Similar Documents at Ginna |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML17250B3041999-10-20020 October 1999 Forwards Changes to Tech Specs Bases for Re Ginna Nuclear Power Plant.Change Bars Indicate Those Revs Which Have Been Incorporated IR 05000244/19990081999-10-14014 October 1999 Forwards Insp Rept 50-244/99-08 on 990809-0919.Severity Level IV Violation of NRC Requirements Occurred & Being Treated as non-cited Violation Consistent with App C of Enforcement Policy ML17265A7651999-10-0808 October 1999 Forwards Fifteen Relief Requests That Will Be Utilized for Ginna NPP Fourth Interval ISI Program That Will Start on Jan 1,2000.Attachment 1 Includes Summaries & Detailed Description of Each Relief Request ML17265A7631999-10-0505 October 1999 Requests Approval for Use of Relief Request Number 43 to Address Volumetric Examination Limitations (Less than 90%) Associated with a & B RHR Heat Exchanger Outlet Nozzle to Shell Welds.Approval Is Requested by Dec 31,2000 ML17265A7641999-10-0505 October 1999 Requests Approval for Use of Relief Request Number 42 to Address Volumetric Examinations Limitations (Less than 90%) Associated with Eight Class 1 Identified Welds or Areas of Reactor Pressure Vessel ML20212J3561999-09-30030 September 1999 Forwards Four Copies of Re Ginna NPP Training & Qualification Plan for Security Officers, Rev 7,dtd 990930. Synopsis of Changes,Encl.Encl Withheld Per 10CFR73.21 ML20212J3801999-09-30030 September 1999 Forwards Four Copies of Rev to Re Ginna NPP Security Plan.Rev Changes Contingency Weapons Available to Response Force to Those Most Effective in Current Defensive Strategy.Encl Withheld Per 10CFR73.21 IR 05000244/19990051999-09-24024 September 1999 Forwards More Detailed Response Re Main Steam Check Valve Performance Questions Arising from NRC Insp Rept 50-244/99-05 Following Completion of Independent Assessment Being Performed by Duke Engineering & Svcs ML17265A7571999-09-24024 September 1999 Forwards More Detailed Response Re Main Steam Check Valve Performance Questions Arising from NRC Insp Rept 50-244/99-05 Following Completion of Independent Assessment Being Performed by Duke Engineering & Svcs IR 05000244/19992011999-09-24024 September 1999 Forwards Insp Rept 50-244/99-201 (Operational Safeguards Response Evaluation) on 990621-24.No Violations Noted. Primary Purpose of Osre to Assess Licensee Ability to Respond to External Threat.Insp Rept Withheld ML17265A7461999-08-31031 August 1999 Submits Response to NRC Administrative Ltr 95-03,rev 2, Availability of Reactor Vessel Integrity Database,Version, Dtd 990726 ML17265A7401999-08-26026 August 1999 Requests Approval for Use of Relief Request Number 35 Re Use of ASME Section XI Code,1995 Edition,1996 Addenda.Code Will Be Used to Develop Plant Fourth 10-year Interval ISI Program on Class 1,2 & 3 Components ML17265A7411999-08-26026 August 1999 Forwards LER 99-004-01 Re Plant Being Outside Design Basis Due to Containment Recirculation Fan Moisture Separator Vanes Being Incorrectly Installed.Part 21 Notification of 990512 Is Being Rescinded ML17265A7451999-08-23023 August 1999 Forwards fitness-for-duty Performance Data Rept for Six Months Ending 990630,per 10CFR26.71(d) ML17250B3021999-08-23023 August 1999 Informs That Util & NRC Had Conference Call on 990816 to Review Approach in Responding to Questions,As Result of Questions Re Main Steam Check Valve Performance Included in Insp Rept 50-244/99-05,dtd 990806 ML17265A7271999-07-30030 July 1999 Forwards 10CFR21 Interim Rept Per Reporting of Defects & Noncompliance,Section 21 (a) (2).Interim Rept Prepared Because Evaluation Cannot Be Completed within 60 Days from Discovery of Deviation or Failure to Comply ML17265A7151999-07-23023 July 1999 Forwards LER 99-007-01 Re Personnel Error Which Caused Two Channels to Be in Tripped Condition,Resulting in Reactor Trip.Further Investigation of Event Identified Addl Corrective Actions ML17265A7061999-07-22022 July 1999 Forwards LER 98-003-02,re Actuations of CR Emergency Air Treatment Sys.All Creats Actuations,Including Those Originally Believed to Be Valid Actuations,Were,In Fact Invalid Actuations ML17265A7191999-07-21021 July 1999 Forwards Ginna Station ISI Rept for Refueling Outage Conducted in 1999 ML17265A7141999-07-21021 July 1999 Withdraws Relief Request 35 for Plant Inservice Insp Program Section XI Requirements,Submitted on 980806.Licensee Plans to Resubmit Relief Request,Which Includes Addl Level of Detail,In Near Future ML17265A7041999-07-16016 July 1999 Submits Info Re Specific Licensing Actions Which May Be Expected to Generate Complex Reviews,In Response to Administrative Ltr 99-02,dtd 990603 ML17265A6911999-06-30030 June 1999 Responds to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants.Gl 98-01 Requested Response on Status of Facility Y2K Readiness by 990701.Readiness Disclosure Attached ML17265A6871999-06-22022 June 1999 Forwards Response to RAI Made During 990225 Telcon Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves. Calculation Encl. Encl ML17265A6841999-06-21021 June 1999 Informs That Util Wishes to Amend Extend of Alternate Exams Provided for Relief Request Re ISI Program ASME Section XI Require Exams for First 10-Yr Interval for Containment ML17265A6741999-06-15015 June 1999 Submits Annual ECCS Rept IAW 10CFR50.46(a)(3)(ii) Requirements.No Changes Have Been Made to Large Break LOCA PCT & Small Break LOCA PCT ML17265A6751999-06-11011 June 1999 Responds to NRC RAI Re Licensee GL 96-05 Program.Encl Info Verifies That Util Is Implementing Provisions of JOG Program on MOV Periodic Verification ML17309A6551999-06-0707 June 1999 Responds to NRC 990310 RAI Re Verification of Seismic Adequacy of Mechanical & Electrical Equipment ML17265A6671999-06-0101 June 1999 Requests Approval of Ginna QA Program for Radioactive Matl Packages,Form 311,approval Number 0019.Ginna QA Program for Station Operation, Was Most Recently Submitted to NRC by Ltr Dtd 981221 & Supplemented on 990301 ML17265A6641999-05-25025 May 1999 Forwards Addl Info on Use of GIP Method a for Re Ginna Nuclear Power Plant.Copy of Re Ginna Station USI A-46 Outlier Resolution Table as Requested ML17265A6611999-05-24024 May 1999 Forwards LER 99-007-00 Re Personnel Error Which Caused Two Channels to Be in Tripped Condition,Resulting in Rt.Util Is Planning to Submit Suppl to LER by 990730 ML20206U0921999-05-13013 May 1999 Forwards Four Copies of Rev R to Gnpp Security Plan,Per Provisions of 10CFR50.54(p).Rev Clarifies Armed Response Team Assignments & Does Not Degrade Physical Security Effectiveness.Rev Withheld,Per 10CFR73.21 ML17265A6461999-05-12012 May 1999 Forwards 1998 Annual Radioactive Effluent Release Rept & 1998 Annual Radiological Environ Operating Rept, for Re Ginna NPP ML17265A6411999-05-12012 May 1999 Forwards LER 99-004-00 IAW 10CFR50.73 & 10CFR21.Further Assessment Will Be Provided in Suppl to LER by 990630 ML20206E7221999-04-29029 April 1999 Forwards Four Copies of Rev Q to Re Ginna Nuclear Power Plant Security Plan,Per 10CFR50.54(p).Changes Do Not Degrade Physical Security Effectiveness.Encl Withheld,Per 10CFR73.21 ML20206H6911999-04-22022 April 1999 Forwards Info Requested During Informal Telcon on 980408 Concerning Upcoming Osre at Ginna Station.Info Requested Listed.Without Encls ML17265A6271999-04-19019 April 1999 Forwards Rev 0 & Rev 1 to Colr,Cycle 28 for Re Ginna NPP, Per TS 5.6.5 ML17309A6501999-04-14014 April 1999 Forwards Revised Ginna Station EOPs & Procedures Index ML17265A6121999-03-29029 March 1999 Forwards Rept on Status of Decommissioning Funding for Re Ginna Npp,For Which Rg&E Is Sole Owner,Per 10CFR50.75. Data Presented Herein,Current as of 981231 ML17265A6041999-03-24024 March 1999 Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(ii)(B) & 10CFR21.Addl Analyses Are Being Performed to Support Future Cycle Operation & Supplemental LER Is Scheduled to Be Submitted by 990618 ML17265A5671999-03-0101 March 1999 Forwards Application for Amend to License DPR-18,to Revise TSs Battery Cell Parameters Limit for Specific Gravity (SR 3.8.6.3 & SR 3.8.6.6).Supporting Tss,Encl ML17265A5641999-03-0101 March 1999 Forwards Response to NRC 990217 RAI Concerning Changes to QA Program for Re Ginna Station Operation.Rg&E Is Modifying Changes Requested in 981221 Submittal.Modified QA Program,Encl ML17265A5551999-02-25025 February 1999 Informs That Util Is in Process of Revising fitness-for-duty Program,Developed in Accordance with 10CFR26.Util Will Continue to Use Dept of Health & Human Svcs Certified Test Facility for Majority of Tests During Yr ML17265A5561999-02-22022 February 1999 Forwards FFD Performance Data Rept for Six Months Ending 981231,per 10CFR26.71(d) ML17265A5451999-02-12012 February 1999 Forwards Simulator Four Year Certification Rept,Per 10CFR55.45(b)(5)(ii) ML17309A6491999-02-12012 February 1999 Forwards Ginna Station EOPs ML17265A5431999-02-0909 February 1999 Supplements 980806 Relief Request with Attached Table.Util Third 10-Yr ISI of Reactor Vessel Being Performed During 1999 Refueling Outage,Beginning on 990301 ML17265A5361999-02-0202 February 1999 Forwards Response to NRC 981203 RAI Re Resolution of Unresolved Safety Issue USI A-46.Util Does Not Agree with NRCs Interpretation.Detailed Bases,Encl ML17311A0691999-01-25025 January 1999 Forwards Revs to Ginna Station Emergency Plan Implementing Procedures (Epips).Previous Rev Had Incorrect Effective Date ML17311A0671999-01-14014 January 1999 Forwards Revised Emergency Operating Procedures for Re Ginna NPP ML17265A5131999-01-12012 January 1999 Forwards Revised Cover Page for Ginna Station Technical Requirements Manual (Trm), Rev 7,correcting Error in Effective Date 1999-09-30
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML17250B3041999-10-20020 October 1999 Forwards Changes to Tech Specs Bases for Re Ginna Nuclear Power Plant.Change Bars Indicate Those Revs Which Have Been Incorporated ML17265A7651999-10-0808 October 1999 Forwards Fifteen Relief Requests That Will Be Utilized for Ginna NPP Fourth Interval ISI Program That Will Start on Jan 1,2000.Attachment 1 Includes Summaries & Detailed Description of Each Relief Request ML17265A7631999-10-0505 October 1999 Requests Approval for Use of Relief Request Number 43 to Address Volumetric Examination Limitations (Less than 90%) Associated with a & B RHR Heat Exchanger Outlet Nozzle to Shell Welds.Approval Is Requested by Dec 31,2000 ML17265A7641999-10-0505 October 1999 Requests Approval for Use of Relief Request Number 42 to Address Volumetric Examinations Limitations (Less than 90%) Associated with Eight Class 1 Identified Welds or Areas of Reactor Pressure Vessel ML20212J3561999-09-30030 September 1999 Forwards Four Copies of Re Ginna NPP Training & Qualification Plan for Security Officers, Rev 7,dtd 990930. Synopsis of Changes,Encl.Encl Withheld Per 10CFR73.21 ML20212J3801999-09-30030 September 1999 Forwards Four Copies of Rev to Re Ginna NPP Security Plan.Rev Changes Contingency Weapons Available to Response Force to Those Most Effective in Current Defensive Strategy.Encl Withheld Per 10CFR73.21 IR 05000244/19990051999-09-24024 September 1999 Forwards More Detailed Response Re Main Steam Check Valve Performance Questions Arising from NRC Insp Rept 50-244/99-05 Following Completion of Independent Assessment Being Performed by Duke Engineering & Svcs ML17265A7571999-09-24024 September 1999 Forwards More Detailed Response Re Main Steam Check Valve Performance Questions Arising from NRC Insp Rept 50-244/99-05 Following Completion of Independent Assessment Being Performed by Duke Engineering & Svcs ML17265A7461999-08-31031 August 1999 Submits Response to NRC Administrative Ltr 95-03,rev 2, Availability of Reactor Vessel Integrity Database,Version, Dtd 990726 ML17265A7401999-08-26026 August 1999 Requests Approval for Use of Relief Request Number 35 Re Use of ASME Section XI Code,1995 Edition,1996 Addenda.Code Will Be Used to Develop Plant Fourth 10-year Interval ISI Program on Class 1,2 & 3 Components ML17265A7411999-08-26026 August 1999 Forwards LER 99-004-01 Re Plant Being Outside Design Basis Due to Containment Recirculation Fan Moisture Separator Vanes Being Incorrectly Installed.Part 21 Notification of 990512 Is Being Rescinded ML17250B3021999-08-23023 August 1999 Informs That Util & NRC Had Conference Call on 990816 to Review Approach in Responding to Questions,As Result of Questions Re Main Steam Check Valve Performance Included in Insp Rept 50-244/99-05,dtd 990806 ML17265A7451999-08-23023 August 1999 Forwards fitness-for-duty Performance Data Rept for Six Months Ending 990630,per 10CFR26.71(d) ML17265A7271999-07-30030 July 1999 Forwards 10CFR21 Interim Rept Per Reporting of Defects & Noncompliance,Section 21 (a) (2).Interim Rept Prepared Because Evaluation Cannot Be Completed within 60 Days from Discovery of Deviation or Failure to Comply ML17265A7151999-07-23023 July 1999 Forwards LER 99-007-01 Re Personnel Error Which Caused Two Channels to Be in Tripped Condition,Resulting in Reactor Trip.Further Investigation of Event Identified Addl Corrective Actions ML17265A7061999-07-22022 July 1999 Forwards LER 98-003-02,re Actuations of CR Emergency Air Treatment Sys.All Creats Actuations,Including Those Originally Believed to Be Valid Actuations,Were,In Fact Invalid Actuations ML17265A7191999-07-21021 July 1999 Forwards Ginna Station ISI Rept for Refueling Outage Conducted in 1999 ML17265A7141999-07-21021 July 1999 Withdraws Relief Request 35 for Plant Inservice Insp Program Section XI Requirements,Submitted on 980806.Licensee Plans to Resubmit Relief Request,Which Includes Addl Level of Detail,In Near Future ML17265A7041999-07-16016 July 1999 Submits Info Re Specific Licensing Actions Which May Be Expected to Generate Complex Reviews,In Response to Administrative Ltr 99-02,dtd 990603 ML17265A6911999-06-30030 June 1999 Responds to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants.Gl 98-01 Requested Response on Status of Facility Y2K Readiness by 990701.Readiness Disclosure Attached ML17265A6871999-06-22022 June 1999 Forwards Response to RAI Made During 990225 Telcon Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves. Calculation Encl. Encl ML17265A6841999-06-21021 June 1999 Informs That Util Wishes to Amend Extend of Alternate Exams Provided for Relief Request Re ISI Program ASME Section XI Require Exams for First 10-Yr Interval for Containment ML17265A6741999-06-15015 June 1999 Submits Annual ECCS Rept IAW 10CFR50.46(a)(3)(ii) Requirements.No Changes Have Been Made to Large Break LOCA PCT & Small Break LOCA PCT ML17265A6751999-06-11011 June 1999 Responds to NRC RAI Re Licensee GL 96-05 Program.Encl Info Verifies That Util Is Implementing Provisions of JOG Program on MOV Periodic Verification ML17309A6551999-06-0707 June 1999 Responds to NRC 990310 RAI Re Verification of Seismic Adequacy of Mechanical & Electrical Equipment ML17265A6671999-06-0101 June 1999 Requests Approval of Ginna QA Program for Radioactive Matl Packages,Form 311,approval Number 0019.Ginna QA Program for Station Operation, Was Most Recently Submitted to NRC by Ltr Dtd 981221 & Supplemented on 990301 ML17265A6641999-05-25025 May 1999 Forwards Addl Info on Use of GIP Method a for Re Ginna Nuclear Power Plant.Copy of Re Ginna Station USI A-46 Outlier Resolution Table as Requested ML17265A6611999-05-24024 May 1999 Forwards LER 99-007-00 Re Personnel Error Which Caused Two Channels to Be in Tripped Condition,Resulting in Rt.Util Is Planning to Submit Suppl to LER by 990730 ML20206U0921999-05-13013 May 1999 Forwards Four Copies of Rev R to Gnpp Security Plan,Per Provisions of 10CFR50.54(p).Rev Clarifies Armed Response Team Assignments & Does Not Degrade Physical Security Effectiveness.Rev Withheld,Per 10CFR73.21 ML17265A6461999-05-12012 May 1999 Forwards 1998 Annual Radioactive Effluent Release Rept & 1998 Annual Radiological Environ Operating Rept, for Re Ginna NPP ML17265A6411999-05-12012 May 1999 Forwards LER 99-004-00 IAW 10CFR50.73 & 10CFR21.Further Assessment Will Be Provided in Suppl to LER by 990630 ML20206E7221999-04-29029 April 1999 Forwards Four Copies of Rev Q to Re Ginna Nuclear Power Plant Security Plan,Per 10CFR50.54(p).Changes Do Not Degrade Physical Security Effectiveness.Encl Withheld,Per 10CFR73.21 ML20206H6911999-04-22022 April 1999 Forwards Info Requested During Informal Telcon on 980408 Concerning Upcoming Osre at Ginna Station.Info Requested Listed.Without Encls ML17265A6271999-04-19019 April 1999 Forwards Rev 0 & Rev 1 to Colr,Cycle 28 for Re Ginna NPP, Per TS 5.6.5 ML17309A6501999-04-14014 April 1999 Forwards Revised Ginna Station EOPs & Procedures Index ML17265A6121999-03-29029 March 1999 Forwards Rept on Status of Decommissioning Funding for Re Ginna Npp,For Which Rg&E Is Sole Owner,Per 10CFR50.75. Data Presented Herein,Current as of 981231 ML17265A6041999-03-24024 March 1999 Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(ii)(B) & 10CFR21.Addl Analyses Are Being Performed to Support Future Cycle Operation & Supplemental LER Is Scheduled to Be Submitted by 990618 ML17265A5641999-03-0101 March 1999 Forwards Response to NRC 990217 RAI Concerning Changes to QA Program for Re Ginna Station Operation.Rg&E Is Modifying Changes Requested in 981221 Submittal.Modified QA Program,Encl ML17265A5671999-03-0101 March 1999 Forwards Application for Amend to License DPR-18,to Revise TSs Battery Cell Parameters Limit for Specific Gravity (SR 3.8.6.3 & SR 3.8.6.6).Supporting Tss,Encl ML17265A5551999-02-25025 February 1999 Informs That Util Is in Process of Revising fitness-for-duty Program,Developed in Accordance with 10CFR26.Util Will Continue to Use Dept of Health & Human Svcs Certified Test Facility for Majority of Tests During Yr ML17265A5561999-02-22022 February 1999 Forwards FFD Performance Data Rept for Six Months Ending 981231,per 10CFR26.71(d) ML17265A5451999-02-12012 February 1999 Forwards Simulator Four Year Certification Rept,Per 10CFR55.45(b)(5)(ii) ML17309A6491999-02-12012 February 1999 Forwards Ginna Station EOPs ML17265A5431999-02-0909 February 1999 Supplements 980806 Relief Request with Attached Table.Util Third 10-Yr ISI of Reactor Vessel Being Performed During 1999 Refueling Outage,Beginning on 990301 ML17265A5361999-02-0202 February 1999 Forwards Response to NRC 981203 RAI Re Resolution of Unresolved Safety Issue USI A-46.Util Does Not Agree with NRCs Interpretation.Detailed Bases,Encl ML17311A0691999-01-25025 January 1999 Forwards Revs to Ginna Station Emergency Plan Implementing Procedures (Epips).Previous Rev Had Incorrect Effective Date ML17311A0671999-01-14014 January 1999 Forwards Revised Emergency Operating Procedures for Re Ginna NPP ML17265A5131999-01-12012 January 1999 Forwards Revised Cover Page for Ginna Station Technical Requirements Manual (Trm), Rev 7,correcting Error in Effective Date ML17265A5111999-01-11011 January 1999 Requests Relief Per 10CFR50.55a(a)(3)(ii) from Certain Requirements of Section XI of ASME Bp&V Code for ISI Program.Relief Requests 37,38 & 39 Encl ML17265A5101999-01-11011 January 1999 Requests Relief Per to 10CFR50.55a(a)(3)(ii) from Certain Requirements of Section XI of ASME B&PV Code for ISI Program.Relief Request 40 Encl 1999-09-30
[Table view] Category:UTILITY TO NRC
MONTHYEARML20059L4481990-09-18018 September 1990 Forwards Responses to Rer 900709-13 Team Visit Findings, Per .Responses Withheld (Ref 10CFR73.21) ML17309A4491990-09-13013 September 1990 Forwards Slides Presented by Facility & Westinghouse to NRC in 900724 Meeting.Encl Withheld ML17262A1331990-09-11011 September 1990 Responds to Violations & Several Unresolved Items Noted in SSFI Rept 50-244/89-81.Update of Appropriate Unresolved Items Encl.Specific Actions Re All NRC Unresolved Items Being Tracked to Completion ML17261B1511990-08-29029 August 1990 Forwards Semiannual Radioactive Effluent Release Rept Jan- June 1990 & Rev 3 to Process Control Program for Ginna Station, Per Tech Specs 6.9.1.4 & 6.16,respectively ML17261B1481990-08-28028 August 1990 Lists Understanding of Issues Util Planning to Address Re Containment Integrity,Per 900718 Telcon.Any Concerns or Action Items Different from Listed Submittal Should Be Provided to Util Prior to NRC 900905 & 06 Visit to Plant IR 05000244/19880261990-08-20020 August 1990 Submits Update on Util Plans to Provide Appropriate Ventilation to Intermediate Bldg Clean Side,Per Violation Noted in Insp Rept 50-244/88-26.Extensive Program to Manually Close All External Openings Implemented ML17261B1501990-08-20020 August 1990 Submits Update on Util Plans to Provide Appropriate Ventilation to Intermediate Bldg Clean Side,Per Violation Noted in Insp Rept 50-244/88-26.Extensive Program to Manually Close All External Openings Implemented ML17261B1371990-08-17017 August 1990 Forwards Rev 0 to, Inservice Insp Rept for Third Interval (1990-1999),First Period,First Outage (1990) at Re Ginna Nuclear Power Plant. ML17309A4481990-08-16016 August 1990 Responds to NRC 900717 Ltr Re Violations Noted in Insp Rept 50-244/90-80.Corrective Actions:Westinghouse Drawing E-2508 Approved & Issued to Central Records ML17261B1351990-08-15015 August 1990 Provides Info & Assessment on Integrity of Connection of Containment Bldg to Foundation,Per 900808 Telcon.Util Believes That Existing Condition Not Safety Concern & No Reason Exists to Suspect Joint Will Not Perform Function ML17261B1361990-08-14014 August 1990 Responds to Commitment Tracking Concerns Noted in Insp Rept 50-244/90-09 & Planned Corrective Actions.Util Confirms Commitments Dates for Implementation of Effective Shelf Life Program & Comprehensive Preventive Maint Program for Parts ML17261B1331990-08-13013 August 1990 Recommits to Performing Enhanced primary-to-secondary Leak Rate Monitoring,Per NRC Bulletin 88-002 ML17261B1261990-07-30030 July 1990 Clarifies Commitment Made in 900316 RO Re Restoring Inoperable Fire Damper I-411-21-P.Util Plans to Design Removable Track Which Will Allow Charcoal Drawer to Be Manipulated.Definitive Schedule Will Be Provided in 60 Days ML20055H9291990-07-23023 July 1990 Forwards Revised Page 6:4 of Plant Security Plan.Page Withheld Per 10CFR73.21 ML17261B1091990-07-20020 July 1990 Advises That Structural Evaluations of Containment Sys Being Performed in Response to Containment Integrity Insp ML17309A4471990-07-17017 July 1990 Forwards Decommissioning Rept, for Plant,Per 10CFR50.33(k) & 50.75(b) ML17261B0881990-07-13013 July 1990 Provides Update to Util 860616 Ltr Re Implementation of NUREG-0737,Item 6.2,Suppl 1, Emergency Response Capability. ML17261B0921990-07-11011 July 1990 Responds to 900709 Request for Addl Info Re Containment Integrity Insp.Util Will Provide Preliminary Results by 900716 Re Where Groundwater Entering Annular Access Area. Meeting Proposed for Wk of 900723 ML20044B0481990-07-10010 July 1990 Discusses Review of Station Blackout Documentation,Per 10CFR50.63.Licensee Will Complete Enhancements to Station Blackout Documentation Identified in Attachment 1 as Indicated & Other Items Will Be Completed within 2 Yrs ML17309A4461990-07-0909 July 1990 Responds to Generic Ltr 90-04 Re Status of Licensee Implementation of Generic Safety Issues Resolved W/ Imposition of Requirements or Corrective Actions ML17261B0931990-07-0909 July 1990 Responds to Generic Ltr 88-14, Instrument Air Supply Sys Problems Affecting Safety-Related Equipment. Util Completed All Actions Requested in Generic Ltr & Will Retain Documentation Verification for Min of 2 Yrs ML17261B0901990-07-0909 July 1990 Advises That Licensee Will Install Containment Isolation Signal Going to Valve AOV 745 by End of 1992 Refueling Outage,Per Util 900608 Ltr Notifying of Condition Outside Design Basis of Plant Under 10CFR50.72 Criterion ML17250B2151990-06-29029 June 1990 Forwards Application for Amend to License DPR-18, Reformatting Auxiliary Electrical Sys Tech Specs & Action Statements for Offsite & Onsite Power Sources Available for Plant Auxiliaries ML17261B0851990-06-28028 June 1990 Forwards LER 89-016-02 Re 891117 Failure of Safety Injection Block/Unblock Switch Which Could Render Both Trains of Safety Injection Sys Inoperable.Also Reported Per Part 21 ML17250B1991990-06-0808 June 1990 Responds to NRC 900509 Ltr Re Violations Noted in Insp Rept 50-244/89-81.Corrective Actions:Improved Battery Load Profile Developed Incorporating Calculational Improvements Contained in Current Industry Std IEEE 485-1983 ML17250B1951990-06-0505 June 1990 Responds to Generic Ltr 89-08, Erosion/Corrosion Induced Pipe Wall Thinning. Util Developed Erosion/Corrosion Program for Single & Two Phase Sys Consistent W/Requirements of NUREG-1344 & NUMARC 870611 Rept ML17250B1851990-06-0101 June 1990 Forwards Application for Amend to License DPR-18,providing Guidance for Action Statements Associated W/Power Distribution Limit Specs ML17261B0691990-06-0101 June 1990 Discusses Testing Frequency for Insp of Incore Neutron Monitoring Sys Thimble Tubes,Per NRC Bulletin 88-009.Thimble Tube Indicating Greatest Wear Recently Repositioned in Effort to Minimize Future Wear ML17250B1811990-05-31031 May 1990 Forwards Addl Info Re Response to Notice of Violation from Insp Rept 50-244/90-04.Info Withheld (Ref 10CFR73.21) ML17250B1801990-05-29029 May 1990 Responds to NRC Bulletin 90-001, Loss of Fill-Oil in Transmitters Mfg by Rosemount. Util Does Not Need to Develop Enhanced Surveillance Program to Monitor Currently Installed Transmitter Based Upon Limited Installed Quantity ML17250B1841990-05-29029 May 1990 Responds to NRC Bulletin 89-002, Stress Corrosion Cracking of High Hardness Type 410 Stainless Steel (SS) Internal Pre-Load Bolting.... Valves Disassembled & 410 SS Studs Removed & Visually & Liquid Penetrant Examined ML17261B0961990-05-29029 May 1990 Responds to NRC 900427 Ltr Re Violations Noted in Insp Rept 50-244/90-07.Corrective Actions:Worker Records Immediately Corrected Indicating That Worker Received No Significant Exposure for Time While Error Occurred ML17250B1721990-05-18018 May 1990 Forwards Rev 1 to Summary Exam Rept for 1990 Steam Generator Eddy Current Insp. Rept Summarizes Observations & Corrective Actions Resulting from Insps Performed During 1990 Outage ML20042G8931990-05-0808 May 1990 Forwards Revised Emergency Operating Procedures,Including Rev 3 to AP-RHR.2,Rev 1 to ES-0.3 & Rev 11 to ES-1.3 ML17261B0611990-04-26026 April 1990 Advises of Changes to 890201 Commitments Made Under Programmed Enhancement Response to Generic Ltr 88-17.Changes Will Not Reduce Capability to Operate Safely in Reduced Inventory Condition or Scope of Programmed Enhancements ML17261B0591990-04-17017 April 1990 Advises That No Interlocks Required for RHR motor-operated Valves 701 & 720 Based on Present Arrangement.Listed Failures Would Have to Occur in Order for Potential Overpressurization of RHR Sys to Occur ML17261B0461990-04-12012 April 1990 Responds to Issues Discussed During 900323 Telcon Re Inservice Testing Program Status & Relief Request.Current Test Methodology for Seat Leakage Acceptable Based on Application of Direct Measurement Sys ML17262A1431990-04-12012 April 1990 Responds to NRC 900202 Ltr Re Weaknesses Noted in Insp Rept 50-244/89-80.Corrective Actions:Procedure ES-0.3 Modified to Provide Guidance for Rapid Cooldown & Depressurization W/ & W/O Reactor & Vessel Instrumentation Sys ML17250B1451990-04-0606 April 1990 Discusses Impact of SER Issuance for Inservice Insp & Inservice Testing Programs & Advises That Timing Will Not Affect Util Implementation Plans for Programs,Except as Listed ML17250B1441990-04-0505 April 1990 Responds to NRC 900309 Ltr Re Violations Noted in Insp Rept 50-244/90-02.Corrective Actions:Positive Indicator Will Be Installed for All Check Valves to Enhance Visible Positive Position Verification Ability & to Avoid Confusion ML17261B0401990-03-30030 March 1990 Advises That Final Results of Station Blackout Documentation Review Will Be Submitted to NRC on or About 900501 ML17261B0321990-03-28028 March 1990 Forwards Annual Rept of ECCS Model Revs as Applicable to Facility,Per 10CFR50.46.Mods to Model for Small Break LOCA Do Not Affect Calculated Peak Clad Temp ML17261B0331990-03-28028 March 1990 Forwards Info Re Reactor Vessel Issues,Per 900305 Telcon Concerning Change of License Expiration Date ML17261B0231990-03-26026 March 1990 Responds to NRC 890222 Ltr Re Violations Noted in Insp Rept 50-244/89-17.Corrective Actions:Personnel Verified Safety Injection Block/Unblock Switch in Proper Position & Operator Procedure 0-1.1 Changed as Indicated ML17261B0281990-03-23023 March 1990 Forwards Addl Info Re Proposed Tech Spec Amend Concerning Use of Reconstituted Fuel,Per 900315 Telcon.During Fuel Assembly Reconstitution,Failed Fuel Rods Will Be Placed W/ Filler Rods ML17261B0221990-03-22022 March 1990 Provides Revised Test Schedule for motor-operated Valve Diagnostic Test Program,Per IE Bulletin 85-003.NRC Notification of Changes to Valve Operability Program Required by Generic Ltr 89-10,dtd 890828 ML17261B0411990-03-20020 March 1990 Forwards Summary of Onsite Property Damage Coverage Currently in Force at Plant,Per 10CFR50.54(w)(4) ML17261B0151990-03-19019 March 1990 Responds to Generic Ltr 89-19, Safety Implication of Control Sys in LWR Nuclear Plants (USI A-47). Overfill Protection Provided Through Trip Bistables in Reactor Protection Racks Powered from 120-volt Instrument Buses ML17261B0101990-03-15015 March 1990 Forwards Application for Amend to License DPR-18,allowing Use of Reconstituted Fuel Assemblies ML20012D2831990-03-14014 March 1990 Responds to Issues Discussed During 900307 Telcon W/Util & Eg&G Re Inservice Testing Program Status & Relief Request. Valves 5960A & 5960B Will Be Disassembled to Verify Forward Flow.Relief Requests PR-8 & VR-25 Encl 1990-09-18
[Table view] |
Text
Z ge Gixzw Stat'cn March 15, 1979 Nr. 3v'ar en S. 2~alton NucleaRem1 a"ory Corrmission Was'.ton, D.C. 20555
Subject:
Code ~sea tabil' o "~e "3" Lalar '.!Ozzie =L=-.- )rcic=-="'cn in t'.-.e R. E. Gi wa. Reactor Pressure Vessel
Dear! . i.~".e tcn:
CCOC..aster Gas c Q "l2C. C Cor O at:~ P~ C .;C Uda ."-: '2:. 'a '~"S detac"ad in ~".2 "3" inlet nozzle o= ~".2 2,. E. Ginna) Reactor Pressure eSSe at <<<<2 m)eet \
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Ccns2.st nt 'R.i:. ) .2 r Qua t or Hcc.. sta Gas c lo ~ ct "c, out.Bast Rase"-~c'.". ns-= ta ca'e)c"ed a tac.".n='"ue ano the necassa=p associa=ac aaui c t to C~ao>> a., U., aSC, 'C 2=.. aswarm - llV De"aa )CiCul=-. tO subja " "'2 o =-."'s. T.t vas
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~.-ould "2 m"2 s~wi=='-."2 ."".~~ t."e c"ca "'e-."'"e 2~" '~=t"'~s o" =.'..'s area.
A raVLEv- Or i."2 U' aSCP'C 2~~'~at-"" <<=Su tS OZ tna '~" ~~~) ar nOZZ'2 =0 vessel aid c~".cnsi=ata '-;2 inc=ease sa.)sit='vity ~at'". "'".a "..2-: i;- cave-opeo a~=-v-'".ation tacana a. Spa.>> "c-'ec""rs vera catactad vi=h "'".'s tacizic e .4'la not '=em~ detectao 'c.= ~".2 Code defineo anzac"'narions of this area cur'ag the Y~~ch 1979 outa=a.
This c early de .Onst=atas the supe iority of this 'newly cava oped techniat'e. Part of the devalo"ment effort of this technique included cons~ceration or nc .al u'scnic cern spread. 3y coL. a imper=act='ons to "'".2 recorded e~mi~"-tion results a conserva<<ively hara in'i~ -ta acct'-ate prediction of t")e reflector size is obtained. Uti '"in'his technic 2 ~d agu "rent, a ref lecto o less than .32 inches (th"oueh-val'.) a- cetac"2 '. z iwer=ecticn o" th's size meets the acceptance s iandards ot act:c,l ZZ.
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Mzcn 13 I /9 Page 2 of 2 Therefore,;.-e conclude that the 15 degree refracted long~ eudinal angle bean e~~i'ticn of the nozzle to vessel velds -.=ca the ..ozz'e bore confirm the s~~c=~al adeayecy of Nese nozzles in accordance ~~~th Section ZE of &e .~~f"" Reviler and Pressure Vessel Code by virtue of the demcnswat d a'pe iority of tMs ne..-ly deve oped t chnique over Code defined e~mtions.
Sincerely, Albert E. C~~is Beld~ .g and Ncl ces 'ct:ve Level iT~, UZ, W, ~2', P",
AEC: kes/d2V The nevi- ceveloced t ~ ~" Ke descr'=ed "-ave 1w been c~m-..s =-"=- '
to yiela s. "e 'or = s" ts to v sat=ac""c..
R. J. Clave~ e ins"ec icn Spec'- 's-H8 0 o +te:- 1 ~03.'e inspec"='cn '~~ =~~=--.ce Cm .y
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BEAM SPREAD CORRECTION W. C. HcGaughey Southwest Research Institute San Antonio, Texas 78284 B earn spreaa measu asuremencs have been a Section XI requirement since the 19>3 Summer A'd a en daa, Paragraph I-4460, became ez=ect"ve. Section Z , p
'graph IWA-2232(a) rezers to Section V, Article 4 for ultrasonic -asonic .examination rules. The latrer Paragraph T-431.3 requires beam spread measuremencs ar.
intervalsal no greacer cer than 3 monchs. The beam spread measurement'echnique is in the nonmandatory appendix as Paragraph B-60, so ocher techniques may be used.
No use oz beam spread measuremenrs is specified 'n the Code. Unozfic'al but generally recognized justification for cont~ning the requirement include (a) identificarion oz beam variables to assist in selection oz a search unit zor a reexaminacion at a later dare, (b) to have the informcion avail-able ien it is determined how co perform beam. spread correcrion oz inaica-tion ai ensions.
Dur'ng the =eoruary 1979 Ins ervic~ Emv'nation oz the Rochester Gas ana
-"'c Com an 's Robert E. Ginna plant, a complete mechanizea examina-t"'on oz tNe reactor pressure vessel weld was accomp~ished. 1"' 'hese Th examina-tions d'isc osea the impe =ect"'ons n tne weld or assoc'ated oase meta ..
. e oresence oz several ultrasonic rezlectors due ro cal.:!ost were readi'ece oned to be within the ASME Code acceptance stanaar!is.
os" oz oi these ese re leccors Therefore, further evaluation oz these reflectors was no ne recoraed for =uture rezerence. One nd'cac'on veld oz 'ozzie 32%%as oz an amplit ae reauir.'ng furrher evaluac'on on oz 'cs
" ce. Ii&rcer to perform a fracture mechanics evaluation oz t"e t..e signi="'cance oz this re lector, the true size oz t.ie z~aw was .
A process oz eva~uacion oz t'x"miaacion the aara was unaertaken in an acta= c co dece "'ne the size ana narure oz this re ec ror. Also controlled exper.'-
ments were perfo=ed to conzi~ che accuracr oz thhe theoretica'alcu'c=cns and considerations.
't Recoraea mechanized ultrasonic examinac'ons penni reaaing indic t=ons t7 Oi.
DAC ana greacer. The 0', '5' 0 , ~5 an 60'xaminat'ons zrom che inside sur=ace oz the vessel as we 11 as c.4 e 45'xamination from the nozz'e bore show no record of the indication detected with che 15 angle beam longitua nal wave from h noz"" e b ore.
the The plane oz maximum sensit"vity is the same for the 15 nozzle bore and the radiographic examinations. his is supported by the zacc that no ultrasonic response from the imper=acr"'on "h 0'5 and 60 examinations per orated on the vessel wall or from the 45'xamination also performed from the nozzzlee bore. ore. These e tially perp essenti erpendicular to the 15 longitudinal wave i
obsezvarions indicate rhat the rezlector is direc tional and is oriented sound 'beam. If the b een o bc ain area.
'd ref 1 ec tor was a rougn and faceted crack, uxcrasonic onic indications from the other examination beams whz.cn alsoo in If the rezlecror were more globular, or rounded, d d resp would have .
interro g ated this res onses co these other examinat"'on angles would also have been nooted. e Based on experience
'n vessel fabricator shops, this type oz th'n 'n p lanar sla g has been notea ermore, a review of the zabricacion raaiograpns other occasions. P urtthermore
'n
1 of this.'weld show the presence of entrapped planar slag. ais vas confi=ea by several 'Level III reviewers of the radiograDhs.
Therezore, it was concluded that the rezlector is thin, smooth, and in a plane perpendicular to the 15'eam. The wr-'tex nas vitnessed the ezcava-tion of a similar indication in a fabrication shop. The shop-ezcavated indication vas not detectea vith the 0', 45'nd 60'ltrasonic ezaminat'ons bur. vas repaired due to a clear raaiographic indication. Zzcavation revealed a 1/32-inch thick, smooth slag inclusion measuring 1-inch throughvall by 3 inches long near midwall at, the fusion line of a nozzle-to-vessel weld.
Due to the similarity of the nondestructive ezamination responses, it is believed that the indication in the Ginna reactor pressure vessel weld N2APis a thin, smooth slag inclusion in a plane(RPV)'ozzle-to-vessel perpendicular to the beam oz the 15'ozzle bore ezamination.
Heat affected zone (HAZ) cracks vere detected in three nozzle-to-shell velds in the 1972 preservice of the Harch Unit 1 RpV. These cracks vere detected with 45'na 60'zaminations from the outside suriace oz the vessel and subsequently ezcavated and repaired. These cracks vere con-firmed with 0', 45'nd 60'zaminarions from rhe inside surzace or the vessel, 10'zamination from the nozzle bore and by metallographic elm'n-arion during ezcavation. Neither record radiographs nor raaiograpns taken on site revealed the PQ c acks. The multifaceted nature of such cracks breaks up the rez'cr."on so that several small indications oz multiple planes are observed. Sizing such rezlectors to the 50% DAC limits oz the indicat"'on works well without beam spread correction of '"dicat'on dimen-sions. Indications having unknovn orie tat-'on and ident'ty should be si"ea to the 50% DAC limits wirhout beam spread correct'on. Howeve , based on Southwest Research inst-'tute's (SwRI) ezper'ence with flav inaicat'on sizing, beam spread correction should be used on some flaw indications.
in Appendi, 'z Undex'ost conait=ons, P essuxe Vesse'ode.
a reflector can be sized by using the rules contained rhe 1974 idition oz Sect=on Zi oz the ASl~ Boile ana In this case, these rules are not approor'ate.
Appena'z 1 sizing rules are basea on us-'ng 45 and/or 60'ng'e oeam (or other angle beams separated by ar least 15') ezamination techniques. Such ezaminat"'ons were applied to the vessel inside surface but did not detect the subject re lecror and the weld in e Sect passed the Code- equ'"ed UT ezaminations. .ven rhough it'as not a Code requirement, an angle beam longiruainal wave was aopl'ea to the bore oz the nozzle and directed perpendicular to rhe azis oz the weld. This additional ezamination vas per ormed in the interest, of mazimizing the ex=ectiveness oz the weld intexrogation. Direct"'ng a beam perpenaicular to the major reflec""'ng plane oz a weld-related defect results in a hign degree oz reflec .'vity from an imperzec ion. This technique, wnich is more sensitive to planar reflectors at the weld intexzace than the typical techniaue describe bed in n Appenaiz 1, can be aoplied only because oz the unique geometry surrounaing the nozzle-to-shell weld. Because the search unit movement during t. e nozzle bore scan is essentially par'allel to the plane of the Slaw, some of the ezamination paramer.ers which enter into the flaw>>size calculations des" cribed in Appendiz 1 are not available. Since reflection amplituae and parallel search unit movement. are the only parameters available to be used in determining z'aw size, suoplemental considerations must be effected.
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Z3-iO Recognizing that the difxerenca between the measured and the true rexlector size can only be determined by consider'ng tha basic sound beam propeztes, a briez summazv of the physics ox ultrasonic beam propagat-'on wnicn de=ines the beam spread and sound pressure ampl'tude distribution within that oeam are as follows:
The beam spread angle calculated from the equat on, j from the beam axis to the edge oz the total beam is
'total1= arcsin 1.22 X/D 4
!.2g V 4
X = wavelength= V/f v'here V = velocity in the mate ial n milli etars per microsecond f = examination frequency in cycles per microsecond D = dimension of the transducer in millimeters The beam spread angle to the 50% point is calculated using the equation, 50'rcsin 0
. 56 V/fD and to the 20% point 20%
= arcsin .92 V/fD A 2.25 M", 3/4-in. d'a. seazch unit produc ng a stzaignt beam longitudinal wave in steel has a V/fD = 5.89/2.25(.75)25.4 = .1374, tharezora
~ 4 ann ~~~ 7 3 50%
Since these angles are comouted for ha oeam ass to the 50% and the 20%
levels, the 50 co 50% and 20 to 2GZ ang'es double. That 's, halz oz the ene gy is outsice the 8.8'one and 20,. oz the energy is outside the cone.
14.6'n order to obtain beam easuremants on the same basis as the computea beam spread angles, we would need to use var ous si"es oz d.sc re lectors (suc..
as z'at-oortom holes) to rezlec the 50 to 50% portion oz the beam. Side-drilled holes are a batter geometz'c siwlation of suspect re lectors and are more convenient razlectors or ang'a beam calibration s'nce they are eaually re lective to var'ous 'oeam angles and modes oz wave motion. The nonmandatory Code technique foz beam spread measurement uses the 50 to 50%
DAC response from the side-drilled hole. (This is diffezent fzom the 50%
~ of total beam computation and the measured angles are dixferent from the computed angles.) En this case the investigation metal path is greater than 3T/4 metal path, so the responses f om the T/2 and 3T/4 calibration rezlectoz were used for beam spread measurement. Figure 2 shows spread for the 50 to 50% DAC points, while similar plotting gave an 5-1/2'eam ll'eam spread for the 20 to 20% DAC points as measured on side-drilled holes. Such a beam detec ed and 50% DAC sized the Figure 1 indication which gave 117% DAC maximum amplitude from a reflector in nor le-to-shell weld 32. in the Ginna RPV dur'ng the 'Aarch 1979 inservica examination.
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As shown in the top frame oz Figure 1, the indication was recorded on a circumrerential scan of the nozzle-to-vessel wild zrom the nozzle bore with the 15'ngle beam longitudinal wave at 7.64-inch metal path in razerence position 19.14 inches and on successive circumxerenciai scans at rarexence positions 19.40, 19.62, and 19.87 inches. These scan increments increase the macai path to a rezlector perpendicular to the 15'eam by the relation-ship:
KP ~ Sin 15'scan increments): that is, EP = Sin 15'.26 in.) = .0673 in.
= Sin 15'.22 in,.) = .0569 in.
= Sin 15'.25 in.) = .0647 in.
Adding these l6s and comparing che computed ilPs for a planar reflector to average maximum amplitude metal paths for each oz the three successive scans g.ves the following:
Range oz Maximum Amplitude Deviat'n Comoutad Comoutaa K've age <i.etal Path No. or Areas from Ave. .Gnus Ave.
7.64 in. 7.64 in. (Base Reading) 0) 7.71 in. 7 73 inr (4) +.01 .02 in.
7.76 in. 7.75 in. (3) 01 +.Ol in.
7.83 in. 7.83 in. (4) +.01 .00 in.
The ~.Ol-inch range oz deviation zrom average calculates to a range oz re"lec"or plane angles o" 15' :3'or tha eleven maximum ampl'tude metal path readings. This substant"'ates our conc'usion that the scrag nc'us on is located at the weld-to-base =ecai inter"aca in a plane perpendicular to the 15'ngle beam long'tudinal wave.
A studv was conducted to demonstrate the appropriateness o= beam spread corrected rez actor siz'ng. Essentially this study consisted or p acing a rlat-bottom hole rarlector in the ca'1'brat"'on block and compaxing the measured size with the known reflector size. in this test, the geometry oz the nozzle azznination area was simulated, the same or s-'milar search unit a d wedges were used, and s- milax records were taken. Other controls exercised in the study to assure aporopriateness oz the compar"'son are as follows:
- 1. A flat-bottom hole was drilled at an angle so that the search unit-wedge combination used in measurement of-the flaw indication
'roduces a beam perpendiculax to the flat-bottom hole at a metal path within +3.0X of the flaw indication metal path.
- 2. The flat-bottom hole was located in a calibrat'on block so it does not intexfere with subsequent calibrations.
t'ced
- 3. The selected calibration block nad ultrasonic coupling conditions similar to the ezamination and had the same diameter side-drilled holes as used in calibration for the ezamination.
- 4. Calibration vas performed on the block for comparing the flat-bottomed hole response to the maximum response of the flaw indica-tion.
- 5. The flat-bottom hole amplitude zesponse did not deviate from the flaw indication response by more than 2 dB.
- 6. 50% to 50X DAC measurements vera made on the flat-bottom hola in the through-vali and length directions as the search unit vas moved toward and across the ra"lector.
- 7. The 50Z to 50% DAC through-vail dimension of the flat-bottom hole minus the flat-bottom hole diameter was demonstrated to be the througn-vail spread correction.
S. The 5 0% to 50X DAC length di=ension of the flat-bottom hole m'nus the fiat-bottom hole diamete was demonstrated to be the length beam spread correct.'on.
- 9. The flaw indicat"'on througn-wall dimension 2a minus tha thzough-vail beam spread correct"'on was shown to be the beam corrected flaw ind'cat'on dimension 2ac.
- 10. The i flav ndicat"'on length d.'=ension minus the length beam spread correct'on vas shown to be the beam spread corrected f'aw dicat"on Ec.
The beam spread cor acted flaw indicat'on dimensions ac and Zc as showa in .""igure 3 vere used 'n computing a/2, rat'o and the a;;I oz t of the indication for compar'son with the ailovabia indication limits apolicabie to the indication location.
In this instance, it vas possible to s'mulata the examination condition a d vessel component geometrr and demonstrate tha ef=ects oz ultrasonic bean spreaa on data~ning the size oz a rezlactor. This paz =cular reflector vas weil suited =or this ezercise bac usa its ox'entat on vas established with an unusuailv hign level oz conzide ce by interzogating 't 'n more ways than is usually possible. All oz the information accu=u atad raiat"'.'a to this rezlector gives a high level of conzidenca that its trna size, or'entation t and character are as reported and that the pract"'ca oz basing its size on the projected 50X DAC l~ts corrected for beam spread s appropriate.
Also, Paragraph DiA-2240 allows. for alternate techniques to be used in lieu of the Code spec.'fie'd techniques ifit can be demonstrated to the sat'sfaction of the inspection specialist that the alternate techniques provide results wnich aza equal or super'or to the Code specified techniques. This was done and the alternate sizing techniques used aza the afore in compliance with the requirements oz Se tion ZI oi the ASM'ode.
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ATTACHMENT 2 FRACTURE MECHANICS EVALUATION OF INLET NOZZLE INSERVICE INSPECTION INDICATION
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