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Category:CORRESPONDENCE-LETTERS
MONTHYEARNOC-AE-000675, Forwards Clarification on Items Included in 990531 Response to RAI Re Proposed License Amend Associated with Operator Action for Sbloca,As Requested1999-10-21021 October 1999 Forwards Clarification on Items Included in 990531 Response to RAI Re Proposed License Amend Associated with Operator Action for Sbloca,As Requested NOC-AE-000680, Forwards Rev 5 to 0PGP03-ZV-0001, Severe Weather Plan1999-10-20020 October 1999 Forwards Rev 5 to 0PGP03-ZV-0001, Severe Weather Plan NOC-AE-000683, Forwards 30-day Rept Concerning Significant Changes to Accepted Large Break Loss of Coolant Accident ECCS Evaluation Model for South Tx Project,Units 1 & 2,IAW 10CFR50.46(a)(3)(ii)1999-10-19019 October 1999 Forwards 30-day Rept Concerning Significant Changes to Accepted Large Break Loss of Coolant Accident ECCS Evaluation Model for South Tx Project,Units 1 & 2,IAW 10CFR50.46(a)(3)(ii) ML20217K9341999-10-15015 October 1999 Forwards SER Accepting Util 990609 Relief Request RR-ENG-2-4 for Relief from ASME Code,Section XI, Nondestructive Exam Requirements Applicable to Stp,Units 1 & 2,reactor Vessel Closure Head Nuts ML20217K9091999-10-15015 October 1999 Forwards SER Accepting Util 990609 Relief Request RR-ENG-2-3 from ASME Code,Section Xi,Nondestructive Exam Requirements Applicable to South Texas Project,Units 1 & 2, Pressurizer Support Attachment Welds 05000498/LER-1999-008, Forwards LER 99-008-00 Re Turbine Trip That Occurred While Performing Main Turbine Emergency Trip Test.Commitments Made by Licensee Are Listed in Corrective Actions Section of LER1999-10-12012 October 1999 Forwards LER 99-008-00 Re Turbine Trip That Occurred While Performing Main Turbine Emergency Trip Test.Commitments Made by Licensee Are Listed in Corrective Actions Section of LER NOC-AE-000674, Forwards Requested Estimates of Needs for Operator Licensing Exams,Per AL-99-03, Operator Licensing National Exam Schedule1999-10-12012 October 1999 Forwards Requested Estimates of Needs for Operator Licensing Exams,Per AL-99-03, Operator Licensing National Exam Schedule NOC-AE-000625, Requests Partial Relief from ASME Section XI Visual Exam Requirements of IWA-5242(a).Relief Request Is Based on Provisions of Draft ASME Section XI Code Case N-616,which Is Expected to Be Published in Near Future1999-10-0707 October 1999 Requests Partial Relief from ASME Section XI Visual Exam Requirements of IWA-5242(a).Relief Request Is Based on Provisions of Draft ASME Section XI Code Case N-616,which Is Expected to Be Published in Near Future NOC-AE-000610, Requests Relief from ASME Section XI Code Nondestructive Exam Requirements of IWA-5250(a)(2) for Second Inservice Insp Interval,Per Provisions of 10CFR50.55a(3)(i)1999-10-0707 October 1999 Requests Relief from ASME Section XI Code Nondestructive Exam Requirements of IWA-5250(a)(2) for Second Inservice Insp Interval,Per Provisions of 10CFR50.55a(3)(i) NOC-AE-000653, Requests Relief from ASME Section XI Code Requirements of Table IWE-2500-1 for VT-3 Visual Exam of Seals & Gaskets on Airlocks,Hatches & Other Devices Required to Assure Containment leak-tight Integrity,Per 10CFR50.55a(a)(3)(i)1999-10-0707 October 1999 Requests Relief from ASME Section XI Code Requirements of Table IWE-2500-1 for VT-3 Visual Exam of Seals & Gaskets on Airlocks,Hatches & Other Devices Required to Assure Containment leak-tight Integrity,Per 10CFR50.55a(a)(3)(i) ML20217C3221999-10-0707 October 1999 Forwards Insp Repts 50-498/99-16 & 50-499/99-16 on 990808-0918.No Violations Noted.Insp Generally Characterized by safety-conscious Operations,Sound Engineering & Maint Practices & Careful Radiological Work Controls 05000499/LER-1999-006, Forwards LER 99-006-00,re Entry Into TS 3.0.3.Licensee Commitments Listed in Corrective Actions Section of Attachment1999-09-30030 September 1999 Forwards LER 99-006-00,re Entry Into TS 3.0.3.Licensee Commitments Listed in Corrective Actions Section of Attachment ML20212L1651999-09-30030 September 1999 Responds to STP Nuclear Operating Co 981012 & s Which Provided Update to TS Bases Pages B 3/4 8-14 Through B 3/4 8-17.NRC Staff Found Change Consistent with TS 3/4.8.2 DC Sources. Staff Found & Deleted Typographical Error NOC-AE-000664, Forwards Rev 1 to STP Electric Generating Station Unit 1 Cycle 9 COLR & Rev 1 to STP Electric Generating Station Unit 2 Cycle 7 Colr1999-09-30030 September 1999 Forwards Rev 1 to STP Electric Generating Station Unit 1 Cycle 9 COLR & Rev 1 to STP Electric Generating Station Unit 2 Cycle 7 Colr ML20212J7141999-09-29029 September 1999 Forwards Insp Repts 50-498/99-15 & 50-499/99-15 on 990920-24 at South Texas Project Electric Generating Station.No Violations Noted.Insp Covered Requalification Training Program & Observation of Requalification Activities NOC-AE-000646, Informs NRC That STP Nuclear Operating Co Is Y2K Ready IAW Nei/Nusmg 97-07 Guidelines & Also Provides Response to NRC Ltr1999-09-28028 September 1999 Informs NRC That STP Nuclear Operating Co Is Y2K Ready IAW Nei/Nusmg 97-07 Guidelines & Also Provides Response to NRC Ltr ML20212J0651999-09-27027 September 1999 Discusses Licensee 980330 Response to GL 97-06, Degradation of SG Internals. Concludes That Response to GL Provides Reasonable Assurance That Condition of SG Internals in Compliance with Current Licensing Bases for Facility ML20212F1791999-09-24024 September 1999 Discusses 990923 Meeting Conducted in Region IV Ofc Re Status of Activities to Support Confirmatory Order, ,modifying OL & to Introduce New Director,Safety Quality Concerns Program.List of Attendees Encl ML20212E9091999-09-23023 September 1999 Discusses GL 98-01, Year 2000 Readiness of Computer Sys at Npps, Supplement 1 & STP Nuclear Operating Co Response for STP Dtd 990629.Understands That at Least One Sys or Component Listed May Have Potential to Cause Transient ML20212F2111999-09-22022 September 1999 Forwards Review of SG 90-day Rept, South Texas Unit-2 Cycle 7 Voltage-Based Repair Criteria Rept, Submitted by Util on 990119 NOC-AE-000633, Forwards Rev 3 to SG-99-04-005, STP 1RE08 Outage Condition Monitoring Rept & Final Operational Assessment. Rept Satisfies Reporting Requirements of NEI 97-06,dtd Dec 19971999-09-21021 September 1999 Forwards Rev 3 to SG-99-04-005, STP 1RE08 Outage Condition Monitoring Rept & Final Operational Assessment. Rept Satisfies Reporting Requirements of NEI 97-06,dtd Dec 1997 NOC-AE-000634, Forwards Addl Info Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Povs. MOV design-basis Review Checklist,Encl1999-09-21021 September 1999 Forwards Addl Info Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Povs. MOV design-basis Review Checklist,Encl NOC-AE-000649, Forwards Current Annual Financial Data for STP Electric Generating Station Per 10CFR50.71(b),acting on Behalf of Central Power & Light Co,City of Austin,Tx,City Public Svc Board of San Antonio & Hl&P1999-09-21021 September 1999 Forwards Current Annual Financial Data for STP Electric Generating Station Per 10CFR50.71(b),acting on Behalf of Central Power & Light Co,City of Austin,Tx,City Public Svc Board of San Antonio & Hl&P 05000499/LER-1999-005, Forwards LER 99-005-00,re Esfa Following Loss of Power to Standby Transformer 2 Due to Electrical Fault.Licensee Commitments Are Listed in Corrective Actions Section of LER1999-09-20020 September 1999 Forwards LER 99-005-00,re Esfa Following Loss of Power to Standby Transformer 2 Due to Electrical Fault.Licensee Commitments Are Listed in Corrective Actions Section of LER ML20212D9171999-09-16016 September 1999 Informs That on 990818,NRC Completed Midcycle PPR of South Texas Project & Identified No Areas in Which Performance Warranted Insp Beyond Core Insp Program.Details of Insp Plan Through Mar 2000 & Historical Listing of Plant Issues,Encl ML20216F5471999-09-15015 September 1999 Discusses 990914 Meeting Conducted at Region Iv.Meeting Was Requested by Staff to Introduce New Management Organization to Region IV & to Discuss General Plant Performance & Mgt Challenges IR 05000498/19990121999-09-14014 September 1999 Forwards Insp Repts 50-498/99-12 & 50-499/99-12 on 990816-19.Three Violations Occurred & Being Treated as Ncvs. Areas Examined During Insp Included Portions of Access Authorization & Physical Security Programs 05000498/LER-1999-007, Forwards LER 99-007-00 Re Train 'B' CR Makeup & Cleanup Filtration Sys Being Inoperable for Greater than Aot.Util Intends to Append Addl Info Section of LER with Brief Description of Test Results,Rather than Submit Separate LER1999-09-13013 September 1999 Forwards LER 99-007-00 Re Train 'B' CR Makeup & Cleanup Filtration Sys Being Inoperable for Greater than Aot.Util Intends to Append Addl Info Section of LER with Brief Description of Test Results,Rather than Submit Separate LER ML20211P8201999-09-0909 September 1999 Forwards SE Authorizing 990224 Submittal of First 10-year Interval ISI Program Plan - Relief Request RR-ENG-24,from ASME Section XI Code,Table IWC-2500-1 NOC-AE-000638, Forwards License Renewal Applications & Certifications of Medical Exam for Seven Listed Licensed Operators at Stp,Per 10CFR55.57.Encl Withheld,Per 10CFR2.790(a)(6)1999-09-0909 September 1999 Forwards License Renewal Applications & Certifications of Medical Exam for Seven Listed Licensed Operators at Stp,Per 10CFR55.57.Encl Withheld,Per 10CFR2.790(a)(6) ML20211P7671999-09-0909 September 1999 Forwards SER Authorizing Licensee 990517 Alternative Proposed in Relief Request RR-ENG-2-8 to Code Case N-491-2 for Second 10-year Insp Interval of South Texas Project, Units 1 & 2,pursuant to 10CFR50.55a(a)(3)(i) ML20211P7871999-09-0909 September 1999 Forwards Safety Evaluation Re First 10-yr Interval Inservice Insp Program Plan Request for Relief RR-ENG-31 IR 05000498/19990141999-09-0303 September 1999 Forwards Insp Repts 50-498/99-14 & 50-499/99-14 on 990627-0807.Apparent Violations Identified & Being Treated as Noncited Violations Consistent with App C of Enforcement Policy NOC-AE-000562, Requests Relief from Contruction Code non-destructive Exam Requirements for Repair/Replacement Activities During Second Inservice Insp Interval of Units 1 & 2,IAW Provisions of 10CFR50.55a(a)(3)(i)1999-08-31031 August 1999 Requests Relief from Contruction Code non-destructive Exam Requirements for Repair/Replacement Activities During Second Inservice Insp Interval of Units 1 & 2,IAW Provisions of 10CFR50.55a(a)(3)(i) ML20212A4351999-08-27027 August 1999 Discusses Investigation Rept OI-4-1999-009 Re Activites at South Texas Project.Oi Investigation Initiated in Response to Alleged Employment Discrimination Complaint. Allegation Not Substantiated.No Further Action Planned NOC-AE-000617, Forwards semi-annual Fitness for Duty Program Performance Rept for 990101-990630,IAW 10CFR26.71(d)1999-08-26026 August 1999 Forwards semi-annual Fitness for Duty Program Performance Rept for 990101-990630,IAW 10CFR26.71(d) ML20211J2511999-08-26026 August 1999 Discusses Proposed TS Change on Replacement SG Water Level Trip Setpoint for Plant,Units 1 & 2 NOC-AE-000585, Provides Notification That South Texas Project Has Completed Integrity Evaluation of Units 1 & 2 Reactor Coolant Pump Casings Required by Paragraph (D) of Code Case N-4811999-08-25025 August 1999 Provides Notification That South Texas Project Has Completed Integrity Evaluation of Units 1 & 2 Reactor Coolant Pump Casings Required by Paragraph (D) of Code Case N-481 ML20211F4421999-08-24024 August 1999 Forwards SE Authorizing Licensee 990513 Request for Relief RR-ENG-2-13,seeking Relief from ASME B&PV Code Section Xi,Exam Vessel shell-to-flange Welds for Second ISI Intervals ML20211F5031999-08-23023 August 1999 Forwards SE Authorizing Licensee 990315 Request for Relief RR-ENG-30,seeking Relief from ASME B&PV Code,Section Xi,Nde Requirements Applicable to Stp,Unit 2 SG Welds ML20212A4391999-08-17017 August 1999 Discusses Investigation Rept OI-4-1999-023 Re Activities at South Texas Project.Oi Investigation Initiated in Response to Alleged Employment Discrimination for Initiating Condition Report to Document Unauthorized Work Practices ML20210U1271999-08-16016 August 1999 Forwards Insp Repts 50-498/99-08 & 50-499/99-08 on 990517-21 & 0607-10.No Violations Noted.Corrective Action Program Was Reviewed ML20211A9501999-08-12012 August 1999 Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl ML20211B7881999-08-10010 August 1999 Transmits Summary of Two Meetings with Risk-Informed TS Task Force in Rockville,Md on 990514 & 0714 ML20210L1461999-08-0303 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams NOC-AE-000603, Informs of Addition of Restriction to SRO License 42658, for KM Espinoza,Effective 990721,per 10CFR50.74.Encl Info Withheld,Per 10CFR2.790(a)(6)1999-07-29029 July 1999 Informs of Addition of Restriction to SRO License 42658, for KM Espinoza,Effective 990721,per 10CFR50.74.Encl Info Withheld,Per 10CFR2.790(a)(6) NOC-AE-000470, Forwards Amend 12 to STP Fire Hazards Analysis Rept. Summary of Changes Made Under Provision of 10CFR50.59 Also Encl1999-07-28028 July 1999 Forwards Amend 12 to STP Fire Hazards Analysis Rept. Summary of Changes Made Under Provision of 10CFR50.59 Also Encl NOC-AE-000599, Forwards STP Unit 1,Cycle 9 Startup Testing Summary Rept. No New Licensing Commitments Contained in Ltr1999-07-28028 July 1999 Forwards STP Unit 1,Cycle 9 Startup Testing Summary Rept. No New Licensing Commitments Contained in Ltr NOC-AE-000589, Forwards Rev to 1RE08 ISI Summary Repts for Repairs & Replacements & for Sys Pressure Tests,Corecting Date of End of Insp Interval Provided in Item 9 of from NIS-1 from 09/24/99 to 09/24/20001999-07-26026 July 1999 Forwards Rev to 1RE08 ISI Summary Repts for Repairs & Replacements & for Sys Pressure Tests,Corecting Date of End of Insp Interval Provided in Item 9 of from NIS-1 from 09/24/99 to 09/24/2000 ML20210F3851999-07-26026 July 1999 Forwards Exam Repts 50-498/99-301 & 50-499/99-301 on 990706- 15.Exam Included Evaluation of 9 Applicants for SO Licenses & 8 Applicants for RO Licenses 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARNOC-AE-000675, Forwards Clarification on Items Included in 990531 Response to RAI Re Proposed License Amend Associated with Operator Action for Sbloca,As Requested1999-10-21021 October 1999 Forwards Clarification on Items Included in 990531 Response to RAI Re Proposed License Amend Associated with Operator Action for Sbloca,As Requested NOC-AE-000680, Forwards Rev 5 to 0PGP03-ZV-0001, Severe Weather Plan1999-10-20020 October 1999 Forwards Rev 5 to 0PGP03-ZV-0001, Severe Weather Plan NOC-AE-000683, Forwards 30-day Rept Concerning Significant Changes to Accepted Large Break Loss of Coolant Accident ECCS Evaluation Model for South Tx Project,Units 1 & 2,IAW 10CFR50.46(a)(3)(ii)1999-10-19019 October 1999 Forwards 30-day Rept Concerning Significant Changes to Accepted Large Break Loss of Coolant Accident ECCS Evaluation Model for South Tx Project,Units 1 & 2,IAW 10CFR50.46(a)(3)(ii) NOC-AE-000674, Forwards Requested Estimates of Needs for Operator Licensing Exams,Per AL-99-03, Operator Licensing National Exam Schedule1999-10-12012 October 1999 Forwards Requested Estimates of Needs for Operator Licensing Exams,Per AL-99-03, Operator Licensing National Exam Schedule 05000498/LER-1999-008, Forwards LER 99-008-00 Re Turbine Trip That Occurred While Performing Main Turbine Emergency Trip Test.Commitments Made by Licensee Are Listed in Corrective Actions Section of LER1999-10-12012 October 1999 Forwards LER 99-008-00 Re Turbine Trip That Occurred While Performing Main Turbine Emergency Trip Test.Commitments Made by Licensee Are Listed in Corrective Actions Section of LER NOC-AE-000625, Requests Partial Relief from ASME Section XI Visual Exam Requirements of IWA-5242(a).Relief Request Is Based on Provisions of Draft ASME Section XI Code Case N-616,which Is Expected to Be Published in Near Future1999-10-0707 October 1999 Requests Partial Relief from ASME Section XI Visual Exam Requirements of IWA-5242(a).Relief Request Is Based on Provisions of Draft ASME Section XI Code Case N-616,which Is Expected to Be Published in Near Future NOC-AE-000610, Requests Relief from ASME Section XI Code Nondestructive Exam Requirements of IWA-5250(a)(2) for Second Inservice Insp Interval,Per Provisions of 10CFR50.55a(3)(i)1999-10-0707 October 1999 Requests Relief from ASME Section XI Code Nondestructive Exam Requirements of IWA-5250(a)(2) for Second Inservice Insp Interval,Per Provisions of 10CFR50.55a(3)(i) NOC-AE-000653, Requests Relief from ASME Section XI Code Requirements of Table IWE-2500-1 for VT-3 Visual Exam of Seals & Gaskets on Airlocks,Hatches & Other Devices Required to Assure Containment leak-tight Integrity,Per 10CFR50.55a(a)(3)(i)1999-10-0707 October 1999 Requests Relief from ASME Section XI Code Requirements of Table IWE-2500-1 for VT-3 Visual Exam of Seals & Gaskets on Airlocks,Hatches & Other Devices Required to Assure Containment leak-tight Integrity,Per 10CFR50.55a(a)(3)(i) 05000499/LER-1999-006, Forwards LER 99-006-00,re Entry Into TS 3.0.3.Licensee Commitments Listed in Corrective Actions Section of Attachment1999-09-30030 September 1999 Forwards LER 99-006-00,re Entry Into TS 3.0.3.Licensee Commitments Listed in Corrective Actions Section of Attachment NOC-AE-000664, Forwards Rev 1 to STP Electric Generating Station Unit 1 Cycle 9 COLR & Rev 1 to STP Electric Generating Station Unit 2 Cycle 7 Colr1999-09-30030 September 1999 Forwards Rev 1 to STP Electric Generating Station Unit 1 Cycle 9 COLR & Rev 1 to STP Electric Generating Station Unit 2 Cycle 7 Colr NOC-AE-000646, Informs NRC That STP Nuclear Operating Co Is Y2K Ready IAW Nei/Nusmg 97-07 Guidelines & Also Provides Response to NRC Ltr1999-09-28028 September 1999 Informs NRC That STP Nuclear Operating Co Is Y2K Ready IAW Nei/Nusmg 97-07 Guidelines & Also Provides Response to NRC Ltr NOC-AE-000633, Forwards Rev 3 to SG-99-04-005, STP 1RE08 Outage Condition Monitoring Rept & Final Operational Assessment. Rept Satisfies Reporting Requirements of NEI 97-06,dtd Dec 19971999-09-21021 September 1999 Forwards Rev 3 to SG-99-04-005, STP 1RE08 Outage Condition Monitoring Rept & Final Operational Assessment. Rept Satisfies Reporting Requirements of NEI 97-06,dtd Dec 1997 NOC-AE-000634, Forwards Addl Info Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Povs. MOV design-basis Review Checklist,Encl1999-09-21021 September 1999 Forwards Addl Info Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Povs. MOV design-basis Review Checklist,Encl NOC-AE-000649, Forwards Current Annual Financial Data for STP Electric Generating Station Per 10CFR50.71(b),acting on Behalf of Central Power & Light Co,City of Austin,Tx,City Public Svc Board of San Antonio & Hl&P1999-09-21021 September 1999 Forwards Current Annual Financial Data for STP Electric Generating Station Per 10CFR50.71(b),acting on Behalf of Central Power & Light Co,City of Austin,Tx,City Public Svc Board of San Antonio & Hl&P 05000499/LER-1999-005, Forwards LER 99-005-00,re Esfa Following Loss of Power to Standby Transformer 2 Due to Electrical Fault.Licensee Commitments Are Listed in Corrective Actions Section of LER1999-09-20020 September 1999 Forwards LER 99-005-00,re Esfa Following Loss of Power to Standby Transformer 2 Due to Electrical Fault.Licensee Commitments Are Listed in Corrective Actions Section of LER 05000498/LER-1999-007, Forwards LER 99-007-00 Re Train 'B' CR Makeup & Cleanup Filtration Sys Being Inoperable for Greater than Aot.Util Intends to Append Addl Info Section of LER with Brief Description of Test Results,Rather than Submit Separate LER1999-09-13013 September 1999 Forwards LER 99-007-00 Re Train 'B' CR Makeup & Cleanup Filtration Sys Being Inoperable for Greater than Aot.Util Intends to Append Addl Info Section of LER with Brief Description of Test Results,Rather than Submit Separate LER NOC-AE-000638, Forwards License Renewal Applications & Certifications of Medical Exam for Seven Listed Licensed Operators at Stp,Per 10CFR55.57.Encl Withheld,Per 10CFR2.790(a)(6)1999-09-0909 September 1999 Forwards License Renewal Applications & Certifications of Medical Exam for Seven Listed Licensed Operators at Stp,Per 10CFR55.57.Encl Withheld,Per 10CFR2.790(a)(6) NOC-AE-000562, Requests Relief from Contruction Code non-destructive Exam Requirements for Repair/Replacement Activities During Second Inservice Insp Interval of Units 1 & 2,IAW Provisions of 10CFR50.55a(a)(3)(i)1999-08-31031 August 1999 Requests Relief from Contruction Code non-destructive Exam Requirements for Repair/Replacement Activities During Second Inservice Insp Interval of Units 1 & 2,IAW Provisions of 10CFR50.55a(a)(3)(i) NOC-AE-000617, Forwards semi-annual Fitness for Duty Program Performance Rept for 990101-990630,IAW 10CFR26.71(d)1999-08-26026 August 1999 Forwards semi-annual Fitness for Duty Program Performance Rept for 990101-990630,IAW 10CFR26.71(d) NOC-AE-000585, Provides Notification That South Texas Project Has Completed Integrity Evaluation of Units 1 & 2 Reactor Coolant Pump Casings Required by Paragraph (D) of Code Case N-4811999-08-25025 August 1999 Provides Notification That South Texas Project Has Completed Integrity Evaluation of Units 1 & 2 Reactor Coolant Pump Casings Required by Paragraph (D) of Code Case N-481 NOC-AE-000603, Informs of Addition of Restriction to SRO License 42658, for KM Espinoza,Effective 990721,per 10CFR50.74.Encl Info Withheld,Per 10CFR2.790(a)(6)1999-07-29029 July 1999 Informs of Addition of Restriction to SRO License 42658, for KM Espinoza,Effective 990721,per 10CFR50.74.Encl Info Withheld,Per 10CFR2.790(a)(6) NOC-AE-000599, Forwards STP Unit 1,Cycle 9 Startup Testing Summary Rept. No New Licensing Commitments Contained in Ltr1999-07-28028 July 1999 Forwards STP Unit 1,Cycle 9 Startup Testing Summary Rept. No New Licensing Commitments Contained in Ltr NOC-AE-000470, Forwards Amend 12 to STP Fire Hazards Analysis Rept. Summary of Changes Made Under Provision of 10CFR50.59 Also Encl1999-07-28028 July 1999 Forwards Amend 12 to STP Fire Hazards Analysis Rept. Summary of Changes Made Under Provision of 10CFR50.59 Also Encl 05000498/LER-1999-006, Forwards LER 99-006-00 Re Automatic Reactor Trip Due to over-temp delta-temp Actuation.Licensee Commitments Are Listed in Corrective Actions Section of LER1999-07-26026 July 1999 Forwards LER 99-006-00 Re Automatic Reactor Trip Due to over-temp delta-temp Actuation.Licensee Commitments Are Listed in Corrective Actions Section of LER NOC-AE-000589, Forwards Rev to 1RE08 ISI Summary Repts for Repairs & Replacements & for Sys Pressure Tests,Corecting Date of End of Insp Interval Provided in Item 9 of from NIS-1 from 09/24/99 to 09/24/20001999-07-26026 July 1999 Forwards Rev to 1RE08 ISI Summary Repts for Repairs & Replacements & for Sys Pressure Tests,Corecting Date of End of Insp Interval Provided in Item 9 of from NIS-1 from 09/24/99 to 09/24/2000 NOC-AE-000582, Forwards 1RE08 ISI Summary Rept for Welds & Component Supports of STP Electric Generating Station,Unit 1. Summary Rept Satisfies Reporting Requirements of IWA-6000 of Section XI for Welds & Component Supports1999-07-26026 July 1999 Forwards 1RE08 ISI Summary Rept for Welds & Component Supports of STP Electric Generating Station,Unit 1. Summary Rept Satisfies Reporting Requirements of IWA-6000 of Section XI for Welds & Component Supports NOC-AE-000597, Forwards voltage-based Criteria 90-day Rept for SG Tube Exam Performed Under NRC GL 95-05 During Refueling Outage 1RE08. Rept Contains Info Required by Section 6.b of Attachment 2 to GL 95-051999-07-23023 July 1999 Forwards voltage-based Criteria 90-day Rept for SG Tube Exam Performed Under NRC GL 95-05 During Refueling Outage 1RE08. Rept Contains Info Required by Section 6.b of Attachment 2 to GL 95-05 NOC-AE-000598, Forwards Four Copies of 1RE08 Refueling Outage ISI Summary Rept for Steam Generator Tubing1999-07-23023 July 1999 Forwards Four Copies of 1RE08 Refueling Outage ISI Summary Rept for Steam Generator Tubing NOC-AE-00586, Forwards Results of Control Rod Testing,In Response to NRC Bulletin 96-01, Control Rod Insertion Problems, Dtd 960308.Core Map Provided to Assist in Understanding Test Data1999-07-21021 July 1999 Forwards Results of Control Rod Testing,In Response to NRC Bulletin 96-01, Control Rod Insertion Problems, Dtd 960308.Core Map Provided to Assist in Understanding Test Data NOC-AE-000595, Forwards Chapters 1.0 & 16.0 to Operations QA Plan for South Texas Project.Rev Is Strictly Administrative & All Content Was Previously Submitted to NRC on 990503 & 9906151999-07-21021 July 1999 Forwards Chapters 1.0 & 16.0 to Operations QA Plan for South Texas Project.Rev Is Strictly Administrative & All Content Was Previously Submitted to NRC on 990503 & 990615 NOC-AE-000518, Requests Exemption from Various Special Treatment Requirements of 10CFR50,as Described in Encls to Ltr.Stp Believes That Pilot Application Will Assist NRC in Development & Implementation of risk-informed 10CFR501999-07-13013 July 1999 Requests Exemption from Various Special Treatment Requirements of 10CFR50,as Described in Encls to Ltr.Stp Believes That Pilot Application Will Assist NRC in Development & Implementation of risk-informed 10CFR50 NOC-AE-000536, Submits Request for Exemption from Requirements of 10CFR50.34(b)(11),10CFR50,App A,Gdc 2 & 10CFR100,App a, Section VI(a)(3) Re Maint of Seismic Instrumentation.Revised Page to Procedure OERP01-ZV-IN01 Included1999-07-13013 July 1999 Submits Request for Exemption from Requirements of 10CFR50.34(b)(11),10CFR50,App A,Gdc 2 & 10CFR100,App a, Section VI(a)(3) Re Maint of Seismic Instrumentation.Revised Page to Procedure OERP01-ZV-IN01 Included NOC-AE-000580, Forwards Response to NRC 990415 RAI Re Implementation of Commitments Related to GL 89-10, Safety-Related MOV Testing & Surveillance & GL 96-05, Periodic Verification of Design Basis Capability of Safety-Related Movs1999-07-13013 July 1999 Forwards Response to NRC 990415 RAI Re Implementation of Commitments Related to GL 89-10, Safety-Related MOV Testing & Surveillance & GL 96-05, Periodic Verification of Design Basis Capability of Safety-Related Movs NOC-AE-000574, Forwards ISI Summary Repts for Repairs & Replacements & for Sys Pressure Tests Performed Between 971004 & Completion of Eighth RO on 9904281999-07-0606 July 1999 Forwards ISI Summary Repts for Repairs & Replacements & for Sys Pressure Tests Performed Between 971004 & Completion of Eighth RO on 990428 NOC-AE-000557, Requests Relief from ASME Section XI Code Nondestructive Exam Requirements of App III,III-3410 for Second ISI Interval.Proposed Alternatives for Ultrasonic Exam of Piping Sys Welds,Attached1999-07-0606 July 1999 Requests Relief from ASME Section XI Code Nondestructive Exam Requirements of App III,III-3410 for Second ISI Interval.Proposed Alternatives for Ultrasonic Exam of Piping Sys Welds,Attached NOC-AE-000498, Requests Relief from ASME Section XI Code Nondestructive Exam Requirements Applicable to SG Main Steam Nozzle inside- Radius Sections.Attachment Includes Discussion of Basis & Justification for Request & Implementation Schedule1999-07-0606 July 1999 Requests Relief from ASME Section XI Code Nondestructive Exam Requirements Applicable to SG Main Steam Nozzle inside- Radius Sections.Attachment Includes Discussion of Basis & Justification for Request & Implementation Schedule NOC-AE-000573, Requests Relief from Requirements of ASME Section XI Code Case N-498,exempting Isolated Class 1 Reactor Vessel Head Vent Atmospheric Vent Piping & Valve from Being Tested at Full RCS Pressure1999-07-0606 July 1999 Requests Relief from Requirements of ASME Section XI Code Case N-498,exempting Isolated Class 1 Reactor Vessel Head Vent Atmospheric Vent Piping & Valve from Being Tested at Full RCS Pressure NOC-AE-000541, Submits Response to GL 98-01,Suppl 1, Y2K Readiness of Computer Systems at Npps. Readiness Disclosure for STP, Encl1999-06-29029 June 1999 Submits Response to GL 98-01,Suppl 1, Y2K Readiness of Computer Systems at Npps. Readiness Disclosure for STP, Encl NOC-AE-000571, Forwards Final Operating Exam Matls for STP Exam Scheduled for 990705.Revised Operating Exam Outline & post-validation Change Summary Has Been Included.Without Encls1999-06-24024 June 1999 Forwards Final Operating Exam Matls for STP Exam Scheduled for 990705.Revised Operating Exam Outline & post-validation Change Summary Has Been Included.Without Encls NOC-AE-000512, Responds to NRC 981201 Telcon Re Jco 93-0004,per Revised MSLB Analysis1999-06-23023 June 1999 Responds to NRC 981201 Telcon Re Jco 93-0004,per Revised MSLB Analysis NOC-AE-000560, Forwards LER 99-S02-00,re Failure to Maintain Positive Control of Vital Area Security Key.Licensee Commitments Are Found in Corrective Action Section of LER1999-06-23023 June 1999 Forwards LER 99-S02-00,re Failure to Maintain Positive Control of Vital Area Security Key.Licensee Commitments Are Found in Corrective Action Section of LER 05000498/LER-1999-005, Forwards LER 99-005-00,re Failure to Meet Requirements of TS Surveillance 3.7.1.2 Action B for Auxiliary FW Sys.Only Commitments Contained in Ltr Are Located in Corrective Action Section of LER1999-06-17017 June 1999 Forwards LER 99-005-00,re Failure to Meet Requirements of TS Surveillance 3.7.1.2 Action B for Auxiliary FW Sys.Only Commitments Contained in Ltr Are Located in Corrective Action Section of LER NOC-AE-000565, Forwards Amended Pages for Insertion Into South Texas Project Nuclear Operating Co Previously Submitted Response to NRC Rai.New Pages Include Expanded Answer to Question 4.b1999-06-16016 June 1999 Forwards Amended Pages for Insertion Into South Texas Project Nuclear Operating Co Previously Submitted Response to NRC Rai.New Pages Include Expanded Answer to Question 4.b NOC-AE-000548, Forwards Response to RAI Re Proposed Amends on Replacement SG Water Level Trip Setpoint Differences for Stp,Units 1 & 2.Nothing Contained in Response Should Be Considered Commitment Unless So Specified in Separate Correspondence1999-06-16016 June 1999 Forwards Response to RAI Re Proposed Amends on Replacement SG Water Level Trip Setpoint Differences for Stp,Units 1 & 2.Nothing Contained in Response Should Be Considered Commitment Unless So Specified in Separate Correspondence NOC-AE-000561, Forwards Change QA-042 to Operations QAP, Rev 13, Reflecting Current Organizational Alignment for STP & Culminating Organizational Realigment That Has Been Taking Place During Past Several Months1999-06-15015 June 1999 Forwards Change QA-042 to Operations QAP, Rev 13, Reflecting Current Organizational Alignment for STP & Culminating Organizational Realigment That Has Been Taking Place During Past Several Months NOC-AE-0559, Forwards STP Commitment Change Summary Rept for Period 981209-990610.Rept Lists Each Commitment for Which Change Was Made During Reporting Period & Provides Basis for Each Change1999-06-15015 June 1999 Forwards STP Commitment Change Summary Rept for Period 981209-990610.Rept Lists Each Commitment for Which Change Was Made During Reporting Period & Provides Basis for Each Change NOC-AE-000499, Forwards Relief Request RR-ENG-2-3,proposing to Perform Alternative Ultrasonic Examination from Outside Surface of Skirt Attachment Weld as Described in Encl,In Lieu of Surface Examination from Inside Pressurizer Skirt1999-06-0909 June 1999 Forwards Relief Request RR-ENG-2-3,proposing to Perform Alternative Ultrasonic Examination from Outside Surface of Skirt Attachment Weld as Described in Encl,In Lieu of Surface Examination from Inside Pressurizer Skirt NOC-AE-000502, Forwards Relief Request RR-ENG-2-6,proposing That Boroscopic VT-1 Visual Examination Be Allowed as Alternative to Section XI Surface Examination of Pump Casing Welds,Or Portions of Welds within Pits1999-06-0909 June 1999 Forwards Relief Request RR-ENG-2-6,proposing That Boroscopic VT-1 Visual Examination Be Allowed as Alternative to Section XI Surface Examination of Pump Casing Welds,Or Portions of Welds within Pits NOC-AE-000500, Forwards Relief Request RR-ENG-2-4,proposing to Perform Alternative Ultrasonic Examination from Outside & End Surfaces of Reactor Vessel Closure Head Nuts,As Described in Encl in Lieu of Surface Examination of Threaded Region1999-06-0909 June 1999 Forwards Relief Request RR-ENG-2-4,proposing to Perform Alternative Ultrasonic Examination from Outside & End Surfaces of Reactor Vessel Closure Head Nuts,As Described in Encl in Lieu of Surface Examination of Threaded Region NOC-AE-000545, Forwards Response to NRC 990416 RAI Re Util Proposed Amend on Operator Action for Small Break Loca, .Draft EOP Re Small Break Loca,Encl to Aid Discussion of Proposed Amend1999-05-31031 May 1999 Forwards Response to NRC 990416 RAI Re Util Proposed Amend on Operator Action for Small Break Loca, .Draft EOP Re Small Break Loca,Encl to Aid Discussion of Proposed Amend 1999-09-09
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- m. l May 1,1998 ST-NOC-AE-000154 STI 30610525 File No.: G20.02 G21.02 10CFR50.36 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 South Texas Project Unit 1 Docket No. STN 50-498 Request for Enforcement Discretion for Technical Specification 3.0.3 as It Anolies to Oncrability Reauirements for the Fuel Handline Buildine HVAC 1
STP Nuclear Operating Company (STPNOC) requests enforcement discretion from the provisions of Technical Specification 3.0.3 as it applies to the requirements of Technical l
Specifications 3.7.8(b) and 3.3.2 (Table 3.3-3, Functional Unit !1) to maintain three independent j Exhaust Booster Fans and three independent Main Exhaust Fans and required actuation l
instrumentation operable. Exhaust Booster Fan 11B has failed and must be replaced. The failed fan '
can be replaced within its 7 day allowed outage time. However, replacement of the fan will require ,
making the other two exhaust booster fans that share the common supply and exhaust plenums inoperable for the brief time needed to install and subsequently remove a temporary modification. ;
Specifically, STPNOC requests discretion from the requirement to apply Specification 3.0.3 for the 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> required to install the temporary modification and for 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> required to remove the ;
temporary modification so that repairs of FHB Exhaust Booster Fan 1iB can be completed. ;
i The attached information is provided pursuant to the Nuclear Regulatory Commission guidance for requests for enforcement discretion.
If you should have any questions concerning this matter please contact either A. W. /'
/
Harrison at (512) 972-7298 or J. R. Lovell at (512) 972-7799. /
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G. L. Parkey e oc/
Plant Manager, Unit 1
Attachment:
Information in Support of Requested Enforcement Discretion 9805130123 980501 PDR ADOCK 05000498 P PDR
r i: .
l NOC-AE-000154 I
File No.: G20.02 G21.02 Page 2 Ellis W. Merschoff Jon C. Wood Regional Administrator, Region IV Matthews & Branscomb '
U. S. Nuclear Regulatory Commission One Alamo Center 611 Ryan Plaza Drive, Suite 400 106 S. St. Mary's Street, Suite 700 Arlington, TX 76011-8064 San Antonio,TX 78205-3692 Thomas W. Alexion Institute of Nuclear Power Project Manager, Mail Code 13H3 Operations - Records Center U. S. Nuclear Regulatory Commission 700 Galleria Parkway Washington, DC 20555-0001 Atlanta, GA 30339-5957 David P. Loveless Richard A. Ratliff Sr. Resident Inspector Bureau of Radiation Centrol i
- c/o U. S. Nuclear Regulatory Commission Texas Department of Health l P. O. Box 910 1100 West 49th Street l _ Bay City, TX 77404-0910 Austin, TX 78756-3189 J. R. Newman, Esquire D. G. Tees /R. L. Balcom Morgan, Lewis & Bockius Houston Lighting & Power Co.
- 1800 M. Street, N.W. P. O. Box 1700 I Washington, DC 20036-5869 Houston,TX 772.~1 M. T. Hardt/W. C. Gunst Central Power and Light Company City Public Service ATTN: G. E. Vaughn/C. A. Johnson P. O. Box 1771 P. O. Box 289, Mail Code: N5012 San Antonio,TX 78296 Wadsworth,TX 77483 l A. Ramirez/C. M. Canady City of Austin Electric Utility Department 721 Barton Springs Road Austin.TX 78704
e Attachment
., , ST-NOC-AE-000154 Page 1 of 10 Information in Support of Requested Enforcement Discretion
- 1) The Technical Specification or other license conditions that will be affected.
Technical Specifications 3.7.8 and 3.3.2 (Table 3.3-3, Functional Unit i1) require ihree independent Exhaust Booster Fans and three independent Maiu Exhaust Fans and actuation instrumentation to be operable. In addition, Technical Specification 3.9.12 establishes requirements for FHB HVAC during movement of fuel. No discretion with respect to Specification 3.9.12 is necessary since STPNOC will comply with the applicable action of this specification not to move fuel or operate the crane over the spent fuel pool. (See Ccmpensatory Actions in Item 6, below.)
Operability of the Fuel Handling Building Exhaust Air System (FHBEAS) ensures that radioactive material leaking from the Err 1ency Core Cooling (ECC) equipment within the FHB following a loss of coolant accident @OCA) and radioactive material release from an accident involving an irradiated assembly in the FHB are filtered prior to reaching the environment.
Replacement of failed exhaust booster fan 11B will require a temporary modification to isolate the ductwork to the fan from the rest of the systan. The process ofinstalling and subsequently removing the temporary modification will require breaching the common exhaust and supply plenums serving the three exhaust booster fans. During the time the plenums are breached, the requirements of Specification 3.7.8 for the FHB HVAC system are not met. In addition, while the modification is being installed and removed, the other exhaust booster fans and the main exhaust fans will be put in pull-to-lock for personnel safety. In this condition, the system cannot automatically actuate and the requirements of Specification 3.3.2, Table 3.3-3, Functional Unit 11 are not met for all trains. Both of these conditions would require that Technical Specification 3.0.3 be entered.
- 2) The circumstance surrounding the situation, includine root causes, the need for promDt action and identification of any relevant historical events.
FHB Exhaust Booster Fan IIB tripped at 0140 hours0.00162 days <br />0.0389 hours <br />2.314815e-4 weeks <br />5.327e-5 months <br /> on April 30,1998 while it was Ung r: stored from a surveillance test. Maintenance personnel determined that the motor o .is grounded and will have to be replaced. The inoperable fan placed STP Unit ! in the ACTION statement of Technical Specification 3.7.8, with 7 days to restore the fan or be in at least hot standby in the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and cold shutdown in the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
Prompt action is requested to approve the enforcement discretion to allow replacement work to proceed on the failed fan. Restoring FHB Exhaust Booster Fan i IB to an operable
9 Attachment
., , ST-NOC-AE-000154 Page 2 of 10 status will require removal and replacement of the motor. As described in Item 1 above, plans for replacement of the fan involve installation and subsequent removal of a temporary modification to isolate the duct to the failed fan from the common supply and exhaust plenums. STPNOC estimates the installation of the temporary modification will take no longer than 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, and the removal of the temporary modification will take no longer than 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. STPNOC has scheduled the entire replacement evolution to be done well within the 7 day allowed outage time of a single failed fan. However, work to install the temporary modification cannot begin until the request for enforcement discretion is approved.
The NRC approved a very sirailar requested waiver of compliance for Exhaust Booster Fan 21C in August,1992. In that case, the NRC approved a waiver from the requirements of Specification 3.0.3 and denied a requested 3 day extension to the 7 day allowed outage time. l The replacement methodology and justification for this proposed enforcement discretion does not substantially differ from the 1992 case except that STPNOC is not requesting extension of the allowed outage time in this request.
The fan failed due to a ground on the motor, although the cause for the ground has not been determined. The current failure did not exhibit the same symptoms as the 1992 failure. In 1992, there were some precursor indications of potential failure whereas in this case no similar precursors were observed. It should be noted that the fan had a history of l satisfactory performance, and that these fans have generally provided satisfactory s :rvice. l There have been two failures of an exhaust booster fan since STP began operation. l STPNOC plans to send the failed fan motor off-site for evaluation. !
- 3) The safety baris for the reauest. including an evaluation of the safety sinnificance and potential consecuences of the proposed course of action.
The purpose of the Fuel Handling Building HVAC System is to mitigate the consequences of a fuel handling accident as well as a Loss-of-Coolant Accident (LOCA) by limiting plant site boundary dose to within the guidelines of10CFR100. This is accomplished by routing exhaust air from the spent fuel pool and the remainder of the FHB through ESF filter units containing HEPA filters and iodine removal carbon filters if high levels of airborne radioactivity are detected in the exhaust air (auto.matically upon an SI signal). i i
The major components of the exhaust air subsystem are:
Attachment
., , ST-NOC-AE-000154 Page 3 of 10 The three 50-percent-capacity exhaust booster fans are of the vaneaxial type. Tine fans are of the direct-drive type with single-speed motors. Fan .notors are totally enclosed, ;
air-cooled, and statically and dynamically balanced. I Normally, exhaust air bypasses the filter units and is exhausted directly to the plant main vent stack. Upon detection of high radiation or SI signal, exhaust air is routed through the filter units, the exhaust booster fans, and main exhaust air fans, and is then delivered to the plant main vent stack.
As noted above, only two accidents scenarios are relevant with regard to the FHB HVAC system. The Fuel Handling Accident will be precluded from occurring by ensuring that no loads will be carried over the Spent Fuel Pool and no movement ofirradiated fuel will take place during the time that the repair activities are occurring. The Large Break LOCA (LBLOCA), although clearly within the design basis of the plant,is a highly unlikely l occurrence. In the event that a LBLOCA were to occur, it would take a minimum of 16 minutes for the Refueling Water Storage Tank to empty and the Emergency Core Cooling system to go into the recirculation mode by taking suction from the containment sump. At that point in time it would be assumed that radiation leakage from the ECCS would occur that would require the FHB HVAC system to be functional.16 minutes is considered ample time to secure the work, restore the plenum and take the fans out of
- pull-to-lock and for the workers to exit the FHB. It should be noted that during the performance of the maintenance activities associated with the 1992 replacement that the plenum was easily restored.
In addition to the above, it should be noted that the Licensing Basis for the STP includes the Leak-Before- Break concept. This methodology has demonstrated that the deterministic LBLOCA is not a credible event arid that in fact any large pipe rupture of the Reactor Coolant System would be preceded by leakage that is detectable by Control Room personnel using instrumentation installed in the containment. The time between initiation of the leakage and the actual break would allow for additional time i.e., greater than 16 minutes, to restore the plenum and place the booster fans in the standby condition.
A qualitative risk assessment based on the proposed action has been performed. The LBLOCA is an unlikely event which contributes very little to Core Damage Frequency.
The probability that a LBLOCA would occur during the 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br /> requested is less than 0.2% of the annual probability of the LBLOCA. The probability that the compensatory actions would subsequently fail is also considered to be small, making the likelihood of any adverse consequences essentially not credible.
r i
Attachment l l
., ST-NOC-AE-000154 I Page 4 of 10 Based on the above, STPNOC believes that safety significance and potential l consequences of the proposed plan of action is extremely small.
l 4) The basis for the conclusion that the enforcement discretion is not a potential l detriment to the public health and safety and that neither an unreviewed safety l question nor a sienificant hazard considerations involved. I Determination of No Unreviewed Safety Question. !
- 1. Does the change involve a increase in the probability of occurrence or the consequences of an accident or malfunction of equipment important to safety j previously evaluated in the Safety Analysis Report? !
l The proposed change is to increase the allowable time specified in Technical 1 Specification 3.0.3 before a plant shutdown is required. No increase in the probability of an evaluated accident will occur due to this extension of a time l limit. The consequences of an accident also do not increase due to this change i
since the compensatory actions will be simple, straightforward, and well briefed I with all participants prior to starting this evolution. Closing an access door, i installing an 18 x 18 inch cover, and manually starting fans can be easily accomplished in the allowed time. In Modes 1 - 4 the purpose of the Fuel J j Handling Building Exhaust Air System is to filter ECCS radioactive leakage that :
occurs during the recirculation phase. Recirculation phase will not occur prior to i 16 minutes after an accident. Following an accident, the reactor will be I l automatically tripped. The plant announcement of this fact and direct communications with the control room will provide sufficient notification to 2 inform the personnel to restore the plenum integrity. The 16 minutes prior to radioactive ECCS leakage occurring is adequate time to secure the work, ensure that the plenum integrity is restored and the FHB Main and Exhaust Booster Fans started and for the workers to exit the FHB.
- 2. Does the change involve a possibility for an accident or malfunction of a different type than any evaluated previously in the Safety Analysis Report?
Delaying the plant shutdown required by Technical Specification 3.0.3 does not have the potential to create a new or different kind of accident from any previously evaluated. The system will continue to respond as required by the design with the compensatory measures established to restore plenum integrity.
f Attachment
, ST-NOC-AF-000154 Page 5 of 10 i
! 3. Does the change involve a reduction in the margin of safety as defined in the basis for any Technical Speci0 cation?
l The delay in plant shutdown required by Technical Specification 3.0.3 will not result in a reduction in the margin of safety since the compensatory measures will restore the Fuel Handling Building Exhaust Air System prior to the time it is required to remove contaminants in the accident condition.
t
! The unreviewed safety question evaluation above considers that the NRC paviously reviewed and approved an almost identical request for replacement of exhaust booster pump 21C in 1992. The conditions described in Houston Lighting & Power Company's ,
request for waiver of compliance dated August 18,1992 (ST-HL-AE-4185) and approved i by the NRC in letter dated August 19,1992 (ST-AE-HL-93160) are substantially the same as those evaluated in this request for discretion. The cumulative discretion time requested in this application is 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br /> vs.16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in the 1992 request.
Based on the above discussions and evaluations and the earlier NRC review and approval of a similar request, no Unreviewed Safety Question exists.
- Determination of No Sige!ficant Hazard Considerations South Texas Project has considered the criteria for assessing the potential of creating an unreviewed safety question or a significant hazards consideration with the exercising of enforcement discretion. In evaluating if discretion in enforcement constitutes a significant hazard the criteria of 10CFR50.92(c) is discussed below
- 1. Does the change involve a significant increase in the probability or l
consequence of an accident previously evaluated?
The proposed change is to increase the allowable time specified in Technical Specification 3.0.3 before a plant shutdown is required. This change will not increase the probability of an evaluated accident. The consequences of an accident also do not increase due to this extension in allowable time limits since the compensatory actions will be simple, straightforward, and well briefed prior to starting this evolution. In Modes 1 - 4 the purpose of the Fuel Handling Building Exhaust Air System is to tilter ECCS radioactive leakage that occurs during the recirculation phase. Recirculatioa phase will not occur prior to 16 minutes after an accident. Following an accident, the reactor will be automatically tripped. The plant announcement of this fact will provide sufficient notification to inform the personnel to restore the plenum integrity. The 16 minutes prior to radioactive ECCS leakage occurring is adequate time to secure the work, ensure that the
1 t
l Attachment l
' ST-NOC-AE-000154 )
l Page 6 of 10 I 1
1 plenum integrity is restored and the FHB Main and Exhaust Booster Fans started and for the workers to exit the FHB.
- 2. Does the change create the possibility of a new or different kind of accident I from any accident previously evaluated? !
Delaying the plant shutdown required by Technical Specification 3.0.3 does not have the potential to create a new or different kind of accident from any previously evaluated. The system will continue to respond as required by the design with the compensatory measures established to restore plenum integrity.
l
- 3. Does this change involve a significant reduction in a margin of safety? l The delay in plant shutdown required by Technical Specifications 3.0.3 will not result in a significant reduction in the margin of safety since the compensatory measures will restore the Fuel Handling Building Exhaust Air System prior to the l time it is required to remove contaminants in the accident condition.
Based on the above evaluation, no Significant Hazard exists.
Since there is no Unreviewed Safety Question or Significant Hazard associated with this fan replacement, there is no potential detriment to the public heath and safety as a result of this request.
l 5) The basis for the conclusion that the enforcement discretion will not involve adverse consequences to the environment.
The South Texas Project has reviewed the proposed Enfucement Discretion request and the l Nuclear Regulatog Commission Final Environmental Assessment for the South Texas l Project Units 1 and 2 and has concluded that pursuant to 10CFR51, there are no significant i
radiological or non-radiological impacts associated with the proposed Enforcement Discretion request.
! This proposed Enforcement Discretion has been evaluated against the criteria for and I
identification of licensing and regulatory actions requiring environmental assessment in accordance with 10CFR51.21. It has been determined that the proposed changes meet the criteria for categorical exclusion as provided for under 10CFR51.22(c)(9). The following is a discussion of how the proposed Enforcement Discretion meets the criteria for categorical exclusion.
I Attachment
, ST-NOC-AE-000154 Page 7 of 10 t
10CFR51.22(c)(9): Although the proposed change involves changes to requirements with I respect to installation or use of a facility component located within the restric'ed area; l
l (i) the proposed change involves no Significant Hazards Consideration (refer to the No Significant Hazards Consideration section of this Enforcement Discretion Request),
(ii) there is no significant change in the types or significant increase in the amounts of any effluent that may be released offsite since the proposed changes do not affect the generation of any radioactive effluent nor do they affect any of the permitted release paths, and (iii) there is no significant increase in individual or cumulative occupational radiation exposure.
Accordingly, the proposed change meets the eligibility criteria for categorical exclusion set forth in 10CFR51.22(c)(9). Based on the aforementioned and pursuant to 10CFR51.22(b),
no environmental assessment or environmental impact statement need be prepared.
- 6) Any proposed compensatory actions.
The following compensatory action will be taken:
- 1. Administrative controls will ensure that in the unlikely event that emergency operation is required, operators have adequate time to ensure that FHB Main and Exhaust Fan motors are manually sta1ed. The following defines the conditions where the Fuel Handling Building Exhtust Air System can be maintained available while the Fans are in the " Pull-to-Lock" position:
a) Prior to opening the FHB Exhaust Booster Fan common plenum access panels, Maintenance personnel will inform the Control Room of their intentions. This information will be noted in the Control Room Log. ,
b) Following the opening of the plenum access panels, Maintenance personnel will maintain a watchstander at each opening who is in continuous communication with the Control Room.
L c) If at any time during this process, the Maintenance personne! are made aware, either via loudspeaker or radio, that a reactor trip has occurred, then the work will be secured, loose material removed, personnel will exit the plenums, and the access panels reinstalled as expeditiously as possible. The Control Room will conflum via
( continuous communication that the access panels have been reinstalled.
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1 l
1 1
! Attachment
, , ST-NOC-AE-000154
) Page 8 of 10 d) Once confirmed that plenum integrity is restored, the Operator will manually ;
j start the required FHB Main and Exhaust Booster Fans, or place them in automatic, I as required.
c) If at any time during this process, the Control Room notices an increase in Reactor Containment Building radioactivity that would be an indication of a Reactor Coolant System pressure boundary leak, Maintenance personnel will be informed to l secure the work, exit the plenums, and install the access panels as expeditiously as possible. Once confirmed that plenum integrity is restored, the Operator will manually start the required FHB Main and Exhaust Booster Fans or place them in l automatic as required. I i 2. During the repair of FHB Exhaust Booster Fan 1IB and the duration of the discretion, no !
l irradiated fuel movement will occur and no loads will be moved over the Spent Fuel Pool. l
- 3. For the duration of the discretion, no activities will be conducted that could affect the level of the Spent Fuel Pool.
The above methodology is deemed acceptable since in Modes 1 - 4 the purpose of the Fuel Handling Building Exhaust Air System is to filter ECCS radioactive leakage that occurs during the recirculation phase. Recirculation phase will not occur prior to 16 minutes after an accident. Following an accident, the reactor will be automatically tripped. The plant announcement of this fact or radio communications will provide sufficient notification to inform the personnel to restore the plenum ir.tegrity. The 16 minutes prior to radioactive ECCS leakage occurring is adequate time to secure work, ensure that the plenum integrity is restored and the FHB Main and Exhaust Booster Fans staned, and for the workers to exit the FHB.
- 7) The lustification for it e duration of the enforcement discretion.
The duration for the requested enforcement discretion from the requirements of Specification 3.0.3 is 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> for the installation of the temporary modification and 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for the removal of the temporary modification. These durations are reasonable and allow the maintenance personnel adequate time to perfomi their work safely with some margin.
- 8) A statement that the reauest has been approved by the Plant Operations Review Committee The South Texas Project Plant Operations Review Committee has reviewed the proposed Enforcement Discretion request and concurs with the content of this request.
Attachment
, ST-NOC-AE-000154 Page 9 of 10
- 9) Discussion of How the Applicable Notice of Enforcement Discretion Criterion for the Appropriate Plant Condition Specified in Section H is Satisfied The applicable Notice of Enforcement Discretion criteria for the subject request is to avoid undesirable transients as a result of forcing compliance with the license condition and, thus , ,
minimize potential safety consequences and operational risks or eliminate testing, I inspection, or system malignment that is inappropriate for the particular plant condition.
1 Since no fuel will be moved during the exhaust booster fan replacement evolution, the fuel handling accident is not credible and the only event for which the FHBEAS provides protection is the large break loss of coolant accident. The large break is an extremely low probability event and the durations for which the mitigation system will be unavailable are relatively small. In addition, the compensatory actions mitigate the technical inoperability of the FHB HVAC exhaust components and provide reasonable assurance that they can perform their design function in the unlikely event of an accident. Consequently,it is not appropriate to put the plant through a shutdown transient because a large break in the relatively short unavailability durations under consideration is not a credible event and the mitigation features are expected to function as required.
Follow up License Amendment Reauired
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10)
No License Amendment will be required.
- 11) Statement that prior adoDtion of HDDroVed line. item imorovements to the Technical Specification or the Improved Technical Specification would not have Obviated the Need For the Notice of Enforcement Discretion Heauest The proposed Improved Technical Specifications for the South Texas Project have shutdown requirements similar to the current Technical Specifications for situations where all three exhaust booster fans are inoperable. Unlike current Technical Specifications, proposed ITS 3.7.12 Condition B allows for more than one exhaust train being inoperable such that entry into Spccification 3.0.3 would not be required. ITS Required Action B provides 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> to be in Mode 3 and may have provided sufficient time for installation of the temporay modification before a shutdown was required. However, whatever relief that may have been provided by ITS 3.7.12 is obviated by proposed ITS 3.3.8 for FHB HVAC Actuation Instrumentation. Required Action Bl.1 of that proposed specification would require that one train of exhaust filtration and two ventilaticn trains be placed in operation.
STPNOC is not aware of any line item improvements that would have provided relief from the condition.
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, , ST-NOC-AE-000154 Page 10 of 10 i J
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- 12) Any other information the NRC staff deems necessary before making a decision to exercise enforcement discretion. l 1
Considering the assessment performed in Items 3,4, and 9, STPNOC believes the proposed i enforcement discretion is overall beneficial to safety.
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