr. , Esquire ,
l Baker & Botts 1 -One Shell Plaza Houston, TX 77002 J.R. Newman, Esquire Newman & Holtzinger, P.C.
1615 L Street, N.W.
j .Washington, DC 20036 ,
l :
1 T.V. Shockley/R.L. Range
. Central Power-& Light Company P. O. Box 2121 Corpus Christi, TX 78403 i
(
l 1
i L1/NRC/fd Revised 2/3/87 i
ATTACHMENT STP FSAR ST.HbAE M 9 D 0 P.A..G. E l OF l 9-5/
In all cases, adequate fire detection and protection of the systems and -
1 co nents and bringare the provided plant to tocold allow the fire brigade to manually extinguish the fire shutdown. g these areas is described in the Fire Hazard Analysis ReportThe protection prov .
possible, adequate fire detection and protection The protec-are installed l47
);'
tion coatings, anc provided is composed of fire suppression systems indicated in the FHAR. thermal barriers or fire stops, or a combination of these, the use o
, as l3 specific deviations are identified and justified in the rFHAR. I 47 Fi The te.ss and isolation rated fire barriers, and separation criteria utilized of in the m 47 Safe shutdown can then be accomplished using the remaining ns.
t train o Safety-related structures are primarily of reinf6rced concrete constru ti a structural steel framing and provide ample inherent fire resistance cforon on walls, floors, and ceilings which separate redundant systems Exposed struc-tural steel is protected with spray-applied fireproofing material h aving a 47 the low fire loading. fire rating of at least 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> except where e to it was deem Within the safety-related structures, interior walls, partitions, structural components, ing are noncombustible or have acceptably lowradiation and materials for insulation, ratings forshielding f and sound47proof/N flame spread, and smoke development. uel contribution, are listed by a nationally recognized Interior finishes testing are noncombustible laboratory as having orfuel cont i bution, flame spread, and smoke develop ratings of 25 or less r-Materials i having being a rating of noncombustible. 50 or less are considered in the fire hazard as analysis !
The use of suspended ceilings withi I Where these ceilings are necessary,n safety-related structures is minimized.
such as in the control room, personnel are of noncombustible construction. and offices, the ceilings and their facilities, health physics area supports
, s' may contain lighting and communication circuits in steel conduit or47fire deT taction circuits in aluminum sheathing (ALS). -
A wet pipe cprinkler system is
! ceiling and are not readily accessible 4:::provided for the one case whe
! provided for access above the portion of the control room with a suspendedS:
ceiling.
i Adequate floor drains are installed throughoutandsafety-relat 1
systems and hose streams from the standpipe systems.g certain areas such as
[%s s5b%ew ,
pmc6 sendta sp% h proosdd diW.u2.), A.M WE.WM e med )5 d<g H ( Rett.
I Wov-voog y c vsi<.\ Wo m - T6sbv ko de m i l*P e t h eN 6 t' b q M c % t v too m h d D"'M SO N (Raam oso) ma G.w& (oo O (R ** U N) 4". w ot p(S v'd*A M %v d va E s b we o s.JW .1 i
n a ree.oWd % dcEm s 4 adj ed cs<<$dws wel toom 5.
9.5-2 Amendment 54 i
.-n.-,--,..-n. , - . - . . -n , , , . , - - - - - - , - . , - , - ----------n. + -n~ - - - . -,-,,-,---,.---,.-n.- -
STP FSAR ATTACHMENT ST-HL AE 10%
PAGE ;LOF l S.
} the control room - ' eft ^ crr :::: [which are not provided with fixed water spray or sprinkler systems, are not provided with floor drains. Any water
(]~ from hose streams used in these areas is removed by the adjacent corridor drains, and precautions have been taken in these areas to prevent runoff water
-from damaging safety-related equipment. Floor drains which may collect water from a radioactive area are routed to the Liquid Weste Processing System. l47 Drains in areas containing combustible liquids are designed to prevent the possibility system.
of fire spreading from one area to another through the drainage 47 C
As in the majority of fires, the principal toxic gas produced by a fire occur- l3 ring in areas where manual fire supression will be used would be carbon monox-ide.
Other toxic gases may be evolved in small quantities, depending upon the exact composition of any combustibles located in the vicinity of a fire. .The 47 removal of smoke and toxic gases required to enable fire fighting personnel to-enter an area is discussed in the FHAR, Section 2.4.3.4.
Ti.. n ' - y erfer. :M-;d; : f r:;;;12 tier errifer:d ia ib e==isa J ;i-Fi. 7 e:estica @ :: rre yr rid:f 1: *eLI. ".3-2. L 47 ItetA/
A 9.5.1.2 System Description. Standpipe and hose systems, together with portable extinguishers, are provided in all buildings throughout the plant, except for the Domineralizer Building and Essential Cooling Water (ECW) intake structuresj which are provided with ou ide fire hydrantsyand the Fire Pump House,which is provided with an automa c wet pipe sprinkler and an outside 47 fire hydrant.
yg ym
)
In addition, fixed fire suppression systems are installed as required.
The type of fire protection provided for each plant area is provided in Table
' 9.5-3 and is discussed in greater detail by fire area and zone in Section 3.0 47 of the FHAR.
Fire Protection System Piping and Instrument Diagrams (P& ids) are provided as Figures 9.5.1-51 through 9.5.1-58. 47 9.5.1.2.1 Fire Protection Water Supply System: Plant fire protection '
systems which utilize water are supplied by an underground piping ring main l 47 system. This undergroung ing main is installed in accordance with the requirements of NFPA 240 he system piping is of cement-lined, ductile iron with push-on joints, and the thrust forces are restrained by tie-rods and l 47 clamps. The entire underground piping system is cathodically protected.
l The STP plant layout comprises two units, approximately 600 ft apart. The underground ring main encompasses both units, and a cross-connection routed between the units connects the north and south sides of the ring to form a figure-eight configuration. The piping used in the primary ring main is of 14-in. nominal size, and can supply the largest water demand of any hasard if 47 that part of the main which would have normally provided the shortest path to the hazard area is out of service.
Sectional isolation valves of the post indicator type are installed in the
[ ' ring main to permit the isolation of any part of the main without removing coverage from any area of the plant. g 9.5-3 Amendment 47
%3
l ATTACHMENT If45 EAT h ST.HL AE 2D7.3
- ,P6GE %_OF i9 i
/ Equipment in the fire protection systems conforms to the standards of the National Fire Protection i Association listed on Table 9.5-2. All known deviations to the NFPA codes have been identified. Exceptions are required for deviations / conditions such as seismic requirements, etc.
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. STP FSAR ATTACHMENT I ST.HL.AE ML3 1 i
t_P. AGE JLOF Ip l
t Branches are taken from the ring main to supply the building internal protec- j tion systems and the special equipment protection systems, as required. Post ,I , '
- indicator valves are installed in all such branches as they leave the main, to )
- parait the isolation of any system.
In addition to supplying the building internal and special equipment protec-j tion systems, the ring main also provides water for the Yard Fire Protection
] System. This system comprises fire hydrants strategically located at approxi-
{ mately 250-ft intervals to provide a good fire-fighting capability. Special l47 attention is given to the placement of hydrants in the vicinity of fire j) hrzards such as the turbine lube oil area, oil-filled transformers, auxiliary i boilers, fuel oil storage area, etc. Each fire hydrant is contained in a hose house which, as a minimum, is equipped with hoses and nossles as required by kNFPA24f9tydrantsaretwo-wayandarefittedwithhosevalves. Threads on hydrant hose valves and hose equipment are National Hose Thread. This hose 47 thread is also used by fire departments and brigades in the vicinity of the
! oite.
Three UL-listed fire water pumps, installed in three separate cubicles within a fire pump hours, are used to provide the required water pressure and flow in the system. Prior to fire water pump start, required water pressure is main- 13 i tcined by an electric jockey pump.
l Each pump is complete with a diesel-engine driver, a fire pump controller, dual starting batteries, and a 550-gallon diesel fuel oil storage tank. The
] three pumps complete with the above accessories, are separated by 3-hour rated i fire barriers and the entire building is provided with a wet pipe sprinkler
] fire protection system. The# eptire fire pump installation meets or exceeds })#
l the requirements of riFPA 20 aYd re
! Unit 1 ::' "-if 2 control roo$ quired alarms are transmitted tc 68the j g 9 . A N M t. t
- P k Ecch pump has a rated capacity lof 2,500 gal / min at 125 psig and is capable of providing at least 150 percent lof the rated capacity at not less than 65 per-cent of the total rated head. j.".ny :ini;1; y .'c'an provide 100 percent of the 47 i flow required for any single system protecting a safety-related area including
- ample flow for additional hose streams. All three pumps discharge into a common header which forms part of the ring main system.
! The three pumps take suction through 14-in.-diameter suction pipes from a l47
) 16-in.-diameter header which in turn is supplied with water from two l 300,000-gallon fire water storage tanks. Two 14-in.-diameter pipe connections are provided between each storage tank and the 16-in.- diameter header (total i four 14-in.-diameter pipes). Isolating valves are provided at the suction j nozzles of the tanks and in each of the 14- in.-diameter pipes as they join i the header. Similar valves are provided in the 16-in. header and in each of j the three 14-in.-diameter pump suction lines as they leave the header. Thus, ,
, any pump or combination of pumps can take suction from either or both fire '
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water storage tanks. In addition, a check valve is provided adjacent to the j isolating valve on each of the four tank suction lines at the header so that a j rupture or leak in either tank does not permit the other tank to be drained
, through the interconnecting piping. Both tanks are used only for fire water ctorage, and no outlets are provided for connection to any other system. ,
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9.5-4 Amendment 47
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.STP FSAR ATTACHMENT ST HL AE WO 4 A.ge PAGE m,OF 4 j i The water supply to refill the fire, W tanks is normally provided from
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i the Fresh Water System, which takes suction from a settling basin and can refill one tank in 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or less. In the event of a failure in this system, l47 I the tank is refilled directly from the site well water system.
.} 9.5.1.2.2 Cablina Areas: jor cabling areas outside Containment are
! ire barriers. Automatic wet pipe sprinkler protection, at ,
1 enclosedby3-hour theceilinglevel,*h {illisprovidedthrou5outthecablespreadingroomsand h
! power cable vault. For concentrated cable in trays outside of the cable
. spreading rooms and power cable vault where the cable tray sections are not 54
[ 1 readilyg ecessible to an effective hose stream, automatic wet pipe sprinkler i systensp ill i;'provided at the ceiling level. The sprinkler systegrill be*-
i j s t hydraulically designed to provide an average density of 0.3 spa /ft8 over any
! 3000 sq. ft of floor area. Specific areas covered are described in detail in Section 3.0 of the IHAR.
t, us&M Lo ad..de. -----'-
A 4 , L 5: i up : n r Ffire suppression,i: ur'Ystandpipes es& hoses awJ j ;
el: ; vi M portable extinguishersfprovided throughout the building.
- a c4.
Cables used in these areas are designed to be wetted without electrical ,
il faulting.
1 Each cabling area contains only one train of redundant safety related cables- :
? except the train B cable spreading / power cable area which contains several train C cable trays. The train C trays pass vertically through the train B j area and terminate in the main control room. Alternate shutdown capability is
- provided for these circuits as described in the FHAR. ,
r i 1 47 !
l( Cabling in these areas meets the IEEE 383-1974 flame test with specific excep-
- tions as noted in the FHAR.
l Within each separate cable division, different classes of cables, such as i medium-voltage cables, low-voltage cables, and instrument cables, are
{ installed in cable trays or raceways specifically dedicated to each class, i Where cable trays are arranged in tiers, the' cables are installed in the tiers j in order of fault energy, whenever possible, with the highest fault energy j cables in the upper trays and ' instrumentation cables in the lower trays. r l Spatial separation is provided between cables of redundant safety-related i i divisions, and also between cables of safety-related and non-safety-related i divisions, in accordance with the requirements of IEEE Standard 384-1974 and l Regulatory Guide (RG) 1.75.
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i 9.5.1.2.3 Switchaear Rooms: The train A, B, and C switchgear rooms are
- \ separated from each other by 3-hour fire barriers gA W switchgear room % ere S l } ne= % d with fire detection and alarms (see Section 9.5.1.2.19k Portable 1 carbon dioxide type extinguishers are provided adjacent to cne switchgear
! rooms, and manual hose stations on the building standpipe system are available in the vicinity of each switchgear room. Only variable pattern nozzles having no straight stream capability and specifically approved for use on electrical fires are installed on hose stations in the vicinity of switchgear rooms.
i i Cables passing through the ESF switchgear rooms, and not directly associated j with those rooms, are kept to a minimum. -
, l47 l (' ) ( ucA d A L setdd brewd> peM semb 53h cem.d. M 94k l
sMS % in & syvbd sem& s%% ta % c % d k o d s W % s-9.5-5 Amendment 54 i
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ATTACHMENT ST.HL-AE oWI3 STP FSAR PAGE O~Fi'L-hose lengths of 100 ft are utilized as permitted by NFPA 14'. The system l 47 design is such that all locations in the building are within reach of at least one hose stream. Braided, noncollapsible hoses installed on hose reels are used throughout the TGB.
Backup fire protection is provided by portable fire extinguishers. The type, i size, number, and locations of these extinguishers are determined by the l 55 i nature of the hazards, but in all cases meet or exceed the requirements of l 47 i NFPA 10:@T The water spray fixed systems, standpipe and hose systems, and preaction l 12 sprinkler systems installed in the TCB are supplied with water from a 6-in.
-diameter pipe header, having a U-shaped configuration, installed beneath the mezzanine level. The ends of the header are connected to the plant underground ring main system at widely separated points. The header is norma-lly supplied with water from both points of the main, but isolating valves of the post indicator type are provided at the connections to the main, such that the header may be supplied from one point only in the event of damage to part of the main.
In addition, isolating valves of the outside screw and yoke type are installed at each end of the header at the inlets to the building, and also at strategic intervals around the header to permit isolation of any damaged section.
l 12 All pipe connections from the header to fire protection systems and standpipes are provided with isolating valves as they leave the header, such that the isolation of any system does not affect the operability of any other system.
The automatic wet pipe sprinkler systems in the TCB are supplied with water directly from the underground ring main. In addition, a backup supply is 12 provided from the TCB internal header.
9.5.1.2.12 Turbine Lube 011 Area: The turbine lube oil area comprises a l47 lube oil reservoir, clean and dirty oil storage tanks, and a lube oil condi-tioner located outdoors and adjacent to the southwest corner of the TCB. The lube oil reservoir is a horizontally positioned cylindrical steel tank, 114 in. in diameter by 432 in. in length, located on a curbed concrete slab at El. 44.0 ft. The clean and dirty oil tanks are cylindrical steel tanks, of 23,000 gallons each, located at El 21.5 ft below the reservoir. Two-hour fire-rated walls are provided for the TGB adjacent to the lube oil area for exposure protection.
The lube oil area is protected by two independent water spray fixed systems: !
one for the reservoir at El. 44.0 ft and one for the tanks and conditioner below. These systems utilize solid cone directional spray nozzles to provide essentially complete direct impingement onto exposed surfaces of the equip-ment, including floor areas within the curbs. The spray systems are designed ,
l in accordance with the requirements of NFPA 15,Tnd the design densities are l47 l 0.25gpm/ft{
l Water is supplied for these systems directly from the underground ring main. I The discharge for each system is controlled by an electrically operated deluge l valve located within the TCB, actuated by the Fire Detection System for the lube oil area (see Section 9.5.1.2.19). In case of failure of the deluge g valve electrical operator, or total failure of both the primary and backup 9.5-11 Amendment 55 l
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ATTACHMENT STP FSAR ST.HL AE 30'13
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9.5.1.2.18 HVAC Carbon Filters: A} fixed water spray deluge system is provided for the HVAC carbon filters in the EAB, MAB, FHB and RCB of each unit. The areas of protection are as follows:
M\Ae e , Cleanup UnityEAB El 10'-0" c,p.\ k.=**
e Cleanup Unit3 EAB El. 35'-0" g$.t A..--
e , Cleanup Unit,EAB El. 60'-0" AW 15 5 e Technical Support CenterpUnit EAB El. 86' 0" 3
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, Makeup Unit)EAB El. 86'-0" e C'[y\(l..*-
Makeup Unitj EAB El. 86'-0"
.u e , ^Makeup Unitj EAB El. 86'-0" is W e
SampleRoomUni$MABEl.41'-0" 3 ,
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- c. W Radiation Chemistry 1.ab , Unit j MAB El. 41' 0" s,b e HVAC Exhaust Subsystem,Unitj FHB El. 30'-0" W
e HVAC Exhaust Subsystem, Unit y FHB El. 30'-0" e
f.W 55 HVAC Exhaust Subsystem, Unity FHB El 42'-6" f.W e HVAC Exhaust Subsystem, Unit y FHB El. 42' 6" (W
e HVAC Exhaust Subsystem, Unit 3 FHB El. 53' 3" e
(W H/AC Exhaust Subsystem, Unit,FHB El. 53'-3" e Nontainment Carbon Filter Unity RCB El. 52'-0" e Containment Carbon Filter Unit3 RCB El. 52'-0" i
The deluge system to each of q the carbon filters is designed in accordance with the requirements of NFPA 15fw[th a design density of not less than 0.25 gpm/fta for hori::ontal beds and 3.2 gpm/f t 8 for vertical beds.
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Dual setpoint continuous thermistor type detectors are provided to alarm both high and high high charcoal temperatures. The deluge valves are manually actuated by hand switches located in the control room and locally. p 9.5.1.2.19 Fire Protection Detection. Control, and Alarm Svstem:
A comprehensive Fire Detection, Control, and Alarm System is installed throughout the plant. The primary operation of this system is automatically governed by a series of local control panels conveniently located throughout the plant.
The Fire Protection System control panels monitor the general plant area fire detectors and monitor and/or control all of the special hazard fire protection systems to ensure their continuous availability. Alarms are transmitted from the local panels to the fire protection data acquisition system in the main control room.
( -i put modow6t Mw g 9.51) Amendment $8 e .,s m es o , m % g ,e, e % d%e . . ~ t h N c u b m M hc3 g g p u h.
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- ATTACHMENT ST HL-AE- G<fD '
STP FSAR P.AG.E g OF 13-9.5.1.2.19.4 Preaction Sprinkler Systems (Manus 1)' - The TG bearings are l 47 i( protected by a preaction sprinkler system. The fire detectors used are ther.
mostatic, spot-type heat detectors with rate compensation.
I A control panel continuously monitors the Fire Detection System associated with each preaction sprinkler system. -Upon receipt of an indication of fire from any detector, the panel activates a fire alarm bell in the protected i area. A visible indication is provided on the panel to show which system is indicating a fire alarm.
Manual switches are located in the main control' room to manual-electrically l i open an electrically actuated deluge valve that controls the water supply to , 55 each proaction sprinkler system. Water is then admitted to the system and discharges from any sprinkler heads that open. A " water flowing" alarm is i also provided in the area of the bearings and in the control room. Upon receipt of this alarm, the operator is assured that the deluge valve has operated.
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In addition to monitoring fire conditions, the panels monitor other conditions necessary to ensure the availability and proper operation of each detection and preaction sprinkler system. Upon receipt of any off-normal condition, i visible and audible indications of the trouble are provided at the panel.
The off-normal conditions include:
i o
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55 Detection circuit trouble
'( o Delugevalvesolenoidcircuittrouble(,TG O o Water flow switch circuit trouble l 47 ,
o System low water pressure I
.o System isolating valve closed o Control panel primary power failure l
l A pair of normally open contacts is provided in the appropriate control panel II 47 ,
l for " trouble" and " fire" conditions for each preaction sprinkler system. The l j contacts are designed to close upon receipt of these conditions and are used -
t to initiate alarms in the control room (see Section 9.5.1.2.19.12). ,
9.5.1.2.19.5 Preaction Sprinkler System (Automatic) - The areas pro-b tected by theofautomatic and portions preaction the Administration sprinkler Building systems and the Lighting are Diesel the DGB engine Generator 4
Building. Control panels continuously monitor the Fire Detection Systems associated with each preaction sprinkler system. l 12
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i j' Two complete detection circuits are provided for each system to protect the 47
< DGB engine rooms and the Lighting Diesel Generator Building. The fire detec-i tors used are thermostatic, spot-type heat detectors with rate compensation. i The two detection circuits utilize the cross-zone principle, by which, upon I j receipt of an indication of fire from one detection circuit, a control panel j
- i. will annunciate a " fire alert." Upon receipt of an indication of fire from l l( ) both detection circuits concurrently, a control panel automatically opens the electrically actuated deluge valve that controls the water supply to the l
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9.5 19 Amendment 55 i
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ATTACHMENT
. ST.HL-AE do? 3 STP FSAR PAGE l 0_OF t 9-The fire detectors used for water spray systems protecting hazards other than
- cabling areas are thermostatic, spot-type heat detectors with rate compen-1 sation or continuous thermistor type in the. case of HVAC carbon filters. l47 Control panels continuously monitor the Fire Detection System associated with each of the water spray fixed systems. Upon receipt of an indication of fire 3
from any detector, the appropriate control panel automatically opens the elec-trically actuated deluge valve that controls the water supply to the spray system associated with that detector. The panel also activates a fire alarm bell local to the protected area. A visible indication-is provided on the panel to show which system is indicating a fire alarm. The HVAC carbon fil- l55
- ' tersdelugevalves{aremanual-electricallyactuated.
l wa Rc6 ch b5 dest velvto In addition to monitoring for fire conditions, the panels monitor other condi- l47 1
- _tions necessary to ensure the availability and proper operation of each detec-i' tion and water spray system. Upon receipt of any off-normal condition, visi-ble and audible " trouble" indications are provided at the appropriate panel.
The off-normal conditions include:
i e Detection circuit trouble e Deluge valve solenoid circuit trouble
.l e Water flowing switch circuit trouble l
} e Manual fire alarm switch circuit trouble p5 lk e System low water pressure (47 e System isolating valve closed I e e
bh d.\db3 Mn orm(W A C. M.m bbf e Control panel primary power failure A pair of normally open contacts is provided in the appropriate control panel l47 l for " trouble" and " fire" conditions for each water spray fixed system. The' contacts are designed to close upon receipt of these conditions and are used to initiate alarms in the control room (see Section 9.5.1.2.19.12). l '.'
- 9.5.1.2.19.7 Standpipe Systems (Vet) - A list of areas protected by l 47
- standpipe systems is provided in Table 9.5-3. These systems are manual and j normally wet, and there is no automatic retion required from a local control j panel for these systems to be operated.
! Control panels do, however, monitor conditions necessary to ensure the avail-j ability and proper operation of each system. Upon receipt of any off-normal i
condition, visible and audible " trouble" indications are provided at the i appropriate panel, l
- The off normal conditions include
j e System isolating valve closed
- {j e System low water pressure l55 i e Control panel primary power failure f 9.5 21 Amendment 55 i
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ATTACHMENT ST.HL AE MU
! STP FSAR PAGE il 0F l} -- ,
The operability of fire protection systems required to protect safe shutdown capability will be assured through the implementation of an administrative
, program similar to the requirements of Revisien 5 of NUREG-0452. This program 4
will include testing requirements, compensatory actions for systems out of 58
- service, and QA audits of program implementation. It will cover those systems, including suppression systems, detection systems, and fire barriers, which are identified in the Fire Hazards Analysis Report as protecting areas / zones containing safe shutdown equipment or cabling.
I Other fire protection systems and equipment will not be included in the administrative or QA programs described above; however, operability testing of
.i a similar nature will be conducted as necessary for property protection and J personnel safety reasons. The need for compensatory actions will be evaluated
- on a case by case basis.
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9.5.1.6.2_ Fire Brigade: A five member fire brigade consisting of the l Chemical Operations Foreman (Brigade Leader) and four other members of the - MO.
- Chemical Operations shift crew will be maintained'on each shift. These ;
4 employees will receive annual physical examinations for strenuous activity and J
will be given training on safety-related systems and other systems as neces-j sary.
Fire brigade members will be provided with protective equipment as described
, below: -
- 1. Turnout gear including bunker coat, boots, gloves, helmet, and self con-l tained breathing apparatus (SCBA). At least 10 SCBAs with full-face 1 positive-pressure masks will be available for fire brigade personnel.
l 2. Portable lights.
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- 3. Communications equipment.
- 4. Ventilation equipment.
- 5. Portable extinguishers.
, At least one hour of extra air in bottles will be available onsite for each of j the ten SCBAs. In addition, a sufficient supply of air will be maintained onsite to supply the five man fire brigade for six hours, g
( The fire brigade training program will include initial training, periodic 4 retraining, and fireground practice sessions. Additional information con- .
cerning fire protection training including fire brigade training, general l employee training, training for offsite fire departments, and contractor / tem. .
i porary employee training is provided in Section 13.2.3. )
f Each shift fire brigade will conduct planned quarterly meetings to review changes in the fire protection program, plant modifications, changes in fire preplans, and other related subjects of interest.
I Drills will be conducted quarterly for each shift fire brigade. Watch station
, assignments will be considered in planning drills i an effort to ensure that j ( each fire brigade member participates in at least7 drillfperyear. Addi. l l tional information concerning frequency, purpose, and content of drills is j i provided in Section 13.2.3. i j 9.5 28 Amendment 58 l
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l STP FSAR ATTACHMENT j
. o . ST HL-AE 433 PAGE_lSOFl l Table 9.5-2 CODES, STANDARDS AND REGUI.ATIONS
, )
ISSUED BY NUMBER TITLE-NFPA 10-1975 Portable Fire Extinguishers NFPA 11-1976 Foam Extinguishing Systems NFPA 12A-1977 Halon 1301 Extinguishing Systems NFPA 13-1976 Sprinkler Systems NFPA 14-1976 Standpipe and Hose Systems NFPA 15-1977 Water Spray Fixed Systema j NFPA 16-1974 Deluge Foam-Water Sprinkler Systems
! and Foam Water Spray Systems NFPA 20-1976 Centrifugal Fire Pumps NFPA 22-1976 Water Tanks NFPA 24-1973 Private Fire Service Mains and 47 3
4 their Appurtenances
.4 il,161 NFPA 30 ,1SR Flammable and Combustible Liquids Code i NFPA 37-1975 Installation and Use of Stationary l Combustion Engines and Gas Turbines ,
l NFPA 50A-1973 Gaseous Hydrogen Systems i NFPA 72D-1975 Proprietary Protective Signalling Systems NFPA 72E-1978 Automatic Fire Detectors
- NFPA 232-1975 Protection of Recorde l
- NFPA 194-1974 Screw Threads and Gaskets for Fire Hose j connections i l W74 NFPA 196 M Fire Hose
! N PA S t, - iris p<g Q Fln '6<53 *cktd i, ea F-PA H g .(gqi H.e,Mo n Chw".cd th}g I NFPA ,3 . igg o t. 3NmgNeMn I
ranPA 3 o . gs s ah.J t.Ac<Av;<. C .la:.
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I 9.5-59d Amendment 47
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