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Category:CORRESPONDENCE-LETTERS
MONTHYEARNOC-AE-000675, Forwards Clarification on Items Included in 990531 Response to RAI Re Proposed License Amend Associated with Operator Action for Sbloca,As Requested1999-10-21021 October 1999 Forwards Clarification on Items Included in 990531 Response to RAI Re Proposed License Amend Associated with Operator Action for Sbloca,As Requested NOC-AE-000680, Forwards Rev 5 to 0PGP03-ZV-0001, Severe Weather Plan1999-10-20020 October 1999 Forwards Rev 5 to 0PGP03-ZV-0001, Severe Weather Plan NOC-AE-000683, Forwards 30-day Rept Concerning Significant Changes to Accepted Large Break Loss of Coolant Accident ECCS Evaluation Model for South Tx Project,Units 1 & 2,IAW 10CFR50.46(a)(3)(ii)1999-10-19019 October 1999 Forwards 30-day Rept Concerning Significant Changes to Accepted Large Break Loss of Coolant Accident ECCS Evaluation Model for South Tx Project,Units 1 & 2,IAW 10CFR50.46(a)(3)(ii) ML20217K9341999-10-15015 October 1999 Forwards SER Accepting Util 990609 Relief Request RR-ENG-2-4 for Relief from ASME Code,Section XI, Nondestructive Exam Requirements Applicable to Stp,Units 1 & 2,reactor Vessel Closure Head Nuts ML20217K9091999-10-15015 October 1999 Forwards SER Accepting Util 990609 Relief Request RR-ENG-2-3 from ASME Code,Section Xi,Nondestructive Exam Requirements Applicable to South Texas Project,Units 1 & 2, Pressurizer Support Attachment Welds 05000498/LER-1999-008, Forwards LER 99-008-00 Re Turbine Trip That Occurred While Performing Main Turbine Emergency Trip Test.Commitments Made by Licensee Are Listed in Corrective Actions Section of LER1999-10-12012 October 1999 Forwards LER 99-008-00 Re Turbine Trip That Occurred While Performing Main Turbine Emergency Trip Test.Commitments Made by Licensee Are Listed in Corrective Actions Section of LER NOC-AE-000674, Forwards Requested Estimates of Needs for Operator Licensing Exams,Per AL-99-03, Operator Licensing National Exam Schedule1999-10-12012 October 1999 Forwards Requested Estimates of Needs for Operator Licensing Exams,Per AL-99-03, Operator Licensing National Exam Schedule NOC-AE-000625, Requests Partial Relief from ASME Section XI Visual Exam Requirements of IWA-5242(a).Relief Request Is Based on Provisions of Draft ASME Section XI Code Case N-616,which Is Expected to Be Published in Near Future1999-10-0707 October 1999 Requests Partial Relief from ASME Section XI Visual Exam Requirements of IWA-5242(a).Relief Request Is Based on Provisions of Draft ASME Section XI Code Case N-616,which Is Expected to Be Published in Near Future NOC-AE-000610, Requests Relief from ASME Section XI Code Nondestructive Exam Requirements of IWA-5250(a)(2) for Second Inservice Insp Interval,Per Provisions of 10CFR50.55a(3)(i)1999-10-0707 October 1999 Requests Relief from ASME Section XI Code Nondestructive Exam Requirements of IWA-5250(a)(2) for Second Inservice Insp Interval,Per Provisions of 10CFR50.55a(3)(i) NOC-AE-000653, Requests Relief from ASME Section XI Code Requirements of Table IWE-2500-1 for VT-3 Visual Exam of Seals & Gaskets on Airlocks,Hatches & Other Devices Required to Assure Containment leak-tight Integrity,Per 10CFR50.55a(a)(3)(i)1999-10-0707 October 1999 Requests Relief from ASME Section XI Code Requirements of Table IWE-2500-1 for VT-3 Visual Exam of Seals & Gaskets on Airlocks,Hatches & Other Devices Required to Assure Containment leak-tight Integrity,Per 10CFR50.55a(a)(3)(i) ML20217C3221999-10-0707 October 1999 Forwards Insp Repts 50-498/99-16 & 50-499/99-16 on 990808-0918.No Violations Noted.Insp Generally Characterized by safety-conscious Operations,Sound Engineering & Maint Practices & Careful Radiological Work Controls 05000499/LER-1999-006, Forwards LER 99-006-00,re Entry Into TS 3.0.3.Licensee Commitments Listed in Corrective Actions Section of Attachment1999-09-30030 September 1999 Forwards LER 99-006-00,re Entry Into TS 3.0.3.Licensee Commitments Listed in Corrective Actions Section of Attachment ML20212L1651999-09-30030 September 1999 Responds to STP Nuclear Operating Co 981012 & s Which Provided Update to TS Bases Pages B 3/4 8-14 Through B 3/4 8-17.NRC Staff Found Change Consistent with TS 3/4.8.2 DC Sources. Staff Found & Deleted Typographical Error NOC-AE-000664, Forwards Rev 1 to STP Electric Generating Station Unit 1 Cycle 9 COLR & Rev 1 to STP Electric Generating Station Unit 2 Cycle 7 Colr1999-09-30030 September 1999 Forwards Rev 1 to STP Electric Generating Station Unit 1 Cycle 9 COLR & Rev 1 to STP Electric Generating Station Unit 2 Cycle 7 Colr ML20212J7141999-09-29029 September 1999 Forwards Insp Repts 50-498/99-15 & 50-499/99-15 on 990920-24 at South Texas Project Electric Generating Station.No Violations Noted.Insp Covered Requalification Training Program & Observation of Requalification Activities NOC-AE-000646, Informs NRC That STP Nuclear Operating Co Is Y2K Ready IAW Nei/Nusmg 97-07 Guidelines & Also Provides Response to NRC Ltr1999-09-28028 September 1999 Informs NRC That STP Nuclear Operating Co Is Y2K Ready IAW Nei/Nusmg 97-07 Guidelines & Also Provides Response to NRC Ltr ML20212J0651999-09-27027 September 1999 Discusses Licensee 980330 Response to GL 97-06, Degradation of SG Internals. Concludes That Response to GL Provides Reasonable Assurance That Condition of SG Internals in Compliance with Current Licensing Bases for Facility ML20212F1791999-09-24024 September 1999 Discusses 990923 Meeting Conducted in Region IV Ofc Re Status of Activities to Support Confirmatory Order, ,modifying OL & to Introduce New Director,Safety Quality Concerns Program.List of Attendees Encl ML20212E9091999-09-23023 September 1999 Discusses GL 98-01, Year 2000 Readiness of Computer Sys at Npps, Supplement 1 & STP Nuclear Operating Co Response for STP Dtd 990629.Understands That at Least One Sys or Component Listed May Have Potential to Cause Transient ML20212F2111999-09-22022 September 1999 Forwards Review of SG 90-day Rept, South Texas Unit-2 Cycle 7 Voltage-Based Repair Criteria Rept, Submitted by Util on 990119 NOC-AE-000633, Forwards Rev 3 to SG-99-04-005, STP 1RE08 Outage Condition Monitoring Rept & Final Operational Assessment. Rept Satisfies Reporting Requirements of NEI 97-06,dtd Dec 19971999-09-21021 September 1999 Forwards Rev 3 to SG-99-04-005, STP 1RE08 Outage Condition Monitoring Rept & Final Operational Assessment. Rept Satisfies Reporting Requirements of NEI 97-06,dtd Dec 1997 NOC-AE-000634, Forwards Addl Info Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Povs. MOV design-basis Review Checklist,Encl1999-09-21021 September 1999 Forwards Addl Info Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Povs. MOV design-basis Review Checklist,Encl NOC-AE-000649, Forwards Current Annual Financial Data for STP Electric Generating Station Per 10CFR50.71(b),acting on Behalf of Central Power & Light Co,City of Austin,Tx,City Public Svc Board of San Antonio & Hl&P1999-09-21021 September 1999 Forwards Current Annual Financial Data for STP Electric Generating Station Per 10CFR50.71(b),acting on Behalf of Central Power & Light Co,City of Austin,Tx,City Public Svc Board of San Antonio & Hl&P 05000499/LER-1999-005, Forwards LER 99-005-00,re Esfa Following Loss of Power to Standby Transformer 2 Due to Electrical Fault.Licensee Commitments Are Listed in Corrective Actions Section of LER1999-09-20020 September 1999 Forwards LER 99-005-00,re Esfa Following Loss of Power to Standby Transformer 2 Due to Electrical Fault.Licensee Commitments Are Listed in Corrective Actions Section of LER ML20212D9171999-09-16016 September 1999 Informs That on 990818,NRC Completed Midcycle PPR of South Texas Project & Identified No Areas in Which Performance Warranted Insp Beyond Core Insp Program.Details of Insp Plan Through Mar 2000 & Historical Listing of Plant Issues,Encl ML20216F5471999-09-15015 September 1999 Discusses 990914 Meeting Conducted at Region Iv.Meeting Was Requested by Staff to Introduce New Management Organization to Region IV & to Discuss General Plant Performance & Mgt Challenges IR 05000498/19990121999-09-14014 September 1999 Forwards Insp Repts 50-498/99-12 & 50-499/99-12 on 990816-19.Three Violations Occurred & Being Treated as Ncvs. Areas Examined During Insp Included Portions of Access Authorization & Physical Security Programs 05000498/LER-1999-007, Forwards LER 99-007-00 Re Train 'B' CR Makeup & Cleanup Filtration Sys Being Inoperable for Greater than Aot.Util Intends to Append Addl Info Section of LER with Brief Description of Test Results,Rather than Submit Separate LER1999-09-13013 September 1999 Forwards LER 99-007-00 Re Train 'B' CR Makeup & Cleanup Filtration Sys Being Inoperable for Greater than Aot.Util Intends to Append Addl Info Section of LER with Brief Description of Test Results,Rather than Submit Separate LER ML20211P8201999-09-0909 September 1999 Forwards SE Authorizing 990224 Submittal of First 10-year Interval ISI Program Plan - Relief Request RR-ENG-24,from ASME Section XI Code,Table IWC-2500-1 NOC-AE-000638, Forwards License Renewal Applications & Certifications of Medical Exam for Seven Listed Licensed Operators at Stp,Per 10CFR55.57.Encl Withheld,Per 10CFR2.790(a)(6)1999-09-0909 September 1999 Forwards License Renewal Applications & Certifications of Medical Exam for Seven Listed Licensed Operators at Stp,Per 10CFR55.57.Encl Withheld,Per 10CFR2.790(a)(6) ML20211P7671999-09-0909 September 1999 Forwards SER Authorizing Licensee 990517 Alternative Proposed in Relief Request RR-ENG-2-8 to Code Case N-491-2 for Second 10-year Insp Interval of South Texas Project, Units 1 & 2,pursuant to 10CFR50.55a(a)(3)(i) ML20211P7871999-09-0909 September 1999 Forwards Safety Evaluation Re First 10-yr Interval Inservice Insp Program Plan Request for Relief RR-ENG-31 IR 05000498/19990141999-09-0303 September 1999 Forwards Insp Repts 50-498/99-14 & 50-499/99-14 on 990627-0807.Apparent Violations Identified & Being Treated as Noncited Violations Consistent with App C of Enforcement Policy NOC-AE-000562, Requests Relief from Contruction Code non-destructive Exam Requirements for Repair/Replacement Activities During Second Inservice Insp Interval of Units 1 & 2,IAW Provisions of 10CFR50.55a(a)(3)(i)1999-08-31031 August 1999 Requests Relief from Contruction Code non-destructive Exam Requirements for Repair/Replacement Activities During Second Inservice Insp Interval of Units 1 & 2,IAW Provisions of 10CFR50.55a(a)(3)(i) ML20212A4351999-08-27027 August 1999 Discusses Investigation Rept OI-4-1999-009 Re Activites at South Texas Project.Oi Investigation Initiated in Response to Alleged Employment Discrimination Complaint. Allegation Not Substantiated.No Further Action Planned NOC-AE-000617, Forwards semi-annual Fitness for Duty Program Performance Rept for 990101-990630,IAW 10CFR26.71(d)1999-08-26026 August 1999 Forwards semi-annual Fitness for Duty Program Performance Rept for 990101-990630,IAW 10CFR26.71(d) ML20211J2511999-08-26026 August 1999 Discusses Proposed TS Change on Replacement SG Water Level Trip Setpoint for Plant,Units 1 & 2 NOC-AE-000585, Provides Notification That South Texas Project Has Completed Integrity Evaluation of Units 1 & 2 Reactor Coolant Pump Casings Required by Paragraph (D) of Code Case N-4811999-08-25025 August 1999 Provides Notification That South Texas Project Has Completed Integrity Evaluation of Units 1 & 2 Reactor Coolant Pump Casings Required by Paragraph (D) of Code Case N-481 ML20211F4421999-08-24024 August 1999 Forwards SE Authorizing Licensee 990513 Request for Relief RR-ENG-2-13,seeking Relief from ASME B&PV Code Section Xi,Exam Vessel shell-to-flange Welds for Second ISI Intervals ML20211F5031999-08-23023 August 1999 Forwards SE Authorizing Licensee 990315 Request for Relief RR-ENG-30,seeking Relief from ASME B&PV Code,Section Xi,Nde Requirements Applicable to Stp,Unit 2 SG Welds ML20212A4391999-08-17017 August 1999 Discusses Investigation Rept OI-4-1999-023 Re Activities at South Texas Project.Oi Investigation Initiated in Response to Alleged Employment Discrimination for Initiating Condition Report to Document Unauthorized Work Practices ML20210U1271999-08-16016 August 1999 Forwards Insp Repts 50-498/99-08 & 50-499/99-08 on 990517-21 & 0607-10.No Violations Noted.Corrective Action Program Was Reviewed ML20211A9501999-08-12012 August 1999 Discusses 990720-21 Workshop Conducted in Region IV Ofc,Re Exchange of Info in Area of Use of Risk Insights in Regulatory Activities.List of Attendees,Summary of Topic & Issues,Agenda & Copies of Handouts Encl ML20211B7881999-08-10010 August 1999 Transmits Summary of Two Meetings with Risk-Informed TS Task Force in Rockville,Md on 990514 & 0714 ML20210L1461999-08-0303 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Requests Submittal of Ltr Identifying Individuals Taking Exam,Personnel Allowed Access to Exams & Mailing Address for Exams NOC-AE-000603, Informs of Addition of Restriction to SRO License 42658, for KM Espinoza,Effective 990721,per 10CFR50.74.Encl Info Withheld,Per 10CFR2.790(a)(6)1999-07-29029 July 1999 Informs of Addition of Restriction to SRO License 42658, for KM Espinoza,Effective 990721,per 10CFR50.74.Encl Info Withheld,Per 10CFR2.790(a)(6) NOC-AE-000470, Forwards Amend 12 to STP Fire Hazards Analysis Rept. Summary of Changes Made Under Provision of 10CFR50.59 Also Encl1999-07-28028 July 1999 Forwards Amend 12 to STP Fire Hazards Analysis Rept. Summary of Changes Made Under Provision of 10CFR50.59 Also Encl NOC-AE-000599, Forwards STP Unit 1,Cycle 9 Startup Testing Summary Rept. No New Licensing Commitments Contained in Ltr1999-07-28028 July 1999 Forwards STP Unit 1,Cycle 9 Startup Testing Summary Rept. No New Licensing Commitments Contained in Ltr NOC-AE-000589, Forwards Rev to 1RE08 ISI Summary Repts for Repairs & Replacements & for Sys Pressure Tests,Corecting Date of End of Insp Interval Provided in Item 9 of from NIS-1 from 09/24/99 to 09/24/20001999-07-26026 July 1999 Forwards Rev to 1RE08 ISI Summary Repts for Repairs & Replacements & for Sys Pressure Tests,Corecting Date of End of Insp Interval Provided in Item 9 of from NIS-1 from 09/24/99 to 09/24/2000 ML20210F3851999-07-26026 July 1999 Forwards Exam Repts 50-498/99-301 & 50-499/99-301 on 990706- 15.Exam Included Evaluation of 9 Applicants for SO Licenses & 8 Applicants for RO Licenses 1999-09-09
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARNOC-AE-000675, Forwards Clarification on Items Included in 990531 Response to RAI Re Proposed License Amend Associated with Operator Action for Sbloca,As Requested1999-10-21021 October 1999 Forwards Clarification on Items Included in 990531 Response to RAI Re Proposed License Amend Associated with Operator Action for Sbloca,As Requested NOC-AE-000680, Forwards Rev 5 to 0PGP03-ZV-0001, Severe Weather Plan1999-10-20020 October 1999 Forwards Rev 5 to 0PGP03-ZV-0001, Severe Weather Plan NOC-AE-000683, Forwards 30-day Rept Concerning Significant Changes to Accepted Large Break Loss of Coolant Accident ECCS Evaluation Model for South Tx Project,Units 1 & 2,IAW 10CFR50.46(a)(3)(ii)1999-10-19019 October 1999 Forwards 30-day Rept Concerning Significant Changes to Accepted Large Break Loss of Coolant Accident ECCS Evaluation Model for South Tx Project,Units 1 & 2,IAW 10CFR50.46(a)(3)(ii) NOC-AE-000674, Forwards Requested Estimates of Needs for Operator Licensing Exams,Per AL-99-03, Operator Licensing National Exam Schedule1999-10-12012 October 1999 Forwards Requested Estimates of Needs for Operator Licensing Exams,Per AL-99-03, Operator Licensing National Exam Schedule 05000498/LER-1999-008, Forwards LER 99-008-00 Re Turbine Trip That Occurred While Performing Main Turbine Emergency Trip Test.Commitments Made by Licensee Are Listed in Corrective Actions Section of LER1999-10-12012 October 1999 Forwards LER 99-008-00 Re Turbine Trip That Occurred While Performing Main Turbine Emergency Trip Test.Commitments Made by Licensee Are Listed in Corrective Actions Section of LER NOC-AE-000625, Requests Partial Relief from ASME Section XI Visual Exam Requirements of IWA-5242(a).Relief Request Is Based on Provisions of Draft ASME Section XI Code Case N-616,which Is Expected to Be Published in Near Future1999-10-0707 October 1999 Requests Partial Relief from ASME Section XI Visual Exam Requirements of IWA-5242(a).Relief Request Is Based on Provisions of Draft ASME Section XI Code Case N-616,which Is Expected to Be Published in Near Future NOC-AE-000610, Requests Relief from ASME Section XI Code Nondestructive Exam Requirements of IWA-5250(a)(2) for Second Inservice Insp Interval,Per Provisions of 10CFR50.55a(3)(i)1999-10-0707 October 1999 Requests Relief from ASME Section XI Code Nondestructive Exam Requirements of IWA-5250(a)(2) for Second Inservice Insp Interval,Per Provisions of 10CFR50.55a(3)(i) NOC-AE-000653, Requests Relief from ASME Section XI Code Requirements of Table IWE-2500-1 for VT-3 Visual Exam of Seals & Gaskets on Airlocks,Hatches & Other Devices Required to Assure Containment leak-tight Integrity,Per 10CFR50.55a(a)(3)(i)1999-10-0707 October 1999 Requests Relief from ASME Section XI Code Requirements of Table IWE-2500-1 for VT-3 Visual Exam of Seals & Gaskets on Airlocks,Hatches & Other Devices Required to Assure Containment leak-tight Integrity,Per 10CFR50.55a(a)(3)(i) 05000499/LER-1999-006, Forwards LER 99-006-00,re Entry Into TS 3.0.3.Licensee Commitments Listed in Corrective Actions Section of Attachment1999-09-30030 September 1999 Forwards LER 99-006-00,re Entry Into TS 3.0.3.Licensee Commitments Listed in Corrective Actions Section of Attachment NOC-AE-000664, Forwards Rev 1 to STP Electric Generating Station Unit 1 Cycle 9 COLR & Rev 1 to STP Electric Generating Station Unit 2 Cycle 7 Colr1999-09-30030 September 1999 Forwards Rev 1 to STP Electric Generating Station Unit 1 Cycle 9 COLR & Rev 1 to STP Electric Generating Station Unit 2 Cycle 7 Colr NOC-AE-000646, Informs NRC That STP Nuclear Operating Co Is Y2K Ready IAW Nei/Nusmg 97-07 Guidelines & Also Provides Response to NRC Ltr1999-09-28028 September 1999 Informs NRC That STP Nuclear Operating Co Is Y2K Ready IAW Nei/Nusmg 97-07 Guidelines & Also Provides Response to NRC Ltr NOC-AE-000633, Forwards Rev 3 to SG-99-04-005, STP 1RE08 Outage Condition Monitoring Rept & Final Operational Assessment. Rept Satisfies Reporting Requirements of NEI 97-06,dtd Dec 19971999-09-21021 September 1999 Forwards Rev 3 to SG-99-04-005, STP 1RE08 Outage Condition Monitoring Rept & Final Operational Assessment. Rept Satisfies Reporting Requirements of NEI 97-06,dtd Dec 1997 NOC-AE-000634, Forwards Addl Info Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Povs. MOV design-basis Review Checklist,Encl1999-09-21021 September 1999 Forwards Addl Info Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Povs. MOV design-basis Review Checklist,Encl NOC-AE-000649, Forwards Current Annual Financial Data for STP Electric Generating Station Per 10CFR50.71(b),acting on Behalf of Central Power & Light Co,City of Austin,Tx,City Public Svc Board of San Antonio & Hl&P1999-09-21021 September 1999 Forwards Current Annual Financial Data for STP Electric Generating Station Per 10CFR50.71(b),acting on Behalf of Central Power & Light Co,City of Austin,Tx,City Public Svc Board of San Antonio & Hl&P 05000499/LER-1999-005, Forwards LER 99-005-00,re Esfa Following Loss of Power to Standby Transformer 2 Due to Electrical Fault.Licensee Commitments Are Listed in Corrective Actions Section of LER1999-09-20020 September 1999 Forwards LER 99-005-00,re Esfa Following Loss of Power to Standby Transformer 2 Due to Electrical Fault.Licensee Commitments Are Listed in Corrective Actions Section of LER 05000498/LER-1999-007, Forwards LER 99-007-00 Re Train 'B' CR Makeup & Cleanup Filtration Sys Being Inoperable for Greater than Aot.Util Intends to Append Addl Info Section of LER with Brief Description of Test Results,Rather than Submit Separate LER1999-09-13013 September 1999 Forwards LER 99-007-00 Re Train 'B' CR Makeup & Cleanup Filtration Sys Being Inoperable for Greater than Aot.Util Intends to Append Addl Info Section of LER with Brief Description of Test Results,Rather than Submit Separate LER NOC-AE-000638, Forwards License Renewal Applications & Certifications of Medical Exam for Seven Listed Licensed Operators at Stp,Per 10CFR55.57.Encl Withheld,Per 10CFR2.790(a)(6)1999-09-0909 September 1999 Forwards License Renewal Applications & Certifications of Medical Exam for Seven Listed Licensed Operators at Stp,Per 10CFR55.57.Encl Withheld,Per 10CFR2.790(a)(6) NOC-AE-000562, Requests Relief from Contruction Code non-destructive Exam Requirements for Repair/Replacement Activities During Second Inservice Insp Interval of Units 1 & 2,IAW Provisions of 10CFR50.55a(a)(3)(i)1999-08-31031 August 1999 Requests Relief from Contruction Code non-destructive Exam Requirements for Repair/Replacement Activities During Second Inservice Insp Interval of Units 1 & 2,IAW Provisions of 10CFR50.55a(a)(3)(i) NOC-AE-000617, Forwards semi-annual Fitness for Duty Program Performance Rept for 990101-990630,IAW 10CFR26.71(d)1999-08-26026 August 1999 Forwards semi-annual Fitness for Duty Program Performance Rept for 990101-990630,IAW 10CFR26.71(d) NOC-AE-000585, Provides Notification That South Texas Project Has Completed Integrity Evaluation of Units 1 & 2 Reactor Coolant Pump Casings Required by Paragraph (D) of Code Case N-4811999-08-25025 August 1999 Provides Notification That South Texas Project Has Completed Integrity Evaluation of Units 1 & 2 Reactor Coolant Pump Casings Required by Paragraph (D) of Code Case N-481 NOC-AE-000603, Informs of Addition of Restriction to SRO License 42658, for KM Espinoza,Effective 990721,per 10CFR50.74.Encl Info Withheld,Per 10CFR2.790(a)(6)1999-07-29029 July 1999 Informs of Addition of Restriction to SRO License 42658, for KM Espinoza,Effective 990721,per 10CFR50.74.Encl Info Withheld,Per 10CFR2.790(a)(6) NOC-AE-000599, Forwards STP Unit 1,Cycle 9 Startup Testing Summary Rept. No New Licensing Commitments Contained in Ltr1999-07-28028 July 1999 Forwards STP Unit 1,Cycle 9 Startup Testing Summary Rept. No New Licensing Commitments Contained in Ltr NOC-AE-000470, Forwards Amend 12 to STP Fire Hazards Analysis Rept. Summary of Changes Made Under Provision of 10CFR50.59 Also Encl1999-07-28028 July 1999 Forwards Amend 12 to STP Fire Hazards Analysis Rept. Summary of Changes Made Under Provision of 10CFR50.59 Also Encl 05000498/LER-1999-006, Forwards LER 99-006-00 Re Automatic Reactor Trip Due to over-temp delta-temp Actuation.Licensee Commitments Are Listed in Corrective Actions Section of LER1999-07-26026 July 1999 Forwards LER 99-006-00 Re Automatic Reactor Trip Due to over-temp delta-temp Actuation.Licensee Commitments Are Listed in Corrective Actions Section of LER NOC-AE-000589, Forwards Rev to 1RE08 ISI Summary Repts for Repairs & Replacements & for Sys Pressure Tests,Corecting Date of End of Insp Interval Provided in Item 9 of from NIS-1 from 09/24/99 to 09/24/20001999-07-26026 July 1999 Forwards Rev to 1RE08 ISI Summary Repts for Repairs & Replacements & for Sys Pressure Tests,Corecting Date of End of Insp Interval Provided in Item 9 of from NIS-1 from 09/24/99 to 09/24/2000 NOC-AE-000582, Forwards 1RE08 ISI Summary Rept for Welds & Component Supports of STP Electric Generating Station,Unit 1. Summary Rept Satisfies Reporting Requirements of IWA-6000 of Section XI for Welds & Component Supports1999-07-26026 July 1999 Forwards 1RE08 ISI Summary Rept for Welds & Component Supports of STP Electric Generating Station,Unit 1. Summary Rept Satisfies Reporting Requirements of IWA-6000 of Section XI for Welds & Component Supports NOC-AE-000597, Forwards voltage-based Criteria 90-day Rept for SG Tube Exam Performed Under NRC GL 95-05 During Refueling Outage 1RE08. Rept Contains Info Required by Section 6.b of Attachment 2 to GL 95-051999-07-23023 July 1999 Forwards voltage-based Criteria 90-day Rept for SG Tube Exam Performed Under NRC GL 95-05 During Refueling Outage 1RE08. Rept Contains Info Required by Section 6.b of Attachment 2 to GL 95-05 NOC-AE-000598, Forwards Four Copies of 1RE08 Refueling Outage ISI Summary Rept for Steam Generator Tubing1999-07-23023 July 1999 Forwards Four Copies of 1RE08 Refueling Outage ISI Summary Rept for Steam Generator Tubing NOC-AE-00586, Forwards Results of Control Rod Testing,In Response to NRC Bulletin 96-01, Control Rod Insertion Problems, Dtd 960308.Core Map Provided to Assist in Understanding Test Data1999-07-21021 July 1999 Forwards Results of Control Rod Testing,In Response to NRC Bulletin 96-01, Control Rod Insertion Problems, Dtd 960308.Core Map Provided to Assist in Understanding Test Data NOC-AE-000595, Forwards Chapters 1.0 & 16.0 to Operations QA Plan for South Texas Project.Rev Is Strictly Administrative & All Content Was Previously Submitted to NRC on 990503 & 9906151999-07-21021 July 1999 Forwards Chapters 1.0 & 16.0 to Operations QA Plan for South Texas Project.Rev Is Strictly Administrative & All Content Was Previously Submitted to NRC on 990503 & 990615 NOC-AE-000518, Requests Exemption from Various Special Treatment Requirements of 10CFR50,as Described in Encls to Ltr.Stp Believes That Pilot Application Will Assist NRC in Development & Implementation of risk-informed 10CFR501999-07-13013 July 1999 Requests Exemption from Various Special Treatment Requirements of 10CFR50,as Described in Encls to Ltr.Stp Believes That Pilot Application Will Assist NRC in Development & Implementation of risk-informed 10CFR50 NOC-AE-000536, Submits Request for Exemption from Requirements of 10CFR50.34(b)(11),10CFR50,App A,Gdc 2 & 10CFR100,App a, Section VI(a)(3) Re Maint of Seismic Instrumentation.Revised Page to Procedure OERP01-ZV-IN01 Included1999-07-13013 July 1999 Submits Request for Exemption from Requirements of 10CFR50.34(b)(11),10CFR50,App A,Gdc 2 & 10CFR100,App a, Section VI(a)(3) Re Maint of Seismic Instrumentation.Revised Page to Procedure OERP01-ZV-IN01 Included NOC-AE-000580, Forwards Response to NRC 990415 RAI Re Implementation of Commitments Related to GL 89-10, Safety-Related MOV Testing & Surveillance & GL 96-05, Periodic Verification of Design Basis Capability of Safety-Related Movs1999-07-13013 July 1999 Forwards Response to NRC 990415 RAI Re Implementation of Commitments Related to GL 89-10, Safety-Related MOV Testing & Surveillance & GL 96-05, Periodic Verification of Design Basis Capability of Safety-Related Movs NOC-AE-000574, Forwards ISI Summary Repts for Repairs & Replacements & for Sys Pressure Tests Performed Between 971004 & Completion of Eighth RO on 9904281999-07-0606 July 1999 Forwards ISI Summary Repts for Repairs & Replacements & for Sys Pressure Tests Performed Between 971004 & Completion of Eighth RO on 990428 NOC-AE-000557, Requests Relief from ASME Section XI Code Nondestructive Exam Requirements of App III,III-3410 for Second ISI Interval.Proposed Alternatives for Ultrasonic Exam of Piping Sys Welds,Attached1999-07-0606 July 1999 Requests Relief from ASME Section XI Code Nondestructive Exam Requirements of App III,III-3410 for Second ISI Interval.Proposed Alternatives for Ultrasonic Exam of Piping Sys Welds,Attached NOC-AE-000498, Requests Relief from ASME Section XI Code Nondestructive Exam Requirements Applicable to SG Main Steam Nozzle inside- Radius Sections.Attachment Includes Discussion of Basis & Justification for Request & Implementation Schedule1999-07-0606 July 1999 Requests Relief from ASME Section XI Code Nondestructive Exam Requirements Applicable to SG Main Steam Nozzle inside- Radius Sections.Attachment Includes Discussion of Basis & Justification for Request & Implementation Schedule NOC-AE-000573, Requests Relief from Requirements of ASME Section XI Code Case N-498,exempting Isolated Class 1 Reactor Vessel Head Vent Atmospheric Vent Piping & Valve from Being Tested at Full RCS Pressure1999-07-0606 July 1999 Requests Relief from Requirements of ASME Section XI Code Case N-498,exempting Isolated Class 1 Reactor Vessel Head Vent Atmospheric Vent Piping & Valve from Being Tested at Full RCS Pressure NOC-AE-000541, Submits Response to GL 98-01,Suppl 1, Y2K Readiness of Computer Systems at Npps. Readiness Disclosure for STP, Encl1999-06-29029 June 1999 Submits Response to GL 98-01,Suppl 1, Y2K Readiness of Computer Systems at Npps. Readiness Disclosure for STP, Encl NOC-AE-000571, Forwards Final Operating Exam Matls for STP Exam Scheduled for 990705.Revised Operating Exam Outline & post-validation Change Summary Has Been Included.Without Encls1999-06-24024 June 1999 Forwards Final Operating Exam Matls for STP Exam Scheduled for 990705.Revised Operating Exam Outline & post-validation Change Summary Has Been Included.Without Encls NOC-AE-000512, Responds to NRC 981201 Telcon Re Jco 93-0004,per Revised MSLB Analysis1999-06-23023 June 1999 Responds to NRC 981201 Telcon Re Jco 93-0004,per Revised MSLB Analysis NOC-AE-000560, Forwards LER 99-S02-00,re Failure to Maintain Positive Control of Vital Area Security Key.Licensee Commitments Are Found in Corrective Action Section of LER1999-06-23023 June 1999 Forwards LER 99-S02-00,re Failure to Maintain Positive Control of Vital Area Security Key.Licensee Commitments Are Found in Corrective Action Section of LER 05000498/LER-1999-005, Forwards LER 99-005-00,re Failure to Meet Requirements of TS Surveillance 3.7.1.2 Action B for Auxiliary FW Sys.Only Commitments Contained in Ltr Are Located in Corrective Action Section of LER1999-06-17017 June 1999 Forwards LER 99-005-00,re Failure to Meet Requirements of TS Surveillance 3.7.1.2 Action B for Auxiliary FW Sys.Only Commitments Contained in Ltr Are Located in Corrective Action Section of LER NOC-AE-000565, Forwards Amended Pages for Insertion Into South Texas Project Nuclear Operating Co Previously Submitted Response to NRC Rai.New Pages Include Expanded Answer to Question 4.b1999-06-16016 June 1999 Forwards Amended Pages for Insertion Into South Texas Project Nuclear Operating Co Previously Submitted Response to NRC Rai.New Pages Include Expanded Answer to Question 4.b NOC-AE-000548, Forwards Response to RAI Re Proposed Amends on Replacement SG Water Level Trip Setpoint Differences for Stp,Units 1 & 2.Nothing Contained in Response Should Be Considered Commitment Unless So Specified in Separate Correspondence1999-06-16016 June 1999 Forwards Response to RAI Re Proposed Amends on Replacement SG Water Level Trip Setpoint Differences for Stp,Units 1 & 2.Nothing Contained in Response Should Be Considered Commitment Unless So Specified in Separate Correspondence NOC-AE-000561, Forwards Change QA-042 to Operations QAP, Rev 13, Reflecting Current Organizational Alignment for STP & Culminating Organizational Realigment That Has Been Taking Place During Past Several Months1999-06-15015 June 1999 Forwards Change QA-042 to Operations QAP, Rev 13, Reflecting Current Organizational Alignment for STP & Culminating Organizational Realigment That Has Been Taking Place During Past Several Months NOC-AE-0559, Forwards STP Commitment Change Summary Rept for Period 981209-990610.Rept Lists Each Commitment for Which Change Was Made During Reporting Period & Provides Basis for Each Change1999-06-15015 June 1999 Forwards STP Commitment Change Summary Rept for Period 981209-990610.Rept Lists Each Commitment for Which Change Was Made During Reporting Period & Provides Basis for Each Change NOC-AE-000499, Forwards Relief Request RR-ENG-2-3,proposing to Perform Alternative Ultrasonic Examination from Outside Surface of Skirt Attachment Weld as Described in Encl,In Lieu of Surface Examination from Inside Pressurizer Skirt1999-06-0909 June 1999 Forwards Relief Request RR-ENG-2-3,proposing to Perform Alternative Ultrasonic Examination from Outside Surface of Skirt Attachment Weld as Described in Encl,In Lieu of Surface Examination from Inside Pressurizer Skirt NOC-AE-000502, Forwards Relief Request RR-ENG-2-6,proposing That Boroscopic VT-1 Visual Examination Be Allowed as Alternative to Section XI Surface Examination of Pump Casing Welds,Or Portions of Welds within Pits1999-06-0909 June 1999 Forwards Relief Request RR-ENG-2-6,proposing That Boroscopic VT-1 Visual Examination Be Allowed as Alternative to Section XI Surface Examination of Pump Casing Welds,Or Portions of Welds within Pits NOC-AE-000500, Forwards Relief Request RR-ENG-2-4,proposing to Perform Alternative Ultrasonic Examination from Outside & End Surfaces of Reactor Vessel Closure Head Nuts,As Described in Encl in Lieu of Surface Examination of Threaded Region1999-06-0909 June 1999 Forwards Relief Request RR-ENG-2-4,proposing to Perform Alternative Ultrasonic Examination from Outside & End Surfaces of Reactor Vessel Closure Head Nuts,As Described in Encl in Lieu of Surface Examination of Threaded Region NOC-AE-000545, Forwards Response to NRC 990416 RAI Re Util Proposed Amend on Operator Action for Small Break Loca, .Draft EOP Re Small Break Loca,Encl to Aid Discussion of Proposed Amend1999-05-31031 May 1999 Forwards Response to NRC 990416 RAI Re Util Proposed Amend on Operator Action for Small Break Loca, .Draft EOP Re Small Break Loca,Encl to Aid Discussion of Proposed Amend 1999-09-09
[Table view] Category:VENDOR/MANUFACTURER TO NRC
MONTHYEARML20012A3071990-02-26026 February 1990 Requests That WCAP-12067,Rev 1,Suppl 2, Reconciliation of Fatigue Crack Growth Results for South Texas Project Unit 1 Surge Line Be Withheld (Ref 10CFR2.790) ML20245F2321989-04-0303 April 1989 Submits Application for Withholding Proprietary WCAP-12164 from Public Disclosure ML20235G6321989-02-14014 February 1989 Requests That Rev 1 to Suppl 1 to WCAP-12067, Addl Info in Support of Evaluations for Thermal Stratification of Pressurizer Surge Lines of South Texas Projects Units... Be Withheld from Public Disclosure (Ref 10CFR2.790) ML20154S8311988-09-0606 September 1988 Requests That Proprietary WCAP-11963, NRC Update Meeting South Texas Bmi Flux Thimble Wear Be Withheld from Public Disclosure (Ref 10CFR2.790) ML20207D7401988-07-0101 July 1988 Requests Withholding of Encl Proprietary Info from Public Disclosure Per 10CFR2.790.Affidavit Providing Basis for Withholding Subj Info from Public Disclosure Also Encl ML20151F5671988-06-0202 June 1988 Request Withholding of Proprietary WCAP-11862, Houston Lighting & Power/Westinghouse/Nrc Bmi Flux Thimble Meeting 880517, Per 10CFR2.790.Affidavit Encl ML20154J9451988-05-0202 May 1988 Requests That Proprietary Rev 1 to WCAP-11761, South Texas Units 1 & 2 Reactor Vessel Tilt & Waviness Clarification Study, Be Withheld,Per 10CFR2.790(b)(4) ML20147B2851987-12-16016 December 1987 Requests Proprietary WCAP-11701, Responses to NRC Questions Re Fast Response,Narrow Range,Thermowell Mounted Resistance Temp Detector, Be Withheld from Public Disclosure (Ref 10CFR2.790(b)(4)) ML20235F3391987-09-10010 September 1987 Requests That Proprietary WCAP-11555, Technical Bases for Eliminating Rupture of Accumulator Line & Attached RHR Piping from Structural Design Basis for South Texas Project Units 1 & 2, Be Withheld NRC-87-3231, Forwards Nonproprietary WCAP-11508 & Proprietary WCAP-11506, Full-Flow Filter Recovery & Equipment Assessment. Proprietary Rept Withheld (Ref 10CFR2.790).Application for Withholding Rept & Affidavit Encl1987-06-11011 June 1987 Forwards Nonproprietary WCAP-11508 & Proprietary WCAP-11506, Full-Flow Filter Recovery & Equipment Assessment. Proprietary Rept Withheld (Ref 10CFR2.790).Application for Withholding Rept & Affidavit Encl ML20215B0001987-06-11011 June 1987 Requests That WCAP-11506, Full-Flow Filter Recovery & Equipment Assessment Be Withheld (Ref 10CFR2.790) ML20214P2331987-05-26026 May 1987 Requests Proprietary Addl Info in Support of Elimination of Postulated Pipe Ruptures in Accumulator Line of South Texas Power Project Units 1 & 2 (WCAP-11383/11351)... Be Withheld (Ref 10CFR2.790) ML20215K6671987-05-0707 May 1987 Submits Application for Withholding Rev 1 to Proprietary WCAP-11273, Westinghouse Setpoint Methodology for Protection Sys,South Texas Project, (Ref 10CFR2.790). Affidavit Encl ML20214G4891987-05-0707 May 1987 Requests That Proprietary Addl Info in Support of Elimination of Postulated Pipe Rupture in Accumulator Line of South Texas Units 1 & 2, Be Withheld (Ref 10CFR2.790). Figures of Accumulator Loops 1,2 & 3 Encl ST-HL-AE-2123, Requests Withholding Proprietary Addl Info in Support of Elimination of Postulated Pipe Ruptures in Pressurizer Surgeline of South Texas Units 1 & 2, Per 10CFR2.7901987-04-21021 April 1987 Requests Withholding Proprietary Addl Info in Support of Elimination of Postulated Pipe Ruptures in Pressurizer Surgeline of South Texas Units 1 & 2, Per 10CFR2.790 ML20207R8171987-03-10010 March 1987 Requests Withholding of Proprietary WCAP-11351, Technical Bases for Eliminating Accumulator Class 1 Low Pressure Line Rupture as Structural Design Basis for South Texas Project Units 1 & 2, from Public Disclosure (Ref 10CFR2.790) ML20211H0601987-02-0404 February 1987 Requests That Proprietary WCAP-11383, Technical Bases for Eliminating Class 1 Accumulator Line Rupture as Structural Design Basis for South Texas Project Units 1 & 2, Be Withheld (Ref 10CFR2.790(b)(4)) ML20214J7371986-11-12012 November 1986 Requests That Proprietary Responses to NRC Questions on Resistance Temp Detector, Be Withheld from Public Disclosure (Ref 10CFR2.790).Related Correspondence ML20215A4421986-11-10010 November 1986 Submits Application for Withholding Proprietary Test Rept Re Noise,Fault,Surge & Radio Frequency Interference,From Public Disclosure.Encl Affidavit Sets Forth Basis on Which Info May Be Withheld (Ref 10CFR2.790) ML20213D7011986-10-30030 October 1986 Requests Proprietary WCAP-11327, Cumulative Usage Factor Criterion for Break Postulation for South Texas Units 1 & 2, Be Withheld (Ref 10CFR2.790) ML20214A1591986-10-29029 October 1986 Requests Withholding of Proprietary Presentation & Handout Matl Re Leak-Before-Break Calculations for South Texas Project 12-Inch Diameter Accumulator Line, Presented During 861015 Meeting W/Nrc.Affidavit Encl ML20215C0321986-09-25025 September 1986 Requests Proprietary WCAP-11232, Comparison of Treat & Notrump Small Break LOCA Transient Results, Be Withheld,Per 10CFR2.790.Affidavit AW-76-45 & Proprietary Matl Previously Submitted Encl NRC-86-3160, Submits Updated List of Plants Affected by Changes in ECCS Evaluation Model Described in Rev 1 to Addendum 3 to WCAP-9561-P1986-09-0808 September 1986 Submits Updated List of Plants Affected by Changes in ECCS Evaluation Model Described in Rev 1 to Addendum 3 to WCAP-9561-P ML20206S4151986-08-20020 August 1986 Requests Withholding of Proprietary WCAP-11256, Addl Info in Support of Elimination of Postulated Pipe Ruptures in Pressurizer Surge Lines of South Texas Project Units 1 & 2, from Public Disclosure Per 10CFR2.790.W/affidavit ML20212A7161986-07-14014 July 1986 Requests Withholding of Supplemental Info Re Momentary Fuel Assembly Liftoff,Specific Data on Tgx Fuel Assembly Forces, from Public Disclosure Per 10CFR2.790 ML20205M5771986-04-0808 April 1986 Responds to 860311 Part 21 Rept Re Improper Qualification of Stock Matls.Bolting Supplied to Bechtel for South Texas Project Upgraded & Acceptable.Matl Supplied to CP&L for Brunswick Units 1 & 2 Tested & Found Acceptable ML20210B9521986-01-29029 January 1986 Requests Proprietary WCAP-9401-P-A Figure 3-2, Floor Design Response Spectrum at Reactor Vessel Supports Elevation,Sse Be Withheld from Public Disclosure (Ref 10CFR2.790) ML20199B5411986-01-0808 January 1986 Application for Withholding Proprietary Info from Public Disclosure (Ref 10CFR2.790).Affidavit Encl ML20128P9671985-07-15015 July 1985 Requests Withholding Equipment Specs from Public Disclosure (Ref 10CFR2.790) Per Encl Affidavit AW-80-53 NRC-85-3049, Forwards Listed Nonproprietary Documents Requested by NRC During 850517 & 0626 Audits & Application for Withholding Proprietary Info from Public Disclosure Per 10CFR2.7901985-07-15015 July 1985 Forwards Listed Nonproprietary Documents Requested by NRC During 850517 & 0626 Audits & Application for Withholding Proprietary Info from Public Disclosure Per 10CFR2.790 NRC-85-3044, Forwards Proprietary CENC-1302, Analytical Rept for South Texas Project 1,Houston Lighting & Power Co. Withholding from Public Disclosure Requested.Rept Withheld (Ref 10CFR2.790)1985-07-0303 July 1985 Forwards Proprietary CENC-1302, Analytical Rept for South Texas Project 1,Houston Lighting & Power Co. Withholding from Public Disclosure Requested.Rept Withheld (Ref 10CFR2.790) ML20129J7371985-07-0303 July 1985 Requests Proprietary WCAP-10865, South Texas Plant (Tgx) Reactor Internals Flow-Induced Vibration Assessment, Be Withheld (Ref 10CFR2.790) ML20140A4581984-11-21021 November 1984 Requests Withholding of WCAP-10489, Technical Bases for Eliminating Pressurizer Surge Line Ruptures as Structural Design Basis for South Texas Project, from Public Disclosure (Ref 10CFR2.790).Affidavit Encl ML20098C8591984-08-14014 August 1984 Alleges That Unqualified Suppliers Awarded Contracts from Plants to Provide Flexible Conduits Unqualified Under IEEE Stds 323 & 344 Despite IEEE Bid Requirements.Meeting Re NRC Position on safety-related Installations Requested ML20094C3691984-06-0101 June 1984 Requests Withholding of WCAP-10559 & WCAP-10560, Technical Bases for Eliminating Large Primary Loop Pipe Rupture as Structural Design Basis for South Texas Project,Units 1 & 2 (Ref 10CFR2.790) ML20151Q5611984-03-14014 March 1984 Advises That Dropped Rod Test Will Be Recommended for Inclusion on New Reactor Core Designs Where Worth of Rods Significantly Different from Current Values,Per WCAP-10297 & WCAP-10298 Repts on Dropped Rod Methodology ML20106D4751984-02-0909 February 1984 Requests Proprietary 17x17 Xl Hydraulic Flow Testing,Results in Response to NRC Question 231.8,be Withheld (Ref 10CFR2.790).Affidavit AW-78-23 & Nonproprietary 17x17 Xl Hydraulic Flow Testing Results Encl ST-HL-AE-2695, Informs That More Definitive Test of Negative Flux Rate Trip Performed on Both Four & Three Loop Plants W/Rod Worths Significantly Less than Max Worth Noted in WCAP-10298, Resulting in Indication of No Reactor Trip1983-11-16016 November 1983 Informs That More Definitive Test of Negative Flux Rate Trip Performed on Both Four & Three Loop Plants W/Rod Worths Significantly Less than Max Worth Noted in WCAP-10298, Resulting in Indication of No Reactor Trip ML20212A7331978-03-21021 March 1978 Requests Withholding of Slides Used in Westinghouse 780321 Optimized Fuel Assembly Presentation to NRC from Public Disclosure Per 10CFR2.790 ML20210C8771975-08-19019 August 1975 Requests Meeting to Resolve Position Re Tests to Demonstrate Design Adequacy of Wiring Separation within Instrumentation & Control Protection Racks,Per 840807 Meeting ML20210C8501975-07-0707 July 1975 Forwards Westinghouse Protection Sys Noise Tests, Dtd Dec 1974,in Support of Application for Ol.Related Info Encl.W/O Rept 1990-02-26
[Table view] |
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ATTACHMENT G ST-HL AE /68]
PAGE / OF 7 Westinfiouse Water Reactor Ba m Pmsbtrgh Pennsytvania 15230-0355 Electric Corporation Divisions January 8, 1986 CAW-86-004 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20055 APPLICATION FOR WITHHOLDING PROPRIETARY INFORMATION FROM PUBLIC DISCLOSURE
Reference:
Houston Lighting & Power Company Letter to NRC dated January 1986
Dear Mr. Denton:
The proprietary material for which withholding is being requested in the reference letter by Houston Lighting & Power Company is further identified in an af fidavit signed by the owner of the proprietary information, Westinghouse
- Electric Corporation. The affidavit, which accompanies this letter, sets forth the basis on which the information may be withheld from public disclosure by the Commission and addresses with specificity the considerations listed in paragraph (b) (4) of 10CFR Section 2.790 of the Commission's regulations.
The proprietary material for which withholding is being requested is of the same technical type as that proprietary material previously submitted with application for withholding CAW-84-102.
Accordingly, this letter authorizes the utilization of the accompanying af fidavit by Houston Lighting & Power Company.
Correspondence with respect to the proprietary aspects of the application for withholding or the Westinghouse affidavit should reference this letter, CAW-86-004, and should be addressed to the undersigned.
Very truly yours, 8606170169 860610 PDR ADOCK 05000498 PDR M
A p hW p ob rt A. Wiesemann, Manager u ulatory & Legislative Affairs HFC/wh/1212n Enclosure cc: E. C. Shomaker, Esq.
Of fice of the Executive Legal Director, NRC
ATTACHMENT C-ST-H L. AE./ 6g/
PAGE c2_ OFr1 CAW-84-102 AFFIDAVIT COMMONWEALTH OF PENNSYLVANIA:
ss COUNTY OF ALLEGHENY:
Before me, the undersigned authority, personally appeared John D. McAdoo,,
who, being by me duly sworn according to law, deposes and says that he is authorized to execute this Affidavit on behalf of Westinghouse Electric Corporation (" Westinghouse") and that the averments of fact set forth in this Affidavit are true and correct to the best of his knowledge, information, and belief:
A w& ' ::
Joh D. McAdoo, Assistant Manager clear Safety Department Sworn to and subscribed before me this A L_ day
....e.f W h .1984.
/
!aio
..h D'\I _
ii 0F I t . e, Mr! !
&.hlOp Notary Public E0asAlbt M. PIPLICA. NOTARY PUBLIC N04R0tYlLLt BORD. ALLECH!hY COUNTY NY COMuisst04 [xPitts Dtc 14.1987 Nember. Pennsylvania Association of botaries HFC/0162n/11-20-84 k
. . ATTACHMENT (L ST HL-AE /681
_ PAGE S OF r2 CAW-84-102 (1) I am Assistant Manager, Nuclear Safety Department, in the Nuclear Technology Division, of Westinghouse Electric Corporation and as such, I have been specifically delegated the function of reviewing the proprietary information sought to be withheld from public disclosure in connection with nuclear power plant licensing or rulemaking proceedings, and am authorized to apply for its withholding on behalf of the Westinghouse Water Reactor Divisions.
(2) I am neking this Affidavit in conformance with the provisions of 10CFR Section 2.790 of the Commission's regulations and in conjunction with the Westinghouse application for withholding accompany this Affidavit.
(3) I have personal knowledge of the criteria and procedures utilized by Westinghouse Nuclear Energy Systems in designating information as a trade secret, privileged or as confidential commercial or financial information.
(4) Pursuant to the provisions of paragraph (b)(4) of Section 2.790 of the Commission's regulations, the following is furnished for consideration by the Commission in determining whether the information sought to be withheld from public disclosure should be withheld.
(i) The information sought to be withheld from public disclosure is
. owned and has been held in confidence by Westinghouse.
(ii) The information is of a type customarily held in confidence by Westinghouse and not customarily disclosed to the public.
Westinghouse has a rational basis for determining the types of j
information customarily held in confidence by it and, in that connection, utilizes a system to determine when and whether to hold certain types of information in confidence. ,
The application of that system and the substance of that system constitutes Westinghouse policy and provides the rational basis required.
HFC/0162n/11-20-84 7 . _ _ .
1 ATTACHMENT C .
ST-HL AE-/MI I
PAGE # OF 7 CAW-84-102 I
Under that system, information is held in confidence if it falls in i one or more of several types, the release of which might result in the loss of an existing or potential competitive advantage, as follows: l l
(a) The information reveals the distinguishing aspects of a process (or component, structure, tool, method, etc.) where prevention of its use by any of Westinghouse's competitors without license from Westinghouse constitutes a competitive economic advantage over other companies.
(b) It consists of supporting data, including test data, relative to process (or component, structure, tool, method, etc.), the application of which data secures a competitive economic advantage, e.g., by optimization or improved marketability.
(c) Its use by a competitor would reduce his expenditure of resources or improve his competitive position in the design, manufacture, shipment, installation, assurance of quality, or licensing a similar product.
It reveals cost or price information, production capacities, (d) budget levels, or commercial strategies c' Westinghouse, its
, customers or suppliers.
(e) It reveals aspects of past, present, or future Westinghouse or customer funded development plans and programs of potential commercial value to Westinghouse.
(f) It contains patentable ideas, for which patent protection may be desirable. -
(g) It is not the property of Westinghouse, but must be treated as proprietary by Westinghouse according to agreements with the owner.
HFC/0162n/11-20-84 l
- ATTACHMENT C, ST.HL AE- 16f/
PAGE $ OF 7 7Aw-s4-loz There are sound policy reasons behind the Westinghouse system which include the following:
(a) The use of such information by Westinghouse gives Westinghouse a competitive advantage over its competitors.
It is, therefore, withheld from disclosure to protect the Westinghouse competitive position.
(b) It is information which is marketable in many ways. The extent to which such inforwation is available to competitors diminishes the Westinghouse ability to sell products and services involving the use of the information.
(c) Use by our competitor would put Westinghouse at a competitive disadvantage by reducing his expenditure of resources at our expense.
(d) Each component of proprietary information pertinent to a particular competitive advantage is potentially as valuable as the total competitive advantage. If competitors acquire components of proprietary information, any one component may be the key to the entire puzzle, thereby depriving Westinghouse of a competitive advantage.
(e) Unrestricted disclosure would jeopardize the position of prominence of Westinghouse in the world market, and thereby give a market advantage to the competition in those countries.
l (f) The Westinghouse capacity to invest corporate assets in l research and development depends upon the success in obtaining and maintaining a competitive advantage.
(iii) The information is being transmitted to the Commission in confidence and, under the provisions of 10CFR Section 2.790, it is to be received in confidence by the Commission.
HFC/0162n/ll-20-84 1
I
, _ - . ~ . _ - _ _ _ - - - . - - _ - -
u- _ aAe _
ATTACHMENT CS ST HL AE- /6t/ )
PAGE 6 OF '7 j t
o 5- CAW-84-102 (iv) The information sought to be protected is not available in public sources to the best of our knowledge and belief.
l (v) The proprietary information sought to be withheld in this submittal is that which is appropriately marked in WCAP-10489,
" Technical Bases for Eliminating Pressurizer Surge line Ruptures as the Structural Design Bases for South Texas Project," dated February 1984, and " Additional Information - South Texas Surge Line."
The subject information could only be duplicated by competitors if they were to invest time and effort equivalent to that invested by Westinghouse provided that they have the requisite talent and experience.
Public disclosure of this information is likely to cause substantial harm to the competitive position of Westinghouse because it would simplify design and evaluation tasks without requiring a commensurate investment of time and effort.
Further the deponent sayeth not.
l t
l HFC/0162n/ll-20-84
1 ATTACHMENT C ST-HL AE-/6 #/#
PAGE ef 0F 7
, PROPRIETARY INFORMATION NOTICE ,
( .
TRANS)CTTED HDEWITH ARE PROPRIETARY AND/0R NON-PROPRIETARY YERSIONS O DOCUMENIS RfRNISHG TO THE NRC IN CONNECTION WITH REQUESTS FOR CE PLAhT SPECIFIC REVIEW AND APPROVAL.
l t---
IN ORDER TO C0hTORM 70 THE REQUIRIMEhTS 710CFR2.790 W THE 0'HMISSION REGULATIONS CONCERNING THE PROTECTION W PROPRIETARY INFORMATION S 70 THE NRC, THE INFORPATION WHICH IS PROPRIETARY IN THE PROPRIETARY VERSIONS IS CONTAING WITHIN BRACKETS AND WHDE THE PROPRIETARY INFORMATION HAS B
. DEI.ETD IN THE NON-PROPRIETARY VDSIONS GC.Y THE BRACKETS RDRIN, THE -
IhTORPATION THAT WAS CONTAINED WITHIN THE BRACKEIS IN THE PROPRIET HAVING BEDI DI2.ETE. THE JUSTIFICATION FOR Q. AIMING THE INFORMATION SO
( DESIGNATED AS PROPRIETARY IS INDICATE IN BOIH VDSIONS BY MEANS W LO LETTDS (a) THROUGH (g) CohTAING WIININ PAREhTi!SES LOCATED AS A SUPERSCRIFT IMMEDIATII.Y FOLLOWING THE BRACKETS EQ.05ING EACH ITIN OF INFORMATION IDENTIFIED AS PROPRIETARY OR IN 1HE MARGIN OPPOSITE SU01 INFORMATIO LOWD CASE LETTERS REFER TO THE TYPES W INFORMATION WDTINGHOUSE CU HOLTS IN CONFIDENCE IDEhTIFIED IN SECTIONS (4)(ii)(a) through (4)(ii)(g) 0F THE AF7IDAVIT ACCOMPAhTING THIS TRANSMITTAL PURSUAhT TO 10CFR2 790(b)(1 Em
Attachment C t ST-HL- AE -1681 PFN: G9.10 SOUTH TEXAS PROJECT LEAK-BEFORE-BREAK SCREENING CRITERIA FOR HIGH ENERGY AUXILIARY PIPING SYSTEMS This attachment presents the screening criteria for the application of leak-before-break to high energy piping systems in South Texas Project.
-The purpose of this effort is to apply the state-of-the-art technology in leak-before-break through a screening process developed to minimize the downstream effort and to obtain an insight in ascertaining the possibility of successful demonstration of leak-before-break. Successfully passing the screening criteria establishes technical justification to eliminate the dynamic effects of postulated breaks. The screening criteria are provided in the following enclosures:
Enclosure 1: WCAP #11043 - South Texas Project Leak-Before-Break Screening Criteria for High Energy Auxiliary Piping Systems (Proprietary Class 2)
Enclosure 2: WCAP #11044 - South Texas Project Leak-Before-Break Screening Criteria for High Energy Auxiliary Piping Systems (Proprietary Class 3) i l
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- z Nj i ATTACHMENT (3 i ST-HL-AE- /68f PAGE / OF 7 Water Reactor Nx 355 Westinghouse Pmsburgh Pennsylvania 15230-0355 88CtflC C0fp0fatl0n Divisions January 8, 1986 CAW-86-004 9
Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20055 APPLICATION FOR WITHHOLDING PROPRIETARY INFORMATION FROM PUBLIC DISCLOSURE
Reference:
Houston Lighting & Power Company Letter to NRC dated January 1986
Dear Mr. Denton:
The proprietary material for which withholding is being requested in the reference letter by Houston Lighting & Power Company is further identified in an affidavit signed by the owner of the proprietary information, Westinghouse Electric Corporation. The affidavit, which accompanies this letter, sets forth the basis on which the information may be withheld from public disclosure by the Commission and addresses with specificity the considerations listed in paragraph (b) (4) of 10CFR Section 2.790 of the Commission's regulations.
The proprietary material for which withholding is being requested is of the same technical type as that proprietary material previously submitted with application for withholding CAW-84-102.
Accordingly, this letter authorizes the utilization of the accompanying affidavit by Houston Lighting & Power Company.
Correspondence with respect to the proprietary aspects of the application for withholding or the Westinghouse affidavit should reference this letter, CAW-86-004, and should be addressed to the undersigned.
Very truly yours, M
60 h w ob rt A. Wiesemann, Manager p
u ulatory & Legislative Affairs
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HFC/wh/1212n Enclosure cc: E. C. Shomaker, Esq.
Office of the Executive Legal Director, NRC
ATTACHMENT CL ST HL AE /6g/
PAGE d2. OF#7 CAW-84-102 s
AFFIDAVIT CONNONWEALTH OF PENNSYLVANIA:
ss COUNTY OF ALLE6HENY:
8efore me, the undersigned authority, personally appeared John D. McAdoo,,
who, being by me duly sworn according to law, deposes and says that he is authorized to execute this Affidavit on behalf of Westinghouse Electric Corporation (" Westinghouse") and that the aver 1nents of fact set forth in this Affidavit are true and correct to the best of his knowledge, information, and belief:
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Joh D. McAdoo, Assistant Manager clear Safety Department Sworn to and subscribed before me this d day
, ....p..f.... h .1984.
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N. l' h Notary Public LottAtht at PirlicA. NOTARY PUBlic WO440tVILLE BORQ. AlltCH!NY COUMIT NY COMul35104 EXPIRIS Ctc 14. lH7 Gember. Pennsylvania Association of hotaries i
l NFC/0162n/11-20-84 L
I ATTACHMENT C
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. ST-HL AE /681 PAGE S OFr1 CAW-84-102 (1) I am Assistant Manager, Nuclear Safety Department, in the Nuclear Technology Division, of Westinghouse Electric Corporation and as such, I have been specifically delegated the function of reviewing the proprietary inforwation sought to be withheld from public disclosure in connection with nuclear power plant licensing or rulemaking proceedings, and am authorized to apply for its withholding on behalf of the Westinghouse Water Reactor Divisions.
(2) I am making this Affidavit in conformance with the provisions of 10CFR Section 2.790 of the Commission's regulations and in conjunction with the Westinghouse application for withholding accompany this Affidavit.
(3) I have personal knowledge of the criteria and procedures utilized by Westinghouse Nuclear Energy Systems in designating information as a trade secret, privileged or as confidential commercial or financial information.
j (4) Pursuant to the provisions of paragraph (b)(4) of Section 2.790 of the Commission's regulations, the following is furnished for consideration by the Commission in determining whether the information sought to be withheld from public disclosure should be withheld.
l (i) The information sought to be withheld from public disclosure is owned and has been held in confidence by Westinghouse.
(ii) The information is of a type customarily held in confidence by Westinghouse and not customarily disclosed to the public.
Westinghouse has a rational basis for determining the types of information customarily held in confidence by it and, in that connection, utilizes a system to determine when and whether to hold certain types of information in confidence. .
The application of that system and the substance of that system constitutes Westinghouse policy and provides the rational basis required.
HFC/0162n/ll-20-84
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- ATTACHMENT C ST-HL AE-/6al PAGE # OF 7
'. CAW-84-102 Under that system, information is held in confidence if it falls in one or more of several types, the release of which might result in the loss of an existing or potential competitive advantage, as follows:
(a) The information reveals the distinguishing aspects of a process (or component, structure, tool, method, etc.) where prevention of its use by any of Westinghouse's competitors without license from Westinghouse constitutes a competitive economic advantage over i other companies.
(b) It consists of supporting data, including test data, relative to process (or component, structure, tool, method, etc.), the application of which data secures a competitive economic advantage, e.g., by optimization or improved marketability.
(c) Its use by a competitor would reduce his expenditure of resources or improve his competitive position in the design, manufacture,
! shipment, installation, assurance of quality, or licensing a similar product.
(d) It reveals cost or price information, production capacities, budget levels, or commercial strategies of Westinghouse, its customers or suppliers.
(e) It reveals aspects of past, present, or future Westinghouse or
, customer funded development plans and programs of potential I commercial value to Westinghouse.
(f) It contains patentable ideas, for which patent protection may be desirable.
(g) It is not the property of Westinghouse, but must be treated as proprietary by Westinghouse according to agreements with the owner.
MFC/0162n/11-20-84 t
ATTACHMENT C, i ST-HL AE- /681 t PAGE 5 OF 7 ;
CAW-84-lD2 s
There are sound policy reasons behind the Westinghouse system which include the following:
(a) The use of such information by Westinghouse gives Westinghouse a competitive advantage over its competitors.
It is, therefore, withheld from disclosure to protect the Westinghouse competitive position.
(b) It is information which is marketable in many ways. The extent to which such information is available to competitors diminishes the Westinghouse ability to sell products and services involving the use of the information.
(c) Use by our competitor would put Westinghouse at a competitive disadvantage by reducing his expenditure of resources at our expense.
(d) Each component of proprietary information pertinent to a particular competitive advantage is potentially as valuable i
as the total competitive advantage. If competitors acquire components of proprietary information, any one component may be the key to the entire puzzle, thereby depriving Westinghouse of a competitive advantage.
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l (e) Unrestricted disclosure would jeopardize the position of prominence of Westinghouse in the world market, and thereby give a market advantage to the competition in those countries.
(f) The Westinghouse capacity to invest corporate assets in research and development depends upon the success in i
obtaining and maintaining a competitive advantage.
l (iii) The information is being transmitted to the Commission in confidence and, under the provisions of 10CFR Section 2.790, it is to be received in confidence by the Commission.
4 HFC/0162n/11-20-84
1 ATTACHMENT CS ST HL AE- /6t/
PAGE 6 OF /7 CAW-84-102
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(iv) The information sought to be protected is not available in public sources to the best of our knowledge and belief.
(v) The proprietary information sought to be withheld in this submittal is that which is appropriately marked in WCAP-10489,
" Technical Bases for Eliminating Pressurizer Surge line Ruptures l as the Structural Design Bases for South Texas Project," dated February 1984, and " Additional Information - South Texas Surge Line."
The subject information could only be duplicated by competitors if they were to invest time and effort equivalent to that invested by Westinghouse provided that they have the requisite talent and experience.
! Public disclosure of this information is likely to cause substantial harm to the competitive position of Westinghouse -
because it would simplify design and evaluation tasks without requiring a commensurate investment of time and effort.
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[ Further the deponent sayeth not.
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HFC/0162n/11-20-84
ATTACHMENT C,
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ST-HL-AE PAGEef OF /6 8'/
i PROPRIETARY INFORMATION NOTICE .
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TRANSMITTED HDEWITH ARE PROPRIETARY AND/OR NON-PROPRIETARY VDSIONS OF DOCUMENTS FURNISHD 70 THE NRC IN CONNECTION WITH REQUDTS FDR CEERIC AC/OR PLAhT SPECIFIC REVIEW AND APPROVAL.
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IN OF. DER 10 C0hTORM TD THE RDUIREMENTS OF 10CFR2.790 0F THE C0HKISSION'S REGULATIONS CONCERNING THE PROTECTION & PROPRIETARY INFVRMATION SO SUBMITTE
_ TD THE NRC, THE INFORFATION WHICH IS PROPRIETARY IN 1HE PROPRIETARY VERSIONS IS CONTAING WITHIN BRACKETS AND WHERE THE PROPRIETARY INFORMATION HAS BEDi
, DELETD IN THE NON-PROPRIETARY VERSIONS DC.Y THE BRACKETS REMAIN, THE IhTORFATION THAT WAS CONTAINED WITHIN THE BRACKEIS IN 1HE PROPRIETARY VERSIO HAVIN3 BED DII.ETD. THE JUSTIFICATION FDR (1. AIMING THE INFORMATION 30 t
( DESIGNATED AS PROPRIETARY IS INDICATED IN BOTH VERSIONS BY MEANS W LOWS CASE LETTDS (a) THROUGH (g) CohTAINED WITHIN PARDiTHESES LOCATED AS A SJPERSCRIPT IMMEDIATE.Y FDLLOWIN3 THE BRACKETS ECI.05ING EACH ITEM OF INFORMATION BEIN3 IDENTIFIED AS PROPRIETARY OR IN THE MARGIN OPPOSITE SJCH INFORMATION. THESE LQiB CASE LEITERS REFIR 1V THE TYPES OF INFORMATION WESTINGHOUSE QJS1DMAR l HC'.DS IN CONFIDENCE DEh71FIED IN SECTIONS (4)(ii)(a) through (4)(ii)(g) 0F THE
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AFFIDAVIT ACCOMPAhTING THIS TRANSMITTAL PURSUAhT 7010CFR2.790(b)(1).
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Attachment D ST-HL-AE- 1681 PFN: G9.10 Page 1 of'2 PROVISIONS FOR MINIMIZING STRESS CORROSION CRACKING IN HIGH ENERGY LINES Industry experience (NUREG 0691) has shown that there is a strong potential for stress corrosion cracking (SCC) if the following three conditions exist simultaneously: (1) high tensile stresses, (2) susceptible piping material, and (3) a corrosive environment. Althcogh any stainless or carbon steel piping will exhibit some degree of resioci mie:;es and material susceptibil-ity, Houston Lighting 4 P)wer Company minimizes the potential for SCC by choosing piping materia' with low susceptibility to stress corrosion and by preventing the existence of a corrosive environment. The material specifica-tions consider compatib 'ity with the system's operating environment (both internal and external), otner materials present in the system, applicable ASME code requirements, fracture toughness characteristics, welding procedures, and pipe fabrication techniques.
The likelihood of stress corrosion cracking in stainless steel increases with carbon content. Consequently, only the lower carbon content stainless steels (304, 304L, 316, 316L) are used in high energy systems in contact with the reactor coolant.1 The existence of a corrosive environment is prevented by strict criteria for internal and external pipe cleaning, and water chemistry control during preoperation testing and normal plant operation. The mainte-nance of extremely low residual oxygen concentrations (less than 0.005 ppm) within the RCS and systems in direct contact with the RCS during normal operation, precludes the occurrence of pipe cracking which has been identified at some facilities.
For most secondary systems, ferritic type carbon steel 2 is used for piping, fittings, and valve bodies forming the pressure boundaries. Significant portions of the Steam Generator Blowdown System (SGBDS) (steam generator to flash tank) use ferritic alloy steel. This ferritic material has been found satisfactory from the standpoint of non-susceptibility to stress corrosion cracking for the service conditions encountered.
High energy piping systems are cleaned externally and flushed as part of the preoperational test program. The piping is flushed with demineralized water subject to limits on total dissolved solids, conductivity, chlorides, j flourides, and pH. Flush water quality is monitored daily. The flushing is controlled in accordance with procedures. Water chemistry for preoperational testing is controlled by written specifications.
I Stainless Steel Material as listed in Attachment A, Table 1.
2 Carbon Steel Material as listed in Attachment A, Table 1.
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7-Attachment <D ST-HL-AE- 1681 PFN: G9.10 Page 2 of 2 During plant operation, primary and secondary side water chemistry are moni-tored, contaminant concentrations are maintained below the thresholds known to be conducive to stress corrosion cracking. The water chemistry control standards are included in operating procedures for those systems where breaks are being eliminated.
Attachment A identifies the systems where breaks are being eliminated.
Portions -of these systems operate at temperatures below 200 F. Industry experience shows that stress corrosion is not a significant concern at temper-atures this low. The water chemistry requirements for primary systems are presented in FSAR section 5.2.3. Secondary system water chemistry control is discussed in FSAR section 10.3.5.
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Attachment E ST-HL- AE- 1681 PFN: G9.10 Page 1 of 1 PROVISIONS FOR MINIMIZING THE EFFECTS OF THERMAL AND VIBRATION INDUCED PIPING FATIGUE I. GENERAL FATIGUE DESIGN CONSIDERATIONS Fatigue considerations are addressed in STP Class 1 piping by the use of a cumulative usage factor (CUF). In order to ensure that piping does not fail due to fatigue, the ASME Code limits the CUF to a maximum of 1.0.
Each Class 1 p.iping system will be reviewed to minimize the number of high stress-intermediate breaks. In accordance with the December, 1985, draft revision of ANSI /ANS 58.2 standards, the CUF threshold for high stress intermediate break locations will be taken as 0.4 in lieu of the 0.1 value noted in section 3.6.2 of the July 1982 Standard Review Plan.
II. THERMAL DESIGN CONSIDERATIONS The STP steam generators have separate nozzles for auxiliary feedwater-(upper nozzle) and main -feedwater (lower nozzle). Thermal fatigue is minimized in the main feedwater piping by preventing the introduction of ,
cold water. The main feedwater lines ,.inside ,the RCB are used only when feedwaterg temperatures downstream of the containment isolation valves are above 250 F. This is assured by permissives on the feedwater isolation valves which prevent their opening until the dognstream feedwater temper-atures measured at two locations g are above 250 F. Feedwater temperature is maintained above 250 F by heating in the deaerator with , extraction, main, or auxiliary steam. During shutdown; startup,and hot standby water is provided to the upper steam generator nozzle. The upper nozzle to the steam generator uses a thermal sleeve to minimize pipe stress resulting from thermal considerations.
The heat affected zone adjacent to the muih feedwater nozzles is the region which has experienced pipe cracks inlPWRs. The fracture mechanics analysis for this piping will be completed to ensure that Leak-Before-Break criteria will be met.
III. YIHRATION DESIGN CONSIDERATIONS -
i f l Piping is designed and supported to minimize transient and steady state vibration. Piping system vibration testing will be performed as de-scribed in FSAR Section 3.9.2 to ensure that piping system vibration'is within allowable levels.
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I Attachment F
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ST-HL- AE-1681 PFN: G9.10 Page 1 of 2 PROVISIONS FOR MINIMIZING STEAM / WATER HAMMER EFFECTS The reactor coolant, safety injection, chemical and volume control, and residual heat removal systems have been designed to preclude water hammer.
Westinghouse has conducted a number of investigations . into the causes and consequences of water hammer events. The results of these investigations have been reflected in STP design interface requirements to assure that water hammer events initiated in the 80P secondary systems do not compromise the performance of the Westinghouse supplied safety-related systems and compo-nents.
The lines in which postulated pipe ruptures are being eliminated and which have the potential for water / steam hammer effects are being designed to minimize or preclude such effects. Water hammer protection in each of these systems is described below:
- 1. Safety In.iection System The safety injection lines are all water solid at ambient temperature; thus, no water hammer is expected.
- 2. Chemical and Volume Control System (CVCS)
Normallyothe CVCS is water solid. In the low temperature lines (less than 125 F), water hammer would not be expected because of the small probability of steam void formation. In the high temperature lines, the piping has been designed to maintain water solid conditions during normal operation, thus minimizing the possibility of water hammer effects.
- 3. Reactor Coolant System Water hammer is not expected to be a concern in the reactor coolant system because it is designed to preclude steam void formation.
l 4. Residual Heat Removal (RHR) System The RHR system lines are all water solid; thus, no water hammer is expected.
- 5. Auxiliary Feedwater System A separate auxiliary feedwater line and nozzle has been provided to each steam generator to minimize the potential for water hammer. This is in l addition to the following design measures. The auxiliary feedwater
! discharge pipe inside the steam generator is arranged to prevent water draining from the pipe following a drop in steam generator water level.
! Piping volume connected to the steam generator nozzle which could form a l steam void is minimized by minimizing the length of horizontal inlet j piping. Specific design features to reduce the potential for condensation-induced water hammer were discussed in Attachments 3 and 4 of ST-HL-AE-1202 dated March 8, 1985 (see Note 1).
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l Attachment F ST-HL-AE- 1681 PFN: G9.10 Page 2 of 2
- 6. Steam Generator Blowdown System Blowdown flow from the steam generators is normally two-phase and of 0-7 percent quality. The normal flow regime between the steam generator and the blowdown control valve is slug flow. This section of pipe is run in horizontal and descending vertical legs to the piping low point drain located at the blowdown control valve. The normal flow regime downstream of the blowdown control valve to the flash tank lies in the dispersed flow regime. Operating procedures calling for gradually increasing flow into the normal operating range minimize the potential for water hammer downstream of the blowdown control valve which establishing flow during startup.
- 7. Main Steam System The main steam piping from the 5 way restraints just outside containment to the main turbine has a minimum slope of 6 inches per 100 feet of piping. Twenty-four-inch diameter drip legs are installed upstream of the main turbine inlet on the 24-inch and 30-inch main steam lines to collect and dispense drainage to the condenser. The branch lines that tee off the main steam lines are sloped and contain low point drains to eliminate the possibility of water hammer due to condensate water pockets collecting in low points.
- 8. Main Feedwater System Westinghouse has conducted extensive investigations into potential sources of water hammer in preheat steam generators as used on STP.
Initiation of main feedwater is controlled by procedure and system interlocks to minimize the potential for water hammer in the main feedwater system.
The routing of the main feedwater piping is in compliance with the Westinghouse criteria for layout, temperature monitoring / alarm, and operational procedures to minimize or eliminate water hammer. Although Westinghouse plants with preheat steam generators have never experienced a bubble collapse type water hammer event in the main feedwater system, the steam generators and feedwater piping are designed for these water hammer events. Specific design and operational features to reduce potential for water hammer are discussed in Attachments 1, 2 and 4 of ST-HL-AE-1202 dated March 8, 1985 (see Note 1).
! Note 1 i
The NRC acceptable evaluation of this justification for elimination of arbitrary intermediate breaks is provided in Appendix G to NUREG-0781 which is
, the Safety Evaluation Report related to operation of South Texas Project Units 1 and 2.
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