Submits Info in Support of Reaffirmation of Director'S Decision DD-88-03,denying Gap 2.206 Petition Re Adequacy of Util QA Program & Mgt Character & CompetenceML20155E767 |
Person / Time |
---|
Site: |
South Texas |
---|
Issue date: |
06/13/1988 |
---|
From: |
Newman J CENTRAL POWER & LIGHT CO., HOUSTON LIGHTING & POWER CO., NEWMAN & HOLTZINGER, SAN ANTONIO, TX |
---|
To: |
Murley T Office of Nuclear Reactor Regulation |
---|
References |
---|
CON-#288-6566, CON-#388-6566 2.206, DD-88-03, DD-88-3, OL, NUDOCS 8806160202 |
Download: ML20155E767 (12) |
|
|
---|
Category:CORRESPONDENCE-LETTERS
MONTHYEARNOC-AE-000675, Forwards Clarification on Items Included in 990531 Response to RAI Re Proposed License Amend Associated with Operator Action for Sbloca,As Requested1999-10-21021 October 1999 Forwards Clarification on Items Included in 990531 Response to RAI Re Proposed License Amend Associated with Operator Action for Sbloca,As Requested NOC-AE-000680, Forwards Rev 5 to 0PGP03-ZV-0001, Severe Weather Plan1999-10-20020 October 1999 Forwards Rev 5 to 0PGP03-ZV-0001, Severe Weather Plan NOC-AE-000683, Forwards 30-day Rept Concerning Significant Changes to Accepted Large Break Loss of Coolant Accident ECCS Evaluation Model for South Tx Project,Units 1 & 2,IAW 10CFR50.46(a)(3)(ii)1999-10-19019 October 1999 Forwards 30-day Rept Concerning Significant Changes to Accepted Large Break Loss of Coolant Accident ECCS Evaluation Model for South Tx Project,Units 1 & 2,IAW 10CFR50.46(a)(3)(ii) ML20217K9341999-10-15015 October 1999 Forwards SER Accepting Util 990609 Relief Request RR-ENG-2-4 for Relief from ASME Code,Section XI, Nondestructive Exam Requirements Applicable to Stp,Units 1 & 2,reactor Vessel Closure Head Nuts ML20217K9091999-10-15015 October 1999 Forwards SER Accepting Util 990609 Relief Request RR-ENG-2-3 from ASME Code,Section Xi,Nondestructive Exam Requirements Applicable to South Texas Project,Units 1 & 2, Pressurizer Support Attachment Welds 05000498/LER-1999-008, Forwards LER 99-008-00 Re Turbine Trip That Occurred While Performing Main Turbine Emergency Trip Test.Commitments Made by Licensee Are Listed in Corrective Actions Section of LER1999-10-12012 October 1999 Forwards LER 99-008-00 Re Turbine Trip That Occurred While Performing Main Turbine Emergency Trip Test.Commitments Made by Licensee Are Listed in Corrective Actions Section of LER NOC-AE-000674, Forwards Requested Estimates of Needs for Operator Licensing Exams,Per AL-99-03, Operator Licensing National Exam Schedule1999-10-12012 October 1999 Forwards Requested Estimates of Needs for Operator Licensing Exams,Per AL-99-03, Operator Licensing National Exam Schedule NOC-AE-000625, Requests Partial Relief from ASME Section XI Visual Exam Requirements of IWA-5242(a).Relief Request Is Based on Provisions of Draft ASME Section XI Code Case N-616,which Is Expected to Be Published in Near Future1999-10-0707 October 1999 Requests Partial Relief from ASME Section XI Visual Exam Requirements of IWA-5242(a).Relief Request Is Based on Provisions of Draft ASME Section XI Code Case N-616,which Is Expected to Be Published in Near Future NOC-AE-000610, Requests Relief from ASME Section XI Code Nondestructive Exam Requirements of IWA-5250(a)(2) for Second Inservice Insp Interval,Per Provisions of 10CFR50.55a(3)(i)1999-10-0707 October 1999 Requests Relief from ASME Section XI Code Nondestructive Exam Requirements of IWA-5250(a)(2) for Second Inservice Insp Interval,Per Provisions of 10CFR50.55a(3)(i) NOC-AE-000653, Requests Relief from ASME Section XI Code Requirements of Table IWE-2500-1 for VT-3 Visual Exam of Seals & Gaskets on Airlocks,Hatches & Other Devices Required to Assure Containment leak-tight Integrity,Per 10CFR50.55a(a)(3)(i)1999-10-0707 October 1999 Requests Relief from ASME Section XI Code Requirements of Table IWE-2500-1 for VT-3 Visual Exam of Seals & Gaskets on Airlocks,Hatches & Other Devices Required to Assure Containment leak-tight Integrity,Per 10CFR50.55a(a)(3)(i) ML20217C3221999-10-0707 October 1999 Forwards Insp Repts 50-498/99-16 & 50-499/99-16 on 990808-0918.No Violations Noted.Insp Generally Characterized by safety-conscious Operations,Sound Engineering & Maint Practices & Careful Radiological Work Controls 05000499/LER-1999-006, Forwards LER 99-006-00,re Entry Into TS 3.0.3.Licensee Commitments Listed in Corrective Actions Section of Attachment1999-09-30030 September 1999 Forwards LER 99-006-00,re Entry Into TS 3.0.3.Licensee Commitments Listed in Corrective Actions Section of Attachment ML20212L1651999-09-30030 September 1999 Responds to STP Nuclear Operating Co 981012 & s Which Provided Update to TS Bases Pages B 3/4 8-14 Through B 3/4 8-17.NRC Staff Found Change Consistent with TS 3/4.8.2 DC Sources. Staff Found & Deleted Typographical Error NOC-AE-000664, Forwards Rev 1 to STP Electric Generating Station Unit 1 Cycle 9 COLR & Rev 1 to STP Electric Generating Station Unit 2 Cycle 7 Colr1999-09-30030 September 1999 Forwards Rev 1 to STP Electric Generating Station Unit 1 Cycle 9 COLR & Rev 1 to STP Electric Generating Station Unit 2 Cycle 7 Colr ML20212J7141999-09-29029 September 1999 Forwards Insp Repts 50-498/99-15 & 50-499/99-15 on 990920-24 at South Texas Project Electric Generating Station.No Violations Noted.Insp Covered Requalification Training Program & Observation of Requalification Activities NOC-AE-000646, Informs NRC That STP Nuclear Operating Co Is Y2K Ready IAW Nei/Nusmg 97-07 Guidelines & Also Provides Response to NRC Ltr1999-09-28028 September 1999 Informs NRC That STP Nuclear Operating Co Is Y2K Ready IAW Nei/Nusmg 97-07 Guidelines & Also Provides Response to NRC Ltr ML20212J0651999-09-27027 September 1999 Discusses Licensee 980330 Response to GL 97-06, Degradation of SG Internals. Concludes That Response to GL Provides Reasonable Assurance That Condition of SG Internals in Compliance with Current Licensing Bases for Facility ML20212F1791999-09-24024 September 1999 Discusses 990923 Meeting Conducted in Region IV Ofc Re Status of Activities to Support Confirmatory Order, ,modifying OL & to Introduce New Director,Safety Quality Concerns Program.List of Attendees Encl ML20212E9091999-09-23023 September 1999 Discusses GL 98-01, Year 2000 Readiness of Computer Sys at Npps, Supplement 1 & STP Nuclear Operating Co Response for STP Dtd 990629.Understands That at Least One Sys or Component Listed May Have Potential to Cause Transient ML20212F2111999-09-22022 September 1999 Forwards Review of SG 90-day Rept, South Texas Unit-2 Cycle 7 Voltage-Based Repair Criteria Rept, Submitted by Util on 990119 NOC-AE-000633, Forwards Rev 3 to SG-99-04-005, STP 1RE08 Outage Condition Monitoring Rept & Final Operational Assessment. Rept Satisfies Reporting Requirements of NEI 97-06,dtd Dec 19971999-09-21021 September 1999 Forwards Rev 3 to SG-99-04-005, STP 1RE08 Outage Condition Monitoring Rept & Final Operational Assessment. Rept Satisfies Reporting Requirements of NEI 97-06,dtd Dec 1997 NOC-AE-000634, Forwards Addl Info Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Povs. MOV design-basis Review Checklist,Encl1999-09-21021 September 1999 Forwards Addl Info Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Povs. MOV design-basis Review Checklist,Encl NOC-AE-000649, Forwards Current Annual Financial Data for STP Electric Generating Station Per 10CFR50.71(b),acting on Behalf of Central Power & Light Co,City of Austin,Tx,City Public Svc Board of San Antonio & Hl&P1999-09-21021 September 1999 Forwards Current Annual Financial Data for STP Electric Generating Station Per 10CFR50.71(b),acting on Behalf of Central Power & Light Co,City of Austin,Tx,City Public Svc Board of San Antonio & Hl&P 05000499/LER-1999-005, Forwards LER 99-005-00,re Esfa Following Loss of Power to Standby Transformer 2 Due to Electrical Fault.Licensee Commitments Are Listed in Corrective Actions Section of LER1999-09-20020 September 1999 Forwards LER 99-005-00,re Esfa Following Loss of Power to Standby Transformer 2 Due to Electrical Fault.Licensee Commitments Are Listed in Corrective Actions Section of LER ML20212D9171999-09-16016 September 1999 Informs That on 990818,NRC Completed Midcycle PPR of South Texas Project & Identified No Areas in Which Performance Warranted Insp Beyond Core Insp Program.Details of Insp Plan Through Mar 2000 & Historical Listing of Plant Issues,Encl ML20216F5471999-09-15015 September 1999 Discusses 990914 Meeting Conducted at Region Iv.Meeting Was Requested by Staff to Introduce New Management Organization to Region IV & to Discuss General Plant Performance & Mgt Challenges IR 05000498/19990121999-09-14014 September 1999 Forwards Insp Repts 50-498/99-12 & 50-499/99-12 on 990816-19.Three Violations Occurred & Being Treated as Ncvs. Areas Examined During Insp Included Portions of Access Authorization & Physical Security Programs 05000498/LER-1999-007, Forwards LER 99-007-00 Re Train 'B' CR Makeup & Cleanup Filtration Sys Being Inoperable for Greater than Aot.Util Intends to Append Addl Info Section of LER with Brief Description of Test Results,Rather than Submit Separate LER1999-09-13013 September 1999 Forwards LER 99-007-00 Re Train 'B' CR Makeup & Cleanup Filtration Sys Being Inoperable for Greater than Aot.Util Intends to Append Addl Info Section of LER with Brief Description of Test Results,Rather than Submit Separate LER ML20211P8201999-09-0909 September 1999 Forwards SE Authorizing 990224 Submittal of First 10-year Interval ISI Program Plan - Relief Request RR-ENG-24,from ASME Section XI Code,Table IWC-2500-1 NOC-AE-000638, Forwards License Renewal Applications & Certifications of Medical Exam for Seven Listed Licensed Operators at Stp,Per 10CFR55.57.Encl Withheld,Per 10CFR2.790(a)(6)1999-09-0909 September 1999 Forwards License Renewal Applications & Certifications of Medical Exam for Seven Listed Licensed Operators at Stp,Per 10CFR55.57.Encl Withheld,Per 10CFR2.790(a)(6) ML20211P7671999-09-0909 September 1999 Forwards SER Authorizing Licensee 990517 Alternative Proposed in Relief Request RR-ENG-2-8 to Code Case N-491-2 for Second 10-year Insp Interval of South Texas Project, Units 1 & 2,pursuant to 10CFR50.55a(a)(3)(i) ML20211P7871999-09-0909 September 1999 Forwards Safety Evaluation Re First 10-yr Interval Inservice Insp Program Plan Request for Relief RR-ENG-31 IR 05000498/19990141999-09-0303 September 1999 Forwards Insp Repts 50-498/99-14 & 50-499/99-14 on 990627-0807.Apparent Violations Identified & Being Treated as Noncited Violations Consistent with App C of Enforcement Policy NOC-AE-000562, Requests Relief from Contruction Code non-destructive Exam Requirements for Repair/Replacement Activities During Second Inservice Insp Interval of Units 1 & 2,IAW Provisions of 10CFR50.55a(a)(3)(i)1999-08-31031 August 1999 Requests Relief from Contruction Code non-destructive Exam Requirements for Repair/Replacement Activities During Second Inservice Insp Interval of Units 1 & 2,IAW Provisions of 10CFR50.55a(a)(3)(i) ML20212A4351999-08-27027 August 1999 Discusses Investigation Rept OI-4-1999-009 Re Activites at South Texas Project.Oi Investigation Initiated in Response to Alleged Employment Discrimination Complaint. Allegation Not Substantiated.No Further Action Planned NOC-AE-000617, Forwards semi-annual Fitness for Duty Program Performance Rept for 990101-990630,IAW 10CFR26.71(d)1999-08-26026 August 1999 Forwards semi-annual Fitness for Duty Program Performance Rept for 990101-990630,IAW 10CFR26.71(d) ML20211J2511999-08-26026 August 1999 Discusses Proposed TS Change on Replacement SG Water Level Trip Setpoint for Plant,Units 1 & 2 NOC-AE-000585, Provides Notification That South Texas Project Has Completed Integrity Evaluation of Units 1 & 2 Reactor Coolant Pump Casings Required by Paragraph (D) of Code Case N-4811999-08-25025 August 1999 Provides Notification That South Texas Project Has Completed Integrity Evaluation of Units 1 & 2 Reactor Coolant Pump Casings Required by Paragraph (D) of Code Case N-481 ML20211F4421999-08-24024 August 1999 Forwards SE Authorizing Licensee 990513 Request for Relief RR-ENG-2-13,seeking Relief from ASME B&PV Code Section Xi,Exam Vessel shell-to-flange Welds for Second ISI Intervals ML20211F5031999-08-23023 August 1999 Forwards SE Authorizing Licensee 990315 Request for Relief RR-ENG-30,seeking Relief from ASME B&PV Code,Section Xi,Nde Requirements Applicable to Stp,Unit 2 SG Welds ML20212A4391999-08-17017 August 1999 Discusses Investigation Rept OI-4-1999-023 Re Activities at South Texas Project.Oi Investigation Initiated in Response to Alleged Employment Discrimination for Initiating Condition Report to Document Unauthorized Work Practices ML20210U1271999-08-16016 August 1999 Forwards Insp Repts 50-498/99-08 & 50-499/99-08 on 990517-21 & 0607-10.No Violations Noted.Corrective Action Program Was Reviewed ML20211A9501999-08-12012 August 1999 Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl ML20211B7881999-08-10010 August 1999 Transmits Summary of Two Meetings with Risk-Informed TS Task Force in Rockville,Md on 990514 & 0714 ML20210L1461999-08-0303 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams NOC-AE-000603, Informs of Addition of Restriction to SRO License 42658, for KM Espinoza,Effective 990721,per 10CFR50.74.Encl Info Withheld,Per 10CFR2.790(a)(6)1999-07-29029 July 1999 Informs of Addition of Restriction to SRO License 42658, for KM Espinoza,Effective 990721,per 10CFR50.74.Encl Info Withheld,Per 10CFR2.790(a)(6) NOC-AE-000470, Forwards Amend 12 to STP Fire Hazards Analysis Rept. Summary of Changes Made Under Provision of 10CFR50.59 Also Encl1999-07-28028 July 1999 Forwards Amend 12 to STP Fire Hazards Analysis Rept. Summary of Changes Made Under Provision of 10CFR50.59 Also Encl NOC-AE-000599, Forwards STP Unit 1,Cycle 9 Startup Testing Summary Rept. No New Licensing Commitments Contained in Ltr1999-07-28028 July 1999 Forwards STP Unit 1,Cycle 9 Startup Testing Summary Rept. No New Licensing Commitments Contained in Ltr NOC-AE-000589, Forwards Rev to 1RE08 ISI Summary Repts for Repairs & Replacements & for Sys Pressure Tests,Corecting Date of End of Insp Interval Provided in Item 9 of from NIS-1 from 09/24/99 to 09/24/20001999-07-26026 July 1999 Forwards Rev to 1RE08 ISI Summary Repts for Repairs & Replacements & for Sys Pressure Tests,Corecting Date of End of Insp Interval Provided in Item 9 of from NIS-1 from 09/24/99 to 09/24/2000 ML20210F3851999-07-26026 July 1999 Forwards Exam Repts 50-498/99-301 & 50-499/99-301 on 990706- 15.Exam Included Evaluation of 9 Applicants for SO Licenses & 8 Applicants for RO Licenses 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARNOC-AE-000675, Forwards Clarification on Items Included in 990531 Response to RAI Re Proposed License Amend Associated with Operator Action for Sbloca,As Requested1999-10-21021 October 1999 Forwards Clarification on Items Included in 990531 Response to RAI Re Proposed License Amend Associated with Operator Action for Sbloca,As Requested NOC-AE-000680, Forwards Rev 5 to 0PGP03-ZV-0001, Severe Weather Plan1999-10-20020 October 1999 Forwards Rev 5 to 0PGP03-ZV-0001, Severe Weather Plan NOC-AE-000683, Forwards 30-day Rept Concerning Significant Changes to Accepted Large Break Loss of Coolant Accident ECCS Evaluation Model for South Tx Project,Units 1 & 2,IAW 10CFR50.46(a)(3)(ii)1999-10-19019 October 1999 Forwards 30-day Rept Concerning Significant Changes to Accepted Large Break Loss of Coolant Accident ECCS Evaluation Model for South Tx Project,Units 1 & 2,IAW 10CFR50.46(a)(3)(ii) NOC-AE-000674, Forwards Requested Estimates of Needs for Operator Licensing Exams,Per AL-99-03, Operator Licensing National Exam Schedule1999-10-12012 October 1999 Forwards Requested Estimates of Needs for Operator Licensing Exams,Per AL-99-03, Operator Licensing National Exam Schedule 05000498/LER-1999-008, Forwards LER 99-008-00 Re Turbine Trip That Occurred While Performing Main Turbine Emergency Trip Test.Commitments Made by Licensee Are Listed in Corrective Actions Section of LER1999-10-12012 October 1999 Forwards LER 99-008-00 Re Turbine Trip That Occurred While Performing Main Turbine Emergency Trip Test.Commitments Made by Licensee Are Listed in Corrective Actions Section of LER NOC-AE-000625, Requests Partial Relief from ASME Section XI Visual Exam Requirements of IWA-5242(a).Relief Request Is Based on Provisions of Draft ASME Section XI Code Case N-616,which Is Expected to Be Published in Near Future1999-10-0707 October 1999 Requests Partial Relief from ASME Section XI Visual Exam Requirements of IWA-5242(a).Relief Request Is Based on Provisions of Draft ASME Section XI Code Case N-616,which Is Expected to Be Published in Near Future NOC-AE-000610, Requests Relief from ASME Section XI Code Nondestructive Exam Requirements of IWA-5250(a)(2) for Second Inservice Insp Interval,Per Provisions of 10CFR50.55a(3)(i)1999-10-0707 October 1999 Requests Relief from ASME Section XI Code Nondestructive Exam Requirements of IWA-5250(a)(2) for Second Inservice Insp Interval,Per Provisions of 10CFR50.55a(3)(i) NOC-AE-000653, Requests Relief from ASME Section XI Code Requirements of Table IWE-2500-1 for VT-3 Visual Exam of Seals & Gaskets on Airlocks,Hatches & Other Devices Required to Assure Containment leak-tight Integrity,Per 10CFR50.55a(a)(3)(i)1999-10-0707 October 1999 Requests Relief from ASME Section XI Code Requirements of Table IWE-2500-1 for VT-3 Visual Exam of Seals & Gaskets on Airlocks,Hatches & Other Devices Required to Assure Containment leak-tight Integrity,Per 10CFR50.55a(a)(3)(i) 05000499/LER-1999-006, Forwards LER 99-006-00,re Entry Into TS 3.0.3.Licensee Commitments Listed in Corrective Actions Section of Attachment1999-09-30030 September 1999 Forwards LER 99-006-00,re Entry Into TS 3.0.3.Licensee Commitments Listed in Corrective Actions Section of Attachment NOC-AE-000664, Forwards Rev 1 to STP Electric Generating Station Unit 1 Cycle 9 COLR & Rev 1 to STP Electric Generating Station Unit 2 Cycle 7 Colr1999-09-30030 September 1999 Forwards Rev 1 to STP Electric Generating Station Unit 1 Cycle 9 COLR & Rev 1 to STP Electric Generating Station Unit 2 Cycle 7 Colr NOC-AE-000646, Informs NRC That STP Nuclear Operating Co Is Y2K Ready IAW Nei/Nusmg 97-07 Guidelines & Also Provides Response to NRC Ltr1999-09-28028 September 1999 Informs NRC That STP Nuclear Operating Co Is Y2K Ready IAW Nei/Nusmg 97-07 Guidelines & Also Provides Response to NRC Ltr NOC-AE-000633, Forwards Rev 3 to SG-99-04-005, STP 1RE08 Outage Condition Monitoring Rept & Final Operational Assessment. Rept Satisfies Reporting Requirements of NEI 97-06,dtd Dec 19971999-09-21021 September 1999 Forwards Rev 3 to SG-99-04-005, STP 1RE08 Outage Condition Monitoring Rept & Final Operational Assessment. Rept Satisfies Reporting Requirements of NEI 97-06,dtd Dec 1997 NOC-AE-000634, Forwards Addl Info Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Povs. MOV design-basis Review Checklist,Encl1999-09-21021 September 1999 Forwards Addl Info Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Povs. MOV design-basis Review Checklist,Encl NOC-AE-000649, Forwards Current Annual Financial Data for STP Electric Generating Station Per 10CFR50.71(b),acting on Behalf of Central Power & Light Co,City of Austin,Tx,City Public Svc Board of San Antonio & Hl&P1999-09-21021 September 1999 Forwards Current Annual Financial Data for STP Electric Generating Station Per 10CFR50.71(b),acting on Behalf of Central Power & Light Co,City of Austin,Tx,City Public Svc Board of San Antonio & Hl&P 05000499/LER-1999-005, Forwards LER 99-005-00,re Esfa Following Loss of Power to Standby Transformer 2 Due to Electrical Fault.Licensee Commitments Are Listed in Corrective Actions Section of LER1999-09-20020 September 1999 Forwards LER 99-005-00,re Esfa Following Loss of Power to Standby Transformer 2 Due to Electrical Fault.Licensee Commitments Are Listed in Corrective Actions Section of LER 05000498/LER-1999-007, Forwards LER 99-007-00 Re Train 'B' CR Makeup & Cleanup Filtration Sys Being Inoperable for Greater than Aot.Util Intends to Append Addl Info Section of LER with Brief Description of Test Results,Rather than Submit Separate LER1999-09-13013 September 1999 Forwards LER 99-007-00 Re Train 'B' CR Makeup & Cleanup Filtration Sys Being Inoperable for Greater than Aot.Util Intends to Append Addl Info Section of LER with Brief Description of Test Results,Rather than Submit Separate LER NOC-AE-000638, Forwards License Renewal Applications & Certifications of Medical Exam for Seven Listed Licensed Operators at Stp,Per 10CFR55.57.Encl Withheld,Per 10CFR2.790(a)(6)1999-09-0909 September 1999 Forwards License Renewal Applications & Certifications of Medical Exam for Seven Listed Licensed Operators at Stp,Per 10CFR55.57.Encl Withheld,Per 10CFR2.790(a)(6) NOC-AE-000562, Requests Relief from Contruction Code non-destructive Exam Requirements for Repair/Replacement Activities During Second Inservice Insp Interval of Units 1 & 2,IAW Provisions of 10CFR50.55a(a)(3)(i)1999-08-31031 August 1999 Requests Relief from Contruction Code non-destructive Exam Requirements for Repair/Replacement Activities During Second Inservice Insp Interval of Units 1 & 2,IAW Provisions of 10CFR50.55a(a)(3)(i) NOC-AE-000617, Forwards semi-annual Fitness for Duty Program Performance Rept for 990101-990630,IAW 10CFR26.71(d)1999-08-26026 August 1999 Forwards semi-annual Fitness for Duty Program Performance Rept for 990101-990630,IAW 10CFR26.71(d) NOC-AE-000585, Provides Notification That South Texas Project Has Completed Integrity Evaluation of Units 1 & 2 Reactor Coolant Pump Casings Required by Paragraph (D) of Code Case N-4811999-08-25025 August 1999 Provides Notification That South Texas Project Has Completed Integrity Evaluation of Units 1 & 2 Reactor Coolant Pump Casings Required by Paragraph (D) of Code Case N-481 NOC-AE-000603, Informs of Addition of Restriction to SRO License 42658, for KM Espinoza,Effective 990721,per 10CFR50.74.Encl Info Withheld,Per 10CFR2.790(a)(6)1999-07-29029 July 1999 Informs of Addition of Restriction to SRO License 42658, for KM Espinoza,Effective 990721,per 10CFR50.74.Encl Info Withheld,Per 10CFR2.790(a)(6) NOC-AE-000599, Forwards STP Unit 1,Cycle 9 Startup Testing Summary Rept. No New Licensing Commitments Contained in Ltr1999-07-28028 July 1999 Forwards STP Unit 1,Cycle 9 Startup Testing Summary Rept. No New Licensing Commitments Contained in Ltr NOC-AE-000470, Forwards Amend 12 to STP Fire Hazards Analysis Rept. Summary of Changes Made Under Provision of 10CFR50.59 Also Encl1999-07-28028 July 1999 Forwards Amend 12 to STP Fire Hazards Analysis Rept. Summary of Changes Made Under Provision of 10CFR50.59 Also Encl 05000498/LER-1999-006, Forwards LER 99-006-00 Re Automatic Reactor Trip Due to over-temp delta-temp Actuation.Licensee Commitments Are Listed in Corrective Actions Section of LER1999-07-26026 July 1999 Forwards LER 99-006-00 Re Automatic Reactor Trip Due to over-temp delta-temp Actuation.Licensee Commitments Are Listed in Corrective Actions Section of LER NOC-AE-000589, Forwards Rev to 1RE08 ISI Summary Repts for Repairs & Replacements & for Sys Pressure Tests,Corecting Date of End of Insp Interval Provided in Item 9 of from NIS-1 from 09/24/99 to 09/24/20001999-07-26026 July 1999 Forwards Rev to 1RE08 ISI Summary Repts for Repairs & Replacements & for Sys Pressure Tests,Corecting Date of End of Insp Interval Provided in Item 9 of from NIS-1 from 09/24/99 to 09/24/2000 NOC-AE-000582, Forwards 1RE08 ISI Summary Rept for Welds & Component Supports of STP Electric Generating Station,Unit 1. Summary Rept Satisfies Reporting Requirements of IWA-6000 of Section XI for Welds & Component Supports1999-07-26026 July 1999 Forwards 1RE08 ISI Summary Rept for Welds & Component Supports of STP Electric Generating Station,Unit 1. Summary Rept Satisfies Reporting Requirements of IWA-6000 of Section XI for Welds & Component Supports NOC-AE-000597, Forwards voltage-based Criteria 90-day Rept for SG Tube Exam Performed Under NRC GL 95-05 During Refueling Outage 1RE08. Rept Contains Info Required by Section 6.b of Attachment 2 to GL 95-051999-07-23023 July 1999 Forwards voltage-based Criteria 90-day Rept for SG Tube Exam Performed Under NRC GL 95-05 During Refueling Outage 1RE08. Rept Contains Info Required by Section 6.b of Attachment 2 to GL 95-05 NOC-AE-000598, Forwards Four Copies of 1RE08 Refueling Outage ISI Summary Rept for Steam Generator Tubing1999-07-23023 July 1999 Forwards Four Copies of 1RE08 Refueling Outage ISI Summary Rept for Steam Generator Tubing NOC-AE-00586, Forwards Results of Control Rod Testing,In Response to NRC Bulletin 96-01, Control Rod Insertion Problems, Dtd 960308.Core Map Provided to Assist in Understanding Test Data1999-07-21021 July 1999 Forwards Results of Control Rod Testing,In Response to NRC Bulletin 96-01, Control Rod Insertion Problems, Dtd 960308.Core Map Provided to Assist in Understanding Test Data NOC-AE-000595, Forwards Chapters 1.0 & 16.0 to Operations QA Plan for South Texas Project.Rev Is Strictly Administrative & All Content Was Previously Submitted to NRC on 990503 & 9906151999-07-21021 July 1999 Forwards Chapters 1.0 & 16.0 to Operations QA Plan for South Texas Project.Rev Is Strictly Administrative & All Content Was Previously Submitted to NRC on 990503 & 990615 NOC-AE-000518, Requests Exemption from Various Special Treatment Requirements of 10CFR50,as Described in Encls to Ltr.Stp Believes That Pilot Application Will Assist NRC in Development & Implementation of risk-informed 10CFR501999-07-13013 July 1999 Requests Exemption from Various Special Treatment Requirements of 10CFR50,as Described in Encls to Ltr.Stp Believes That Pilot Application Will Assist NRC in Development & Implementation of risk-informed 10CFR50 NOC-AE-000536, Submits Request for Exemption from Requirements of 10CFR50.34(b)(11),10CFR50,App A,Gdc 2 & 10CFR100,App a, Section VI(a)(3) Re Maint of Seismic Instrumentation.Revised Page to Procedure OERP01-ZV-IN01 Included1999-07-13013 July 1999 Submits Request for Exemption from Requirements of 10CFR50.34(b)(11),10CFR50,App A,Gdc 2 & 10CFR100,App a, Section VI(a)(3) Re Maint of Seismic Instrumentation.Revised Page to Procedure OERP01-ZV-IN01 Included NOC-AE-000580, Forwards Response to NRC 990415 RAI Re Implementation of Commitments Related to GL 89-10, Safety-Related MOV Testing & Surveillance & GL 96-05, Periodic Verification of Design Basis Capability of Safety-Related Movs1999-07-13013 July 1999 Forwards Response to NRC 990415 RAI Re Implementation of Commitments Related to GL 89-10, Safety-Related MOV Testing & Surveillance & GL 96-05, Periodic Verification of Design Basis Capability of Safety-Related Movs NOC-AE-000574, Forwards ISI Summary Repts for Repairs & Replacements & for Sys Pressure Tests Performed Between 971004 & Completion of Eighth RO on 9904281999-07-0606 July 1999 Forwards ISI Summary Repts for Repairs & Replacements & for Sys Pressure Tests Performed Between 971004 & Completion of Eighth RO on 990428 NOC-AE-000557, Requests Relief from ASME Section XI Code Nondestructive Exam Requirements of App III,III-3410 for Second ISI Interval.Proposed Alternatives for Ultrasonic Exam of Piping Sys Welds,Attached1999-07-0606 July 1999 Requests Relief from ASME Section XI Code Nondestructive Exam Requirements of App III,III-3410 for Second ISI Interval.Proposed Alternatives for Ultrasonic Exam of Piping Sys Welds,Attached NOC-AE-000498, Requests Relief from ASME Section XI Code Nondestructive Exam Requirements Applicable to SG Main Steam Nozzle inside- Radius Sections.Attachment Includes Discussion of Basis & Justification for Request & Implementation Schedule1999-07-0606 July 1999 Requests Relief from ASME Section XI Code Nondestructive Exam Requirements Applicable to SG Main Steam Nozzle inside- Radius Sections.Attachment Includes Discussion of Basis & Justification for Request & Implementation Schedule NOC-AE-000573, Requests Relief from Requirements of ASME Section XI Code Case N-498,exempting Isolated Class 1 Reactor Vessel Head Vent Atmospheric Vent Piping & Valve from Being Tested at Full RCS Pressure1999-07-0606 July 1999 Requests Relief from Requirements of ASME Section XI Code Case N-498,exempting Isolated Class 1 Reactor Vessel Head Vent Atmospheric Vent Piping & Valve from Being Tested at Full RCS Pressure NOC-AE-000541, Submits Response to GL 98-01,Suppl 1, Y2K Readiness of Computer Systems at Npps. Readiness Disclosure for STP, Encl1999-06-29029 June 1999 Submits Response to GL 98-01,Suppl 1, Y2K Readiness of Computer Systems at Npps. Readiness Disclosure for STP, Encl NOC-AE-000571, Forwards Final Operating Exam Matls for STP Exam Scheduled for 990705.Revised Operating Exam Outline & post-validation Change Summary Has Been Included.Without Encls1999-06-24024 June 1999 Forwards Final Operating Exam Matls for STP Exam Scheduled for 990705.Revised Operating Exam Outline & post-validation Change Summary Has Been Included.Without Encls NOC-AE-000512, Responds to NRC 981201 Telcon Re Jco 93-0004,per Revised MSLB Analysis1999-06-23023 June 1999 Responds to NRC 981201 Telcon Re Jco 93-0004,per Revised MSLB Analysis NOC-AE-000560, Forwards LER 99-S02-00,re Failure to Maintain Positive Control of Vital Area Security Key.Licensee Commitments Are Found in Corrective Action Section of LER1999-06-23023 June 1999 Forwards LER 99-S02-00,re Failure to Maintain Positive Control of Vital Area Security Key.Licensee Commitments Are Found in Corrective Action Section of LER 05000498/LER-1999-005, Forwards LER 99-005-00,re Failure to Meet Requirements of TS Surveillance 3.7.1.2 Action B for Auxiliary FW Sys.Only Commitments Contained in Ltr Are Located in Corrective Action Section of LER1999-06-17017 June 1999 Forwards LER 99-005-00,re Failure to Meet Requirements of TS Surveillance 3.7.1.2 Action B for Auxiliary FW Sys.Only Commitments Contained in Ltr Are Located in Corrective Action Section of LER NOC-AE-000565, Forwards Amended Pages for Insertion Into South Texas Project Nuclear Operating Co Previously Submitted Response to NRC Rai.New Pages Include Expanded Answer to Question 4.b1999-06-16016 June 1999 Forwards Amended Pages for Insertion Into South Texas Project Nuclear Operating Co Previously Submitted Response to NRC Rai.New Pages Include Expanded Answer to Question 4.b NOC-AE-000548, Forwards Response to RAI Re Proposed Amends on Replacement SG Water Level Trip Setpoint Differences for Stp,Units 1 & 2.Nothing Contained in Response Should Be Considered Commitment Unless So Specified in Separate Correspondence1999-06-16016 June 1999 Forwards Response to RAI Re Proposed Amends on Replacement SG Water Level Trip Setpoint Differences for Stp,Units 1 & 2.Nothing Contained in Response Should Be Considered Commitment Unless So Specified in Separate Correspondence NOC-AE-000561, Forwards Change QA-042 to Operations QAP, Rev 13, Reflecting Current Organizational Alignment for STP & Culminating Organizational Realigment That Has Been Taking Place During Past Several Months1999-06-15015 June 1999 Forwards Change QA-042 to Operations QAP, Rev 13, Reflecting Current Organizational Alignment for STP & Culminating Organizational Realigment That Has Been Taking Place During Past Several Months NOC-AE-0559, Forwards STP Commitment Change Summary Rept for Period 981209-990610.Rept Lists Each Commitment for Which Change Was Made During Reporting Period & Provides Basis for Each Change1999-06-15015 June 1999 Forwards STP Commitment Change Summary Rept for Period 981209-990610.Rept Lists Each Commitment for Which Change Was Made During Reporting Period & Provides Basis for Each Change NOC-AE-000499, Forwards Relief Request RR-ENG-2-3,proposing to Perform Alternative Ultrasonic Examination from Outside Surface of Skirt Attachment Weld as Described in Encl,In Lieu of Surface Examination from Inside Pressurizer Skirt1999-06-0909 June 1999 Forwards Relief Request RR-ENG-2-3,proposing to Perform Alternative Ultrasonic Examination from Outside Surface of Skirt Attachment Weld as Described in Encl,In Lieu of Surface Examination from Inside Pressurizer Skirt NOC-AE-000502, Forwards Relief Request RR-ENG-2-6,proposing That Boroscopic VT-1 Visual Examination Be Allowed as Alternative to Section XI Surface Examination of Pump Casing Welds,Or Portions of Welds within Pits1999-06-0909 June 1999 Forwards Relief Request RR-ENG-2-6,proposing That Boroscopic VT-1 Visual Examination Be Allowed as Alternative to Section XI Surface Examination of Pump Casing Welds,Or Portions of Welds within Pits NOC-AE-000500, Forwards Relief Request RR-ENG-2-4,proposing to Perform Alternative Ultrasonic Examination from Outside & End Surfaces of Reactor Vessel Closure Head Nuts,As Described in Encl in Lieu of Surface Examination of Threaded Region1999-06-0909 June 1999 Forwards Relief Request RR-ENG-2-4,proposing to Perform Alternative Ultrasonic Examination from Outside & End Surfaces of Reactor Vessel Closure Head Nuts,As Described in Encl in Lieu of Surface Examination of Threaded Region NOC-AE-000545, Forwards Response to NRC 990416 RAI Re Util Proposed Amend on Operator Action for Small Break Loca, .Draft EOP Re Small Break Loca,Encl to Aid Discussion of Proposed Amend1999-05-31031 May 1999 Forwards Response to NRC 990416 RAI Re Util Proposed Amend on Operator Action for Small Break Loca, .Draft EOP Re Small Break Loca,Encl to Aid Discussion of Proposed Amend 1999-09-09
[Table view] Category:UTILITY TO NRC
MONTHYEARST-HL-AE-3578, Forwards 1RE02 Inservice Insp Summary Rept for Welds & Component Supports..., Describing Exams Performed During Period of 900329-0621,per 1983 Edition of ASME Code,Section XI & Summer 1983 Addenda1990-09-20020 September 1990 Forwards 1RE02 Inservice Insp Summary Rept for Welds & Component Supports..., Describing Exams Performed During Period of 900329-0621,per 1983 Edition of ASME Code,Section XI & Summer 1983 Addenda ST-HL-AE-3577, Responds to Generic Ltr 90-07, Operator Licensing Natl Exam Schedule1990-09-18018 September 1990 Responds to Generic Ltr 90-07, Operator Licensing Natl Exam Schedule ST-HL-AE-3567, Requests NRC Review of Proposed Rev to Schedule for Inservice Insp Exam of Class 1,Category B-D Vessel Nozzles1990-09-14014 September 1990 Requests NRC Review of Proposed Rev to Schedule for Inservice Insp Exam of Class 1,Category B-D Vessel Nozzles ST-HL-AE-3570, Forwards Rev 5 to, South Texas Project Unit 1 Pump & Valve Inservice Test Plan1990-09-14014 September 1990 Forwards Rev 5 to, South Texas Project Unit 1 Pump & Valve Inservice Test Plan ST-HL-AE-3553, Forwards WCAP-12629, Analysis of Capsule U from South Texas Unit 1 Reactor Vessel Radiation Surveillance Program. Pressure-temp Curves Currently in Use in Facility Tech Specs Are More Conservative than Presented in App a of Rept1990-09-10010 September 1990 Forwards WCAP-12629, Analysis of Capsule U from South Texas Unit 1 Reactor Vessel Radiation Surveillance Program. Pressure-temp Curves Currently in Use in Facility Tech Specs Are More Conservative than Presented in App a of Rept ST-HL-AE-3565, Forwards Rev 8 to Operations QA Plan. Plan Revised in Order to Include More Detailed Criteria of Chapter 17.2 of Updated Fsar.Approval Requested1990-09-10010 September 1990 Forwards Rev 8 to Operations QA Plan. Plan Revised in Order to Include More Detailed Criteria of Chapter 17.2 of Updated Fsar.Approval Requested ST-HL-AE-3546, Forwards Corrected Semiannual Radioactive Effluent Release Rept for Second Half of 19891990-08-28028 August 1990 Forwards Corrected Semiannual Radioactive Effluent Release Rept for Second Half of 1989 ST-HL-AE-3550, Forwards Semiannual fitness-for-duty Program Performance Rept for Jan-June 1990,per 10CFR26.71(d)1990-08-28028 August 1990 Forwards Semiannual fitness-for-duty Program Performance Rept for Jan-June 1990,per 10CFR26.71(d) ST-HL-AE-3540, Provides Schedule Under Which Facility Turbine Components Inspected for Functional Integrity.Required Insp Intervals Calculated to Maintain Probability of Missile Generation for Each Low Pressure Rotor1990-08-28028 August 1990 Provides Schedule Under Which Facility Turbine Components Inspected for Functional Integrity.Required Insp Intervals Calculated to Maintain Probability of Missile Generation for Each Low Pressure Rotor ST-HL-AE-3551, Forwards Responses to NRC 900807 Request for Addl Info Re Probabilistic Safety Assessment Human Reliability Analysis. Paper on Quantification of Human Error Rates Using slim-based Approach Encl1990-08-26026 August 1990 Forwards Responses to NRC 900807 Request for Addl Info Re Probabilistic Safety Assessment Human Reliability Analysis. Paper on Quantification of Human Error Rates Using slim-based Approach Encl ML20043H6191990-06-21021 June 1990 Forwards 1989 Annual Financial Repts for Licensees for Plant ML20043H5971990-06-19019 June 1990 Forwards Responses to Open Items Resulting from Sandia Draft Rept on Probabilistic Safety Assessment.Dominant Sequence Model Encl,Per NRC Reviewers Request ML20043H7781990-06-18018 June 1990 Forwards Rev 1 to SER Commitment Status for Plant,Per NUREG-0781.List of Action Items Completed But Not Incorporated Into Sser & List of Items for Actions Not Completed Also Encl ML20043F6261990-06-11011 June 1990 Forwards Rev 0 to Unit 1 Cycle 3 Core Operating Limits Rept. ML20043F3191990-06-0404 June 1990 Responds to NRC 900504 Ltr Re Violations Noted in Insp Repts 50-498/90-01 & 50-499/90-01.Corrective Actions:Compressed Gas Cylinders Removed from Power Block & Nashua 357 Tape Returned to Nuclear Purchasing Matl Mgt Co ML20043D3241990-06-0101 June 1990 Forwards Rev 10 to Safeguards Contingency Plan.Rev Withheld (Ref 10CFR73.21) ML20043B1651990-05-21021 May 1990 Advises That Qualified Display Processing Sys on Line Parameter Update Mod Will Be Completed During Next Refueling Outages,Per 900312 Ltr ML20043A9951990-05-16016 May 1990 Discusses Actions Taken Re Prompt Notification Sys.Util Found Autodialer Sys Offer Acceptable Alternative to Replacing Majority of Tone Alert Radios ML20043H6531990-05-16016 May 1990 Forwards Plant Owner Draft Decommissioning Certificate & Util & City Public Svc Board of San Antonio Decommissioning Master Trust Agreements for South Texas Project ML20043A6081990-05-16016 May 1990 Forwards Rev 16 to Physical Security Plan.Rev Withheld (Ref 10CFR73.21) ML20043A8641990-05-14014 May 1990 Clarifies Operation of Telephone Autodialer Sys,As Part of Prompt Notification Sys.Autodialer Sys,As Currently Configured,Can Autodial & Deliver Prerecorded Message to Residents at Rate of Approx 20 Calls Per Minute ML20043A3271990-05-10010 May 1990 Forwards Endorsements 7 & 6 to Maelu Certificates M-113 & M-116,respectively & Endorsement 6 to Nelia Certificates N-113 & N-116 ML20042G8641990-05-0909 May 1990 Comments on SALP Repts 50-498/90-06 & 50-499/90-06 for Jan 1989 to Jan 1990.Util Working on Areas Identified During SALP Rept & Mgt Meeting on 900425 ML20042F9571990-05-0707 May 1990 Responds to NRC 900405 Ltr Re Violations Noted in Insp Repts 50-498/90-05 & 50-499/90-05.Corrective Actions:Surveillances of Emergency Response Equipment in Technical Support Ctrs Performed to Ensure That Emergency Requirements Satisfied ML20042F1171990-05-0101 May 1990 Submits Special Rept Re Evaluation of third-yr Containment Tendon Surveillance.Tendons Which Had Voids Have Been Filled & No Evidence of Grease Leakage from Sheathing Exists ML20042F3631990-04-30030 April 1990 Provides Summary of Expected Sequence of Events for Updates to Prompt Notification Sys ML20042E6361990-04-20020 April 1990 Forwards Revised Organization Chart,Correcting Postion Titles Reflected in 900326 Submittal ML20042E5421990-04-12012 April 1990 Responds to 900316 Notice of Violation for Insp Repts 50-498/90-08 & 50-499/90-08.Violation Addressed in LER 90-003 Re Failure to Perform Tech Spec Required Surveillance Due to Deficient Procedure ML20042E1591990-04-0505 April 1990 Provides Listed Guidelines for Development of Operating Procedures Re Ac Power Restoration to Respond to Station Blackout Event,Per 10CFR50.63, Loss of All AC Power. ML20012F2881990-04-0202 April 1990 Provides Rept of Nuclear Insurance Protection,Per 10CFR50.54(w)(2).NEIL-II Decontamination Liability & Excess Property Policy Increased Effective 891115 ML20012F2831990-04-0202 April 1990 Informs of Deferral of Facility Mods to Install Permanent RHR Pump Motor Current Indication.Mod Will Be Completed Before Next Reduced RCS Inventory Conditions on Unit ML20012D8731990-03-19019 March 1990 Forwards Revised Correspondence Distribution List of Designated Recipients ML20012C6121990-03-16016 March 1990 Forwards NRC Regulatory Impact Survey Questionnaire Sheets in Response to Generic Ltr 90-01, Request for Voluntary Participation in NRC Regulatory Impact Survey. Brief Summary Table of Questionnaire Data Also Encl ML20012C6171990-03-16016 March 1990 Forwards Status of Actions Committed to Re NRC Bulletin 88-004 in Response to G Dick Request ML20012C2811990-03-12012 March 1990 Forwards Suppl 3 to Qualified Display Processing Sys (Qdps) Verification & Validation Process Final Rept & Summary of Qualified Display Processing Sys (Qdps) Recurring Component Failure Data. ML20012C0641990-03-12012 March 1990 Forwards Rev 15 to Physical Security Plan.Rev Withheld (Ref 10CFR73.21) ML20012B7651990-03-0909 March 1990 Responds to Generic Ltr 88-17, Loss of Dhr. Util Will Revise Appropriate Procedures to Require Entering Reduced Inventory Operation at 3 Ft Below Reactor Vessel Flange ML20042D6701990-03-0808 March 1990 Responds to NRC Generic Ltr 89-19, Resolution of USI A-47,Safety Implication of Control Sys in LWR Nuclear Power Plants. Plant Design Meets Criteria of Generic Ltr 89-19 for Automatic Steam Generator Overfill Protection ML20012A1291990-03-0101 March 1990 Forwards Responses to Questions Raised by Sandia During Review of Plant PRA Covering Steam Generator Dryout ML20012A3001990-02-28028 February 1990 Forwards Nonproprietary & Proprietary Rev 1,Suppl 2 to WCAP-12087 & WCAP-12067, Reconciliation of Fatigue Crack Growth Results for South Texas Project Unit 1 Surge..., Per NRC Bulletin 88-011.WCAP-12067 Withheld (Ref 10CFR2.790) ML20011F1921990-02-22022 February 1990 Responds to NRC 900123 Ltr Re Violations Noted in Insp Repts 50-498/89-47 & 50-499/89-47.Corrective Actions:Heat Trace Circuit Temp Controllers Calibr & Analog Indication Checked & Found within Tolerance on All But Three Channels ML20011E9061990-02-16016 February 1990 Responds to NRC IE Bulletin 89-003, Potential Loss of Required Shutdown Margin During Refueling Operations. Util Concluded That Sufficient Precautions Will Be in Place to Ensure Against Loss of Required Shutdown Margin ML20006D9121990-02-0707 February 1990 Forwards Updated Schedule of Responses to NRC Generic Ltrs 83-28,88-17,88-20,89-05,89-06,89-07,89-08,89-10,89-12,89-13, 89-17,89-19 & 89-21 & Bulletins 88-001,88-008,88-010,88-011, 89-001,89-002,89-003,88-008,Suppl 1 & 88-010,Suppl 1 ML20011E8251990-02-0505 February 1990 Requests Consideration of Scenario Manual for 900404 Graded Emergency Preparedness Exercise as Proprietary Info Until After Graded Exercise ML20006B8801990-01-31031 January 1990 Forwards Comparison of Instrusion Detection Sys Proposed for Various Physical Security Upgrade.Encl Withheld (10CFR73.21) ML20011E1831990-01-30030 January 1990 Requests Approval of Schedular Exemption from 10CFR50,App J, Type C Local Leak Rate Testing Requirements by 900301,based on Interval Between Completion of Unit 1 First Refueling Outage & Second Refueling Outage Start of Only 6 Months ML20011E1361990-01-29029 January 1990 Responds to Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment. Three Bays of Essential Cooling Water Intake Structure Will Be Inspected Once Every 18 Months for Macroscopic Biological Fouling Organisms ML20006A9791990-01-26026 January 1990 Provides Addl Info Re Surge Line Stratification at Facility, Per NRC Bulletin 88-011.W/exception of One Heatup Cycle, Stratification Observed in Surge Line Determined to Be within Bounds of WCAP-12067,Rev 1 ML20006A7981990-01-26026 January 1990 Forwards Response to Violations Noted in Insp Repts 50-498/89-39 & 50-499/89-39.Response Withheld ML20006B3551990-01-23023 January 1990 Forwards Rev 4 to Pump & Valve Inservice Test Plan. Rev Includes Addition of Component Cooling Water Valves FV-0864,FV-0862 & FV-0863 & Containment Sys Valves FV-1025, FV-1026,FV-1027 & FV-1028 1990-09-20
[Table view] |
Text
'
RENAL NEWMAN & HoLTzINGEu, P.C.
JACM R. NEWMAN **' WTLUAM L BAER.JR JOHN E. HOLT 21NGER, JR.
WASHINGTON, C.C. 20036 J EA ON M snct A L o JANET C B ECMER J, A 60VKN#GMT, JR. Lois R. riNKELSTONS 202 955 66OO eRIAN R. GISH GEORGE L, EDGAR MATHLEEN H. SHEA ANDREW N. GREENE' DOUGLAS G. GREEN PANELA A LACEY KAROL LYN NEWMAh FRANK R UNOH f JOHN T. SiouGM. JR. MATHLEEN M MCOERMOTT JEFFREY B. MULHALL*
ALVIN H. GUTTERMAN EDWARO J, TWOMEY PAUL J. SAviDGE' JACOLYN A SIMMONS ROBERT H. SOLOMON THOMASA SCHMyT3 CMARLES C. THEBAUD, JR iStCHAEL F. HEALY F.3BERT L WHITE ROBIN T. W1GGtNS.
STEVEN P. FRANTZ DAVLD B RA$ KIN ROBERT 3 0WENSTEIN KEVIN J. UPSON HERBERT 8. CONN ERNEST C. BAYNARD. Hi QF CQw sta, DONALE, J. SILVE PMAN JOSEPH E. STVBBS eteQT ADee:TTrp se O C.
CQWSEL June 13, 1988 Thomas E. Murley, Director Office of Nuclear Reactor Regulation United States Nuclear Regulatory Commission I Washington, D.C. 20555 Re: Houston Lighting & Power Company, et al.
South Texas Project, Units 1 & 2; Docket No,39-498 OL, 50-499 OL
Dear Mr. Murley:
By letter dated March 22, 1988, Mr. Chilk, the Secretary to the Commission, edvised the Government Accountability Project (GAP) that its "Appeal of Director's Decision on the South Texas Project" (GAP Appeal) has been referred to the NRC Staff to determine whether the "Appeal" raised anything that would cause the Director to reconsider his decision dated March 18, 1988 denying GAP's section 2.206 petition (DD-88-3). For the reasons descrit ed below, Houston Lighting & Power Company (HL&P), on behalf of itself and the other licensees, urges you to reaffirm the denial of the GAP 2.206 petition.
Backaround On January 20, and 21, 1987, newspapers in Texas reported that representatives of GAP had publicly announcedorthat GAP had received information from approximately 36 current former workers on the South Texas Project (STP) which called into 8806160202 880613 'f0b
) PDR ADOCK 05000498 L 8# DCD -.. _-
EWMAN & HoLTzlNOEH. P. C.
Thomas E. Murley, Director June 13, 1988 Page 2 question the safety of the Project. Based on the newspaper articles, the Group Vice President-Nuclear of HL&P wrote to the GAP representative urging her to make the substance of the allegations available to HL&P or the NRC to permit investigation and any necessary corrective action. Although HL&P offered a variety of procedural safeguards to assure the anonymity of the allegers and tha good faith of HL&P's investigations, GAP declined to tell HL&P the substance of the allegations. When it be cani.> appa r e n t , in April 1987, that GAP would not give HL&P access to the allegations, HL&P wrote to the dRC's Executive Director of Operations urging that the NRC investigate the allegations.
Correspondence subsequently revealed b'r GAP and the NRC shows that at the same time that HL&P was negotiating with GAP for access to the allegations, the NRC was also unsuccescfully urging GAP to make the allegations available for investigation.
On May 29, 1987, the NRC issued a subpoena directing the GAP representative, Ms. Garde, to appear to testify about the allegations and to bring with her GAP's records related to the allegations. GAP moved NRC to quash the subpoena, contending that the requested information constituted privileged attorney-client communications and attorney work product. The NRC denied the motion to quash, and ordered Ms. Garde to comply with the subpoena. Nevertheless, when Ms. Garde appeared for her depo-sition on July 27 and August 5, 1987, she testified only regarding the bases for her claims of privilege and refused to ;
provide the allegations or to produce GAP's records.
On August 14, 1987, the United States, on behalf of the NRC, initiated an action in the United States District Court for the District of Columbia, seeking enforcement of the subpoena.
Ms. Garde opposed the Government's Petition, again asserting that the information was pr!vileged as confidential attorney-client communications and attorney work product. GAP intervened on behalf of Ms. Garde, asserting, in part, that disclosure of the identities of the allegers would infringe on their First
, Amendment rights of association. Based on GAP's arguments, on
) October 27, 1987, the District Court decided that the subpoena l
was too broad, and that it should be narrowed to protect the l
First Amendment rights asserted by GAP. The District Court I suggested that the NRC further negotiate with GAP to obtain the information.
On January 26, 1988, GAP filed its 2.206 petition.
Documents attached to that petition, and various other documents l subsequently disclosed by GAP and the NRC, show that in November l 1987, GAP made the allegations available to the ad hoc Safety l Significance Assessment Team (SSAT) which NRC organized to l investigate them. With the consent of GAP, the SSAT reviewed GAP records describing the allegations and interviewed some of the 4
9 hEWMAN & HoLTz NGER, R C.
Thomas E. Murley, Director June 13, 1988 Page 3 allegers by telephone and others in person. One of the allegers also accompanied the SSAT during its investigation at the STP site. The resulta of the SSAT investigation published in March 1988, formed a significant part of the factual basis for the Director's Decision.. The Director also relied on the results of previous NRC inspections and evaluations previously documented in several Safety Evaluation Reports. Director's Decision at 3. In its Petition and in its Appeal GAP now argues that the SSAT did not have sufficient time to perform a proper investigation of the allegations and that the investigation was inadequate in other respects.
Alleaed Inadecuacies of the NRC Investication The crux of GAP's 2.206 complaint, which is again repeated in its Appeal, is that it believes there is an issue regarding the adequacy of HL&P's quality assurance program and c
management character and competence and that the Commission should have done more to investigate GAP's belief before it 1
authorized full power operation. Thus, the first part of the GAP Appeal argues that the Director's Decision was improper because the SSAT did not take sufficient time to properly inves*1 gate the allegations, the SSAT violated 10 C.F.R 50, Appendix B and the SSAT did not investigate all of the allegations. Although NRC is properly situated to judge for itself whether it was able to perform an adequate investigation, HL&P would like to respond to a few of GAP's arguments.
At the Commission meeting on March 21, 1988, the Commission Staff submitted to the Commission as part cf Ata presentation a computation of the number of staff hours spent on inspection and investigation at STP since 1975 -- over 22,500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br />. 1/ The Staff reviewed the fact that the Commission conducted a special investigative inspection in 1979 which resulted in a Show Cause Order. Since 1979, the NRC has main-tained a full time resident inspection office at STP. The NRC conducted a detailed review of the facility design and the preparations for its operation, tne results of which are docu-mented in the Safety Evaluation Report (NUREG-0781) and supple-ments that total over 1000 pages. The applicat in has been reviewed by the Advisory Committee on Reactor Safeguards pursuant to 42 USC 2039, and that Committee has provided its advice to the NRC.
The issues of HL&P management's character and compe-tence and alleged harassment / intimidation of employees were the subject of extensive NRC hearings. In accordance with Section 1/ Transcript of Commission Briefing on Full Power Licensing of the South Texas Project, Unit 1, March 21, 1988, at 46.
NEWMAN & Hot.TztNoza, R C.
Thomas E. Murley, Director June 13, 1988 Page 4 189 of the Atomic Energy Act, at the request of two intervenor groups, the NRC conducted hearings on the application for licenses to operate STP Units 1 and 2. The intervenors' conten-tions addressed the character and competence of HL&P management, the adequacy of facility construction and various other issues.
An Atomic Safety and Licensing Board, designated pursuant to 10 C.F.R. S 2.704, conducted hearings over 65 days between May 1981 and December 1986, received testimony from over 75 witnesses, including 20 NRC staff managers, inspectors and investigators, and accumulated a hearing record that included approximately 16,000 pages of transcript. In a series of decisions in 1983-86 totalling 394 pages the Atomic Safety and Licensing Board decided that HL&P has the necessary character and competence and recom-mended issuance of Operating Licenses. LBP-84-13, 19 NRC 659 (1984); LBP-86-15, 23 NRC 595 (1986); LBP-86-29, 24 NRC 295 (1986), and affirmed by the Atomic Safety and Licensing Appeal Board (ALAB-799, 21 NRC 360 (1985); ALAB-849, 24 NRC 523 (1986).
The Cemmission level of inspection effort has remained intensive.
Of the approximately 350 inspections and investigations performed since 1975, approximately 90 have taken place since the beginning of 1987, the time period during which GAP began accumulating its allegations.
Thus, GAP's allegations and tne response thereto of SSAT and the Director of Nuclear Reactor Regulation do not exist in a vacuum. Tc. the contrary, they exist in an environment in which allegations of the same type have received intensive scrutiny by the commission and its Staff over a long period of time.
The procedures followed by the SSAT were consistent with the NRC guidance on the conduct of investigations of allegations contained in NRC Manual Chapter 0517, "Management of Allegations" and the NRC Policy Statement on the Handling of Late Allegations (50 Fed. Reg. 11030, March 19, 1985). 2/ This NRC guidance makes clear that allegations which are not material to a licensing decision or which are "too vague or general in nature to provide sufficient information for the staff to investigate will receive no further consideration." NUREG-1306 shows that the SSAT fulfilled the requirements of this guidance. It j
2/ The GAP Appeal asserts that the SSAT violated "10 C.F.R.
Part 50, Appendix B Criterion I, which prohibits ' cost and schedule' pressure to override quality review efforts." GAP i
Appeal at 5. There is no evidence that there was "cost and I schedule" pressure on the SSAT or that anything "overrode" its review. Moreover, 10 C.F.R. 50, Appendix B is not applicable to the NRC Staff. That regulation, by its express terms, applies only to Applicants for licenses to i
construct and operate nuclear power plants, and the recipients of such licenses.
NEWMAN & Hor.TzrNonst, R C.
Thomas E. Murley, Director June 13, 1988 Page 5 investigated the allegations which were sufficiently specific to investigate and, in addition, investigated the areas that were the subject of the non-specific GAP allegations. The SSAT determined that the 71 allegations it selected for inspection included the 16 allegations that included specific information and were "representative of the technical concerns conveyed by the allegers represented by GAP, and bounded the 200 allega-tions." NUREG 1306 at 2-6. At the Commission briefing on the issuance of the full power license for STP Unit 1 the Director of the SSAT, Mr. Calvo, described the investigation and was questioned extensively by the Commission regarding its scope and whether the SSAT had enough time. Transcript at 52-67, 70-72.
Mr. Calvo stated that the SSAT "reviewed all (of the) GAP allegations, and has identified no safety issues which will affect safe operation of the South Texas Project facility."
Transcript at 53. He also stated that the SSAT had sufficient time and would have taken longer if it had seen the need to do so. Transcript at 62-63.
As described in much greater detail in the SSAT Report and in the Director's Decision, the effort expended by the SSAT was more than sufficient to evaluate GAP's vague and general allegations. Before the inspection team conducted its on-site investigation, it reviewed GAP's files pertaining to the subject allegations. The SSAT had access to these files for approxi-mately two months preceding the on-site investigation. These files consisted of audio tapes of interviews with the allegers, handwritten text extrapolated from the tapes accompanied with supporting information, and allegation data sheets that contained the alpha-numeric identification and brief description of each allegation. During this review, the SSAT identified approxi-mately 700 allegations provided oy approximately 35 individuals.
Each allegation was reviewed and evaluated for appropriate disposition (Director's Decision at 8), even though many of these allegations were so vague and general that they would not normally be investigated. Director's Decision at 3. However, the Ccamission Staff investigated "many allegations that would normally have been considered too vague or general, in order to confirm that the types of deficiencies alleged either did not exist or would not undermine safety." Id. at 3. Due to the deficiencies of the allegations in terms of specific details, the SSAT developed a program to compensate for the generalized nature of the allegations. As described in the Director's decision:
An essential part of the SSAT program was the development of detailed inspection plans.
These plans (described in NUREG-1306) included all the steps necessary to thoroughly inspect the installed condition at STP and establish a bounding condition for the generalized concerns conveyed by the allegations.
NEWMAN & HoLTz1Nozu. P. C.
Thomas E. Murley, Director June 13, 1988 Page 6 Director's Decision at 9.
GAP contended in its S 2.206 petition that the SSAT team "was given four days to complete the task and report back to NRC management and the Commissioners." This is a gross dis-tortion of the record. While the SSAT was at the site for four days, it put in several weeks of review before the on-site inspection, the equivalent of eight work days at the site, and additional time reviewing and evaluating inspection reports and supporting data. In total, approximately 3000 staff hours were expended to review the subject allegations. Director's Decision at 10.
GAP also complains about how the SSAT counted and categorized the allegations, but GAP itself has provided several different counts of its allegations. 3/ It is apparent that the allegations must be somewhat vague, and subject to being parsed in a variety of ways. In any event, the only issue of importance-is whether the SSAT adequately investigated the allegations, regardless of their number. The GAP Appeal provides no basis for questioning the adequacy of the investigation.
The Alleaations Specifically Mentioned in the GAP Aooeal
- 1. GAP describes an allegatio.1 that "twenty percent of the valves in the plant were installed backwards." GAP Appeal at 13, 14. In support of this allegation GAP cites (and miscon- '
strues) Exhibit 1 to its Appeal, a copy of an internal STP report on the results of quality control inspections during the week ended April 25, 1986. GAP asserts that this report shows that "valses were installed reversed 20 percent of the time." GAP Appeal at 14. 4/
3/ In its May 29, 1987 Petition seeking to quash the subpoena of Billie Pirner Garde, GAP mentions "over 400 serious safety allegations" (at 1), and "over 500 allegations . . .
an overwhelming number (50%) pertain to the safety of the plant . . ." (at 4). In its 2.206 Petition dated January 26, 1988 GAP cites "over 60 ' allegations (at 9),
and in its Appeal dated March 18, 1288 it cites "nearly 700" (at 5).
4/ GAP also cites its Exhibit 1 as basis for stating: (a) the raject rate for instrumentation was an "incredibly high" 67 percent; and (b) "100 percent of the engineering inspection point (sic) for small bore hangers was missing or incorrect." GAP Appeal at 13, 14. Neither point is relied upon by GAP for any argument, and both are laced with innuendo that is without merit. The "incredibly high" (footnote continued)
NzWMAN & HoLTzixozu, P. C.
Thomas E. Murley, Director June 13, 1988 Page 7 GAP misconstrues the data in several respects. First, Exhibit I does not show that many valves were reversed. The GAP is based on figure only oneof valve 20 percent havingthat beenhas been found to highlighted be reversed.by 5/ It does not represent all of the valves in the plant, nor all of the instru-mentation valves, nor all of the instrumentation valves installed during the week ending April 25, 1986. There is no basis for excrapolating from that single valve to the remainder of the valves in the plant. Moreover, Exhibit 1 reports the data for (footnote continued from previous page) reject rate was based on only the 15 inspections during the week ending April 25, 1986. These represent a small portion of the more than 4000 such instrumentation installations in STP Unit 1, which experienced an overall reject rate under ten percent.
The reject rate for final inspections of hangers for small bore pipe was 30 percent, or 8 of the 27 that week. Of the 8 rejects, five were for hardware problems and three related to paper work. The latter three were due to a missing or incorrect Engineering Inspection Point. Thus, GAP's figure of 100 percent actually relates to three of 27 inspections.
In any event, Engineering Inspection Points are not required by NRC regulation, and their omission would not affect safety. HL&P required Field Engineers to inspect these installations prior to the Quality Control Inspection for acceptance, to increase the assurance that installations would be ready for acceptance by the Quality Control Inspectors. Regardless of whether there was any Engineering Inspection, the Quality Control Inspectors covered the acceptance attributes and would identify any concerns not found by Engineering. Moreover, as shown by Exhibit 1, Quality Control determined if an Engineering Inspection Point was omitted.
5/ This can be seen by a careful reading of Exhibit 1. The first page of Exhibit 1 reports the results of the 15 instrumentation final inspections that week. Of those 15 inspection there were ten rejections, including five hardware related rejectirns. The seventh page of the exhibit, titled INSTRUMENTS, shows that 20 % of the hardware rejections were due to "valve reversed." In other words, one fifth of the five instrumentation rejections (i.e., one) was due to identification of a reversed valve. It should also be noted that those instrument inspections encompassed the instrumentation mounting and associated tubing, tube track, and supports. Each inspection therefore consisted of a number of attributes ranging fron dozens to hundreds, any one of which could be the basis for rejection of the installation.
l NEWMAN & HOLTZINOEH, P. C.
Thomas E. Murley, Director June 13, 1988 Page 8 only a single week during a construction process that took years.
The results for one week, without more, cannot reasonably be assumed to represent performance over a period of years. This is particularly true here, since the data cited by GAP in Exhibit 1 is extremely limited.
Second, the valve is no lonaer reversed. Exhibit 1 shows that the reversed valve was identified in a QC inspection.
As required by 10 C.F.R. 50, Appendix B, Criterion XV, the inspection finding resulted in correction of the deficiency; the one valve that was found to be installed reversed was removed and reinstalled in proper orientation. If any message is to be drawn from this report about the quality of valve installations generally at STP, it is that where a valve was installed improperly, it was detected by the qualicy control program and corrected.
Third, the STP OA orocram would have orevented recur-rent improcer installation of valves. Exhibit 1 is an example of a weekly report identifying the results of inspections and the cause of deficiencies. Such reports were used to identify any need for action to prevent the recurrence of deficiencies. If there had been repeated instances of valves being installed backwards, HL&P and its contractors would have taken action in accordance with 10 C.F.R. 50, Appendix B, Criterion XVI, to prevent the repetition of such errors.
Fourth, testina of the systems would have detected the alleaed backwards valvaa. Prior to the start of the SSAT investigative effort STP completed extensive pre-operational and start-up testing which would have identified the condition alleged by GAP (i.e., 20 percent of the valves backwards). The pre-operational and start-up testing was subjected to intensive NRC inspection.
In snort, there is no reason why the SSAT should have considered GAP's Exhibit 1 as evidence that supports the prepos-terous allegation that 20 percent of the valves are installed backwards.
- 2. A second allegation mentioned by GAP is that "installed equipment is not properly reflected by the as-built design drawings." GAP Appeal at 14-15. GAP cites as evidence in l support of this allegation its Exhibit 2, which reflects a l clarification of the assigned responsibility between different l EBASCO groups for technical review of the installation documents which support ASME N-5 certification packages. {/ GAP claims
{/ GAP alleges that EBASCO "terminated the responsibilities of l the final quality review for the N-5 group and changed it to l (footnote continued) l l
l
\
L
~
$EWMAN & HoLTz1NOEH, P. C.
Thomas E. Murley, Director June 13, 1988 Page 9 that the SSAT investigation of this claim was flawed because the SSAT based its resolution of the issue on review of the Reactor Makeup Water and Essential Cooling Water systems. According to GAP, this sample size was inadequate, and "more importantly, the section of pipe that the staff looked at had already been subjected to various inspections and reviews while the alleger was working according to the original procedures." GAP Appeal at 14.
Apparently GAP's first criticism is based on the premise that the SSAT should have been required to reinspect all or large parts of the plant because the allegation was vague and did not identify any specific deficiencies. There is no valid basis for this position. In essence, the allegation, as reported in Section 5.9 of the NUREG-1306, and by GAP at 14-15, was that documentation of actual plant configuration was generally incorrect. It was reasonable for the SSAT to test that general-ization by review of a sample. Moreover, the SSAT also performed a review of procedures, records of NRC inspections and project investigation, inspection, audit and surveillance activities.
NUREG-1306 at 5-80 through 5-84.
As to GAP's "more important" criticism, it is based on the assertion that the piping reviewed by the SSAT was installed before the December 4, 1985 clarification of responsibilities within EBASCO reflected by Exhibit 2. The work on the Reactor Makeup Water System N-5 packages was done during that early time frame (i.e., 1985), but the packages for the Essential Cooling Water System were completed in 1987, long after the clarification of responsibility for the technical review of N-5 packages.
Thus, the work reviewed by the SSAT was representative of both periods.
- 3. The balance of the GAP criticisms of the SSAT investigation relate to several cases currently pending before the Department of Labor under Section 210 of the Energy Reorganization Act of 1974. HL&P has investigated each cf the cases to assure that the contractors engaged in the design and construction of STP are complying with the requirements of Federal law and regulations, including the provisions of Section 210. It also has been performing Quality Assurance audits of contractors' personnel systems to assure that the contractors are in compliance with Section 210 and 10 C.F.R. 50.7. Based on (footnote continued from previous page) a straight accounting task, eliminating the requirement for verificatiwn of correctness, completeness, and the as-built walkdown." GAP Appeal at 14. That is simply not true; such verification continued to be done by EBASCO.
{
t
NEWMAN & HoLTztwonn, P. C.
Thomas E. Murley, Director June 13, 1988 Page 10 these audits, actions have been taken to strengthen the con-tractor programs that assure compliance with Section 210 and Section 50.7.
HL&P's conclusion that it and its contractors are complying with the law and regulations is supported by the fact that there have been only a few complaints filed out of the tens of thousands of individuals who have been employed at STP. The fact that some cases are pending before the Department of Labor is not material to the NRC licensing decision. However, if the Department of Labor decides against the employers, HL&P will review the decisions to determine if additional action is required to assure compliance at STP. In that eventuality, GAP will certainly be able to bring that matter to NRC's attention, and the NRC can then determine if further action is required.
The GAP Appeal refers only to a few quality concerns of the complainants in those Section 210 cases, and does not provide any specific allegations about the safety of STP. At page 16, GAP cites a concern raised by Mr. Goldstein about a "thermoweld",
but does not contend that this was an allegation that SSAT did not properly investigate. HL&P investigaced and resolved this allegation when it was reported to it by Mr. Goldstein. GAP cites no basis for questioning that resolution. 7/
7/ This appears to be the allegation discussed by NUREG-1306 at 5 a6. If so, the NUREG indicates that Mr. Goldstein agreed that the concern was properly resolved.
NzwMAN & Hot.Tztwoza, P. C.
Thomas E. Murley, Director June 13, 1988 Page 11 d
The GAP Appeal also mentions coatings allegations and complains that the SSAT interviewed only one coatings inspector and that that inspector had additional information not reviewed by the SSAT. However, nowhere does GAP provide such information ci otherwise identify any deficiency in the quality of STP construction.
f Respectfully submitted, Y JLan, %
ack R. Newman'[
Attorney for Hodston Light
& Power Company, Project Manager of the South Texas Project, acting herein on behalf of itself and the other licensees, CITY OF SAN ANTONIO,. TEXAS, acting by and through the City Public Service Board of the City of San Antonio, CENTRAL POWER AND LIGHT COMPANY and CITY 7F AUSTIN, TEXAS
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of )
)
HOUSTON LIGHTING & POWER ) Docket Nos. 50-498 OL COMPANY, ET AL. ) 50-499 OL
)
(South Texas Project, )
. Units 1 and 2) )
CERTIFICATE OF SERVICE I hereby certify that copies of the letter to Thomas E. Murley from Jack R. Newman, dated June 13, 1988, have been served on the following individuals and entities by deposit in the United States mail, first-class, postage prepaid, or by arranging for delivery by messenger as indicated by asterisk, this 13th day of June, 1988.
Ms. Billie P. Garde Director of the Midwest Office Government Accountability Project l 3424 North Marcos Lane Appleton, Wisconsin 54911 Richard E. Condit Government Accountability Project 1555 Connecticut Avenue, NW Suite 202 Washington, D.C. 20036 William Paton*
Office of the General Counsel U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Office of the Secretary
- U.S. Nuclear Pegulatory Commission Washington, D.C. 20555
,$x a w Jack R. Newman'
-- ~ -