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Category:CORRESPONDENCE-LETTERS
MONTHYEARNPL-99-0564, Forwards Response to NRC Request During 990720 Meeting,To Provide Addl Details to Several Questions Re Amend Currently Under Review by Staff Pertaining to CR Habitability1999-10-19019 October 1999 Forwards Response to NRC Request During 990720 Meeting,To Provide Addl Details to Several Questions Re Amend Currently Under Review by Staff Pertaining to CR Habitability ML20217A5911999-09-30030 September 1999 Advises of NRC Plans for Future Insp Activities at Facility for Licensee to Have Opportunity to Prepare for Insps & to Provide NRC with Feedback on Any Planned Insps Which May Conflict with Plant Activities.Plant Issues Matrix Encl 05000266/LER-1999-007, Forwards LER 99-007-00 for Point Beach Nuclear Plant,Unit 1. Condition Would Be Outside App R Design Basis for Plant.New Commitments within Rept Indicated in Italics1999-09-30030 September 1999 Forwards LER 99-007-00 for Point Beach Nuclear Plant,Unit 1. Condition Would Be Outside App R Design Basis for Plant.New Commitments within Rept Indicated in Italics ML20212J7431999-09-30030 September 1999 Forwards Insp Repts 50-266/99-15 & 50-301/99-15 on 990830- 0903.No Violations Noted.Inspectors Concluded That Util Licensed Operator Requalification Training Program Satisfactorily Implemented NPL-99-0555, Discusses Rev 1,suppl 1 to GL 92-01, Reactor Vessel Structural Integrity. Calculation That Provides Evaluation of New Surveillance Data for Assessing Integrity of Unit 1 Reactor Vessel1999-09-29029 September 1999 Discusses Rev 1,suppl 1 to GL 92-01, Reactor Vessel Structural Integrity. Calculation That Provides Evaluation of New Surveillance Data for Assessing Integrity of Unit 1 Reactor Vessel ML20212K7651999-09-29029 September 1999 Forwards Insp Repts 50-266/99-13 & 50-301/99-13 on 990714-0830.No Violations Noted.Operators Responded Well to Problems with Unit 1 Instrument Air Leak & Unit 2 Turbine Governor Valve Position Fluctuation ML20212D5771999-09-15015 September 1999 Discusses Review of Response to GL 88-20,suppl 4,requesting All Licensees to Perform Ipeee.Ser,Ter & Supplemental TER Encl ML20211Q6451999-09-0808 September 1999 Forwards Operator Licensing Exam Repts 50-266/99-301OL & 50-301/99-301OL for Exams Conducted on 990726-0802 at Point Beach Npp.All Nine Applicants Passed All Sections of Exam ML20211Q4171999-09-0606 September 1999 Responds to VA Kaminskas by Informing That NRC Tentatively Scheduled Initial Licensing Exam for Operator License Applicants During Weeks of 001016 & 23.Validation of Exam Will Occur at Station During Wk of 000925 05000266/LER-1999-004, Forwards LER 99-004-01,re Fuel Oil Transfer Pump Cable in AFW Pump Room Being Outside App R Design Basis.Suppl to LER Provides Corrective Actions to Address Concerns Re Fire Disrupting Electrical Power to Fuel Oil Transfer Pump1999-09-0202 September 1999 Forwards LER 99-004-01,re Fuel Oil Transfer Pump Cable in AFW Pump Room Being Outside App R Design Basis.Suppl to LER Provides Corrective Actions to Address Concerns Re Fire Disrupting Electrical Power to Fuel Oil Transfer Pump ML20211K5261999-08-31031 August 1999 Forwards Insp Repts 50-266/99-14 & 50-301/99-14 on 990726- 30.Areas Examined within Secutity Program Identified in Rept.No Violations Noted ML20211F6941999-08-27027 August 1999 Provides Individual Exam Results for Applicants That Took Initial License Exam in July & August of 1999.Completed ES-501-2,copy of Each Individual License,Ol Exam Rept, ES-303-1,ES-303-2 & ES-401-8 Encl.Without Encl NPL-99-0473, Informs of Change Being Made to Plan Third 10-year Interval ISI Long Term Plan.Change Extends Interval from Current End Date of 001130 to 020831,due to Operating Cycle Being Increased from 12 to 18 Months1999-08-27027 August 1999 Informs of Change Being Made to Plan Third 10-year Interval ISI Long Term Plan.Change Extends Interval from Current End Date of 001130 to 020831,due to Operating Cycle Being Increased from 12 to 18 Months ML20211E8791999-08-24024 August 1999 Discusses Completion of Licensing Action for GL 96-01, Testing of Safety-Related Logic Circuits, for Point Beach Nuclear Power Plant,Units 1 & 2.Licensees Provided Requested Info & Responses Required by GL 96-01 ML20211F1501999-08-24024 August 1999 Submits Summary of Meeting Held on 990729,in Region III Office with Util Re Proposed Revs to Plant Emergency Action Level Criteria Used in Classifying Emergencies & Results of Recent Improvement Initiatives in Emergency Preparedness 05000266/LER-1999-006, Forwards LER 99-006-00 Which Describes Discovery That Postulated Fire in Central Zone of Primary Auxiliary Bldg Could Result in Spurious Operation of Pressurizer Porv. New Commitments within Rept Are Indicated in Italics1999-08-19019 August 1999 Forwards LER 99-006-00 Which Describes Discovery That Postulated Fire in Central Zone of Primary Auxiliary Bldg Could Result in Spurious Operation of Pressurizer Porv. New Commitments within Rept Are Indicated in Italics NPL-99-0477, Forwards Revised Procedures to Point Beach Nuclear Plant Epips.Revised Procedures Dtd 990723,should Be Filed in NRC Copies of Manual IAW Attached Instructions1999-08-18018 August 1999 Forwards Revised Procedures to Point Beach Nuclear Plant Epips.Revised Procedures Dtd 990723,should Be Filed in NRC Copies of Manual IAW Attached Instructions NPL-99-0426, Requests Relief from Section II of ASME B&PV Code, Nuclear Vessels, 1965 Edition,No Addenda.Detailed Info Attached1999-08-16016 August 1999 Requests Relief from Section II of ASME B&PV Code, Nuclear Vessels, 1965 Edition,No Addenda.Detailed Info Attached ML20210L9141999-08-0404 August 1999 Informs That Versions of Info Re WCAP-14787,submitted in 990622 Application for Amend,Marked Proprietary,Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954,as Amended ML20210K5221999-08-0404 August 1999 Discusses Point Beach Nuclear Plant,Units 1 & 2 Response to Request for Info in GL 92-01,Rev 1,Suppl 1, Rv Structural Integrity NPL-99-0436, Forwards fitness-for-duty Performance Data for six-month Period Ending 9906301999-08-0202 August 1999 Forwards fitness-for-duty Performance Data for six-month Period Ending 990630 ML20210G6011999-07-30030 July 1999 Discusses 990415 Complaint OSHA Received from Employee of Wisconsin Electric Power Co Alleging That Employee Received Lower Performance Appraisal for 1998 Because Employee Raised Safety Concerns While Performing Duties at Point Beach NPL-99-0406, Provides Response to NRC GL 99-02, Lab Testing of Nuclear- Grade Activated Charcoal1999-07-29029 July 1999 Provides Response to NRC GL 99-02, Lab Testing of Nuclear- Grade Activated Charcoal ML20210H0211999-07-28028 July 1999 Forwards Insp Repts 50-266/99-09 & 50-301/99-09 on 990528-0713.Two Violations of NRC Requirements Occurred & Being Treated as non-cited Violations,Consistent with App C of Enforcement Policy ML20210G2441999-07-26026 July 1999 Discusses 990714 Meeting with PRA Staff to Discuss Initiatives in Risk Area & to Establish Dialog Between SRAs & PRA Staff NPL-99-0408, Forwards Pbnps,Units 1 & 2 Plant Simulation Four-Yr Rept, IAW 10CFR55.45(b)(5)(ii).Rept Describes Certification Program Tests Conducted from 1996-1999,identifies Test Discrepancies Still Outstanding & Schedules for 2000-20031999-07-15015 July 1999 Forwards Pbnps,Units 1 & 2 Plant Simulation Four-Yr Rept, IAW 10CFR55.45(b)(5)(ii).Rept Describes Certification Program Tests Conducted from 1996-1999,identifies Test Discrepancies Still Outstanding & Schedules for 2000-2003 ML20209H5471999-07-14014 July 1999 Forwards Insp Repts 50-266/99-12 & 50-301/99-12 on 990614-18.One Violation Noted,But Being Treated as non-cited violation.Long-term MOV Program Not Sufficiently Established to close-out NRC Review of Program,Per GL 89-10 NPL-99-0395, Forwards Partial Response to NRC 990512 RAI Re TS Change 204 Re Control Room Habitability.Meeting Is Planned with NRC to Discuss Issues Related to Control Room & Primary Auxiliary Bldg Ventilation Sys Modifications1999-07-12012 July 1999 Forwards Partial Response to NRC 990512 RAI Re TS Change 204 Re Control Room Habitability.Meeting Is Planned with NRC to Discuss Issues Related to Control Room & Primary Auxiliary Bldg Ventilation Sys Modifications NPL-99-0390, Projects Listed Major near-term License Amend Requests That Could Be Expected to Impact Staff Resources Into Fiscal Years 2000 & 2001,in Response to Administrative Ltr 99-021999-07-0808 July 1999 Projects Listed Major near-term License Amend Requests That Could Be Expected to Impact Staff Resources Into Fiscal Years 2000 & 2001,in Response to Administrative Ltr 99-02 NPL-99-0388, Forwards MORs for June 1999 & Revised MORs for May 1999 for Pbnps,Units 1 & 21999-07-0707 July 1999 Forwards MORs for June 1999 & Revised MORs for May 1999 for Pbnps,Units 1 & 2 NPL-99-0381, Submits Response to NRC GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. GL 98-01 Requested Response on Status of Facility Y2K Readiness by 990701.Disclosure Encl1999-06-30030 June 1999 Submits Response to NRC GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. GL 98-01 Requested Response on Status of Facility Y2K Readiness by 990701.Disclosure Encl ML20196J4161999-06-30030 June 1999 Discusses Relief Requests Submitted by Wisconsin Electric on 980930 for Pump & Valve Inservice Testing Program,Rev 5. Safety Evaluation Authorizing Relief Requests VRR-01,VRR-02, PRR-01 & ROJ-16 Encl NPL-99-0379, Documents Telcon with Hg Ashar of NRC Re Licensee Intentions & Basis for Reselection of Control Tendons in Pbnps Containment Structures.Plants Are Currently Completing 28th Year Tendon Surveillance During Summer of 19991999-06-29029 June 1999 Documents Telcon with Hg Ashar of NRC Re Licensee Intentions & Basis for Reselection of Control Tendons in Pbnps Containment Structures.Plants Are Currently Completing 28th Year Tendon Surveillance During Summer of 1999 NPL-99-0376, Forwards Errata to Pbnp 1998 Annual Monitoring Rept, Originally Submitted by Ltr Dtd 990427.List of Corrections, Provided1999-06-28028 June 1999 Forwards Errata to Pbnp 1998 Annual Monitoring Rept, Originally Submitted by Ltr Dtd 990427.List of Corrections, Provided NPL-99-0353, Forwards June 1999 Rev to FSAR for Point Beach Nuclear Plant,Units 1 & 2, IAW Requirements of 10CFR50.71(e).Each Package Contains Revised FSAR Pages That Are to Be Inserted IAW Instructions1999-06-23023 June 1999 Forwards June 1999 Rev to FSAR for Point Beach Nuclear Plant,Units 1 & 2, IAW Requirements of 10CFR50.71(e).Each Package Contains Revised FSAR Pages That Are to Be Inserted IAW Instructions ML20196D4931999-06-18018 June 1999 Forwards Insp Repts 50-266/99-08 & 50-301/99-08 on 990411- 0527.No Violations Noted.Operator Crew Response to Equipment Induced Challenges Generally Good.Handling of Steam Plume in Unit 1 Turbine Bldg Particularly Good ML20195J9471999-06-16016 June 1999 Discusses Ltr from NRC ,re Arrangements Made to Finalized Initial Licensed Operator Exam to Be Administered at Point Beach Nuclear Plant During Week of 990726 ML20196A2931999-06-16016 June 1999 Ack Receipt of Transmitting Changes to Listed Sections of Point Beach Nuclear Plant Security Plan & ISFSI Security Plan,Submitted IAW 10CFR50.54(p).No NRC Approval Is Required Since Changes Do Not Decrease Effectiveness ML20195J9251999-06-14014 June 1999 Discusses 990610 Telcon Between Wp Walker & D Mcneil Re Arrangements for NRC to Inspect Licensed Operator Requalification Program at Point Beach Nuclear Power Plant for Week of 990816 05000266/LER-1999-005, Forwards LER 99-005-00,re Failure of Shell of 4B FW Heater Which Resulted in Significant Steam Leak & Manual Trip. New Commitments within Rept Are Indicated in Italics1999-06-11011 June 1999 Forwards LER 99-005-00,re Failure of Shell of 4B FW Heater Which Resulted in Significant Steam Leak & Manual Trip. New Commitments within Rept Are Indicated in Italics NPL-99-0336, Forwards Unit 2 Refueling 23 Inservice Insp Summary Rept for Form NIS-1, IAW ASME Section Xi,Subsection IWA-62301999-06-10010 June 1999 Forwards Unit 2 Refueling 23 Inservice Insp Summary Rept for Form NIS-1, IAW ASME Section Xi,Subsection IWA-6230 NPL-99-0330, Forwards Revs to Pbnp Security Plan Sections 2.1,2.4,3.1, Figures A,D & T & Pbnp ISFSI Security Plan Section 2.0, Dtd 990604.Plans Withheld1999-06-0404 June 1999 Forwards Revs to Pbnp Security Plan Sections 2.1,2.4,3.1, Figures A,D & T & Pbnp ISFSI Security Plan Section 2.0, Dtd 990604.Plans Withheld 05000301/LER-1999-003, Forwards LER 99-003-00 for Point Beach Nuclear Plant,Unit 2. Rept Is Provided in Accordance with 10CFR50.73(a)(2)(i)(B), as Any Operation or Condition Prohibited by Plant Tech Specs1999-05-28028 May 1999 Forwards LER 99-003-00 for Point Beach Nuclear Plant,Unit 2. Rept Is Provided in Accordance with 10CFR50.73(a)(2)(i)(B), as Any Operation or Condition Prohibited by Plant Tech Specs NPL-99-0319, Provides Main Control Board Wiring Separation Project Status Update Rept for Pbnps,Units 1 & 21999-05-28028 May 1999 Provides Main Control Board Wiring Separation Project Status Update Rept for Pbnps,Units 1 & 2 ML20206T3691999-05-17017 May 1999 Ltr Contract,Task Order 242 Entitled, Review Point Beach 1 & 2 Conversion of Current TS for Electrical Power Systems to Improved TS Based on Standard TS, Under Contract NRC-03-95-026 ML20206N5561999-05-13013 May 1999 Informs That NRC Office of Nuclear Reactor Regulation Reorganized Effective 990328.As Part of Reorganization,Div of Licensing Project Mgt Created.Cm Craig Will Be Section Chief for Point Beach Npp.Organization Chart Encl ML20206P2551999-05-12012 May 1999 Forwards Handout Provided to NRC by Wisconsin Electric at 990504 Meeting Which Discussed Several Recent Operational Issues & Results of Recent Improvement Initiatives in Engineering ML20206N5331999-05-12012 May 1999 Forwards RAI Re & Suppl by Oral Presentation During 980604 Meeting,Requesting Amend for Plant,Units 1 & 2 to Revise TSs 15.3.12 & 15.4.11 ML20196F3211999-05-11011 May 1999 Requests Proprietary WCAP-14787, W Revised Thermal Design Procedure Instrument Uncertainty Methodology for Wepc Point Beach Units 1 & 2 (Fuel Upgrade & Uprate to 1656 Mwt-NSSS Power), Be Withheld from Public Disclosure ML20206K0391999-05-0707 May 1999 Forwards Insp Repts 50-266/99-06 & 50-301/99-06 on 990223- 0410.Ten Violations of NRC Requirements Occurred & Being Treated as non-cited Violations,Consistent with App C of Enforcement Policy 1999-09-08
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARNPL-99-0564, Forwards Response to NRC Request During 990720 Meeting,To Provide Addl Details to Several Questions Re Amend Currently Under Review by Staff Pertaining to CR Habitability1999-10-19019 October 1999 Forwards Response to NRC Request During 990720 Meeting,To Provide Addl Details to Several Questions Re Amend Currently Under Review by Staff Pertaining to CR Habitability 05000266/LER-1999-007, Forwards LER 99-007-00 for Point Beach Nuclear Plant,Unit 1. Condition Would Be Outside App R Design Basis for Plant.New Commitments within Rept Indicated in Italics1999-09-30030 September 1999 Forwards LER 99-007-00 for Point Beach Nuclear Plant,Unit 1. Condition Would Be Outside App R Design Basis for Plant.New Commitments within Rept Indicated in Italics NPL-99-0555, Discusses Rev 1,suppl 1 to GL 92-01, Reactor Vessel Structural Integrity. Calculation That Provides Evaluation of New Surveillance Data for Assessing Integrity of Unit 1 Reactor Vessel1999-09-29029 September 1999 Discusses Rev 1,suppl 1 to GL 92-01, Reactor Vessel Structural Integrity. Calculation That Provides Evaluation of New Surveillance Data for Assessing Integrity of Unit 1 Reactor Vessel 05000266/LER-1999-004, Forwards LER 99-004-01,re Fuel Oil Transfer Pump Cable in AFW Pump Room Being Outside App R Design Basis.Suppl to LER Provides Corrective Actions to Address Concerns Re Fire Disrupting Electrical Power to Fuel Oil Transfer Pump1999-09-0202 September 1999 Forwards LER 99-004-01,re Fuel Oil Transfer Pump Cable in AFW Pump Room Being Outside App R Design Basis.Suppl to LER Provides Corrective Actions to Address Concerns Re Fire Disrupting Electrical Power to Fuel Oil Transfer Pump NPL-99-0473, Informs of Change Being Made to Plan Third 10-year Interval ISI Long Term Plan.Change Extends Interval from Current End Date of 001130 to 020831,due to Operating Cycle Being Increased from 12 to 18 Months1999-08-27027 August 1999 Informs of Change Being Made to Plan Third 10-year Interval ISI Long Term Plan.Change Extends Interval from Current End Date of 001130 to 020831,due to Operating Cycle Being Increased from 12 to 18 Months 05000266/LER-1999-006, Forwards LER 99-006-00 Which Describes Discovery That Postulated Fire in Central Zone of Primary Auxiliary Bldg Could Result in Spurious Operation of Pressurizer Porv. New Commitments within Rept Are Indicated in Italics1999-08-19019 August 1999 Forwards LER 99-006-00 Which Describes Discovery That Postulated Fire in Central Zone of Primary Auxiliary Bldg Could Result in Spurious Operation of Pressurizer Porv. New Commitments within Rept Are Indicated in Italics NPL-99-0477, Forwards Revised Procedures to Point Beach Nuclear Plant Epips.Revised Procedures Dtd 990723,should Be Filed in NRC Copies of Manual IAW Attached Instructions1999-08-18018 August 1999 Forwards Revised Procedures to Point Beach Nuclear Plant Epips.Revised Procedures Dtd 990723,should Be Filed in NRC Copies of Manual IAW Attached Instructions NPL-99-0426, Requests Relief from Section II of ASME B&PV Code, Nuclear Vessels, 1965 Edition,No Addenda.Detailed Info Attached1999-08-16016 August 1999 Requests Relief from Section II of ASME B&PV Code, Nuclear Vessels, 1965 Edition,No Addenda.Detailed Info Attached NPL-99-0436, Forwards fitness-for-duty Performance Data for six-month Period Ending 9906301999-08-0202 August 1999 Forwards fitness-for-duty Performance Data for six-month Period Ending 990630 NPL-99-0406, Provides Response to NRC GL 99-02, Lab Testing of Nuclear- Grade Activated Charcoal1999-07-29029 July 1999 Provides Response to NRC GL 99-02, Lab Testing of Nuclear- Grade Activated Charcoal NPL-99-0408, Forwards Pbnps,Units 1 & 2 Plant Simulation Four-Yr Rept, IAW 10CFR55.45(b)(5)(ii).Rept Describes Certification Program Tests Conducted from 1996-1999,identifies Test Discrepancies Still Outstanding & Schedules for 2000-20031999-07-15015 July 1999 Forwards Pbnps,Units 1 & 2 Plant Simulation Four-Yr Rept, IAW 10CFR55.45(b)(5)(ii).Rept Describes Certification Program Tests Conducted from 1996-1999,identifies Test Discrepancies Still Outstanding & Schedules for 2000-2003 NPL-99-0395, Forwards Partial Response to NRC 990512 RAI Re TS Change 204 Re Control Room Habitability.Meeting Is Planned with NRC to Discuss Issues Related to Control Room & Primary Auxiliary Bldg Ventilation Sys Modifications1999-07-12012 July 1999 Forwards Partial Response to NRC 990512 RAI Re TS Change 204 Re Control Room Habitability.Meeting Is Planned with NRC to Discuss Issues Related to Control Room & Primary Auxiliary Bldg Ventilation Sys Modifications NPL-99-0390, Projects Listed Major near-term License Amend Requests That Could Be Expected to Impact Staff Resources Into Fiscal Years 2000 & 2001,in Response to Administrative Ltr 99-021999-07-0808 July 1999 Projects Listed Major near-term License Amend Requests That Could Be Expected to Impact Staff Resources Into Fiscal Years 2000 & 2001,in Response to Administrative Ltr 99-02 NPL-99-0388, Forwards MORs for June 1999 & Revised MORs for May 1999 for Pbnps,Units 1 & 21999-07-0707 July 1999 Forwards MORs for June 1999 & Revised MORs for May 1999 for Pbnps,Units 1 & 2 NPL-99-0381, Submits Response to NRC GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. GL 98-01 Requested Response on Status of Facility Y2K Readiness by 990701.Disclosure Encl1999-06-30030 June 1999 Submits Response to NRC GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. GL 98-01 Requested Response on Status of Facility Y2K Readiness by 990701.Disclosure Encl NPL-99-0379, Documents Telcon with Hg Ashar of NRC Re Licensee Intentions & Basis for Reselection of Control Tendons in Pbnps Containment Structures.Plants Are Currently Completing 28th Year Tendon Surveillance During Summer of 19991999-06-29029 June 1999 Documents Telcon with Hg Ashar of NRC Re Licensee Intentions & Basis for Reselection of Control Tendons in Pbnps Containment Structures.Plants Are Currently Completing 28th Year Tendon Surveillance During Summer of 1999 NPL-99-0376, Forwards Errata to Pbnp 1998 Annual Monitoring Rept, Originally Submitted by Ltr Dtd 990427.List of Corrections, Provided1999-06-28028 June 1999 Forwards Errata to Pbnp 1998 Annual Monitoring Rept, Originally Submitted by Ltr Dtd 990427.List of Corrections, Provided NPL-99-0353, Forwards June 1999 Rev to FSAR for Point Beach Nuclear Plant,Units 1 & 2, IAW Requirements of 10CFR50.71(e).Each Package Contains Revised FSAR Pages That Are to Be Inserted IAW Instructions1999-06-23023 June 1999 Forwards June 1999 Rev to FSAR for Point Beach Nuclear Plant,Units 1 & 2, IAW Requirements of 10CFR50.71(e).Each Package Contains Revised FSAR Pages That Are to Be Inserted IAW Instructions 05000266/LER-1999-005, Forwards LER 99-005-00,re Failure of Shell of 4B FW Heater Which Resulted in Significant Steam Leak & Manual Trip. New Commitments within Rept Are Indicated in Italics1999-06-11011 June 1999 Forwards LER 99-005-00,re Failure of Shell of 4B FW Heater Which Resulted in Significant Steam Leak & Manual Trip. New Commitments within Rept Are Indicated in Italics NPL-99-0336, Forwards Unit 2 Refueling 23 Inservice Insp Summary Rept for Form NIS-1, IAW ASME Section Xi,Subsection IWA-62301999-06-10010 June 1999 Forwards Unit 2 Refueling 23 Inservice Insp Summary Rept for Form NIS-1, IAW ASME Section Xi,Subsection IWA-6230 NPL-99-0330, Forwards Revs to Pbnp Security Plan Sections 2.1,2.4,3.1, Figures A,D & T & Pbnp ISFSI Security Plan Section 2.0, Dtd 990604.Plans Withheld1999-06-0404 June 1999 Forwards Revs to Pbnp Security Plan Sections 2.1,2.4,3.1, Figures A,D & T & Pbnp ISFSI Security Plan Section 2.0, Dtd 990604.Plans Withheld NPL-99-0319, Provides Main Control Board Wiring Separation Project Status Update Rept for Pbnps,Units 1 & 21999-05-28028 May 1999 Provides Main Control Board Wiring Separation Project Status Update Rept for Pbnps,Units 1 & 2 05000301/LER-1999-003, Forwards LER 99-003-00 for Point Beach Nuclear Plant,Unit 2. Rept Is Provided in Accordance with 10CFR50.73(a)(2)(i)(B), as Any Operation or Condition Prohibited by Plant Tech Specs1999-05-28028 May 1999 Forwards LER 99-003-00 for Point Beach Nuclear Plant,Unit 2. Rept Is Provided in Accordance with 10CFR50.73(a)(2)(i)(B), as Any Operation or Condition Prohibited by Plant Tech Specs ML20196F3211999-05-11011 May 1999 Requests Proprietary WCAP-14787, W Revised Thermal Design Procedure Instrument Uncertainty Methodology for Wepc Point Beach Units 1 & 2 (Fuel Upgrade & Uprate to 1656 Mwt-NSSS Power), Be Withheld from Public Disclosure NPL-99-0242, Submits Commitment Schedule Update,Per GL 95-07 Re Pressure Locking & Thermal Binding of safety-related power-operated Gate Valves.Unit 1 Block Valve Replacement Will Be Performed During Upcoming 1999 U1R25 Outage1999-04-27027 April 1999 Submits Commitment Schedule Update,Per GL 95-07 Re Pressure Locking & Thermal Binding of safety-related power-operated Gate Valves.Unit 1 Block Valve Replacement Will Be Performed During Upcoming 1999 U1R25 Outage NPL-99-0246, Forwards 1998 Annual Monitoring Rept, for Pbnps Units 1 & 2.Revised ODCM & Environ Manual Are Encl1999-04-27027 April 1999 Forwards 1998 Annual Monitoring Rept, for Pbnps Units 1 & 2.Revised ODCM & Environ Manual Are Encl ML20206C2361999-04-22022 April 1999 Forwards 1998 Annual Rept to Stockholders of Wepc Which Includes Certified Financial Statements,Per 10CFR50.71 NPL-99-0230, Submits Clarification of Which Portions of OMa-1988 Parts 6 & 10 Are Being Utilized at Pbnp for IST Program Implementation & Cold SD & RO Justifications,Per 990218 Telcon with NRC1999-04-19019 April 1999 Submits Clarification of Which Portions of OMa-1988 Parts 6 & 10 Are Being Utilized at Pbnp for IST Program Implementation & Cold SD & RO Justifications,Per 990218 Telcon with NRC 05000301/LER-1999-002, Forwards LER 99-002-00 Re Discovery That Cable Necessary to Provide Plant Parameter Required to Be Monitored for App R Safe SD Location Was Not Routed Independent of Appropriate Fire Zone.Commitments in Rept Indicated in Italic1999-04-16016 April 1999 Forwards LER 99-002-00 Re Discovery That Cable Necessary to Provide Plant Parameter Required to Be Monitored for App R Safe SD Location Was Not Routed Independent of Appropriate Fire Zone.Commitments in Rept Indicated in Italics NPL-99-0219, Provides Final Notification of Change to Commitments Documented in LER 266/97-022-00 Re Electrical Short Circuits During CR Fire1999-04-15015 April 1999 Provides Final Notification of Change to Commitments Documented in LER 266/97-022-00 Re Electrical Short Circuits During CR Fire 05000266/LER-1999-001, Forwards LER 99-001-01,describing Discovery That Common Min Recirculation Flow Line Return to RWST for Safety Injection & Containment Spray Pumps Was Partially Frozen & Would Not Pass Flow.New Commitments Indicated in Italics i1999-04-0808 April 1999 Forwards LER 99-001-01,describing Discovery That Common Min Recirculation Flow Line Return to RWST for Safety Injection & Containment Spray Pumps Was Partially Frozen & Would Not Pass Flow.New Commitments Indicated in Italics in Rept NPL-99-0174, Confirms Completion of Requested Actions in Accordance with Required Response of GL 96-01 for Unit 2.Confirmation of Completion for Unit 1 Was Provided in Ltr Npl 98-0591,dtd 9807141999-03-30030 March 1999 Confirms Completion of Requested Actions in Accordance with Required Response of GL 96-01 for Unit 2.Confirmation of Completion for Unit 1 Was Provided in Ltr Npl 98-0591,dtd 980714 ML20206B8231999-03-30030 March 1999 Forwards Final Exercise Rept for Biennial Radiological Emergency Preparedness Exercise Conducted on 981103 for Point Beach Power Plant.One Deficiency Identified for Manitowoc County.County Corrected Deficiency Immediately NPL-99-0177, Forwards Decommissioning Funding Status Info for Pbnp,Units 1 & 2,per 10CFR50.751999-03-30030 March 1999 Forwards Decommissioning Funding Status Info for Pbnp,Units 1 & 2,per 10CFR50.75 05000301/LER-1999-001, Forwards LER 99-001-00,re Loss of Safeguards Electrical Bus During Refueling Surveillance Testing Which Resulted in Temporary Unavailability of One Train of Decay Heat Removal. Commitments Made by Util Are Identified in Italics1999-03-10010 March 1999 Forwards LER 99-001-00,re Loss of Safeguards Electrical Bus During Refueling Surveillance Testing Which Resulted in Temporary Unavailability of One Train of Decay Heat Removal. Commitments Made by Util Are Identified in Italics NPL-99-0122, Forwards Relief Requests RR-1-19 & RR-2-25,requesting Relief from Section XI of ASME B&PV Code, Rules for Inservice Exam of NPP Components, 1986 Edition,No Addenda.Requirements for Relief Apply to Third ten-yr ISI Interval for Units 1 &1999-03-0303 March 1999 Forwards Relief Requests RR-1-19 & RR-2-25,requesting Relief from Section XI of ASME B&PV Code, Rules for Inservice Exam of NPP Components, 1986 Edition,No Addenda.Requirements for Relief Apply to Third ten-yr ISI Interval for Units 1 & 2 NPL-99-0111, Informs NRC That IAW Provisions of ASME Boiler & Pressure Code,Section Xi,Paragraphs IWA-2430(d) & IWA-2430(e),WEPC Has Extended Third 10 Yr Interval for Pressure Testing Program at Pbnp,Unit 1 by 21 Months1999-03-0303 March 1999 Informs NRC That IAW Provisions of ASME Boiler & Pressure Code,Section Xi,Paragraphs IWA-2430(d) & IWA-2430(e),WEPC Has Extended Third 10 Yr Interval for Pressure Testing Program at Pbnp,Unit 1 by 21 Months NPL-99-0116, Forwards Proprietary & non-proprietary Revised Point Beach Nuclear Plant Emergency Plan IAW 10CFR50.54(q).Proprietary Plan Withheld1999-03-0101 March 1999 Forwards Proprietary & non-proprietary Revised Point Beach Nuclear Plant Emergency Plan IAW 10CFR50.54(q).Proprietary Plan Withheld NPL-99-0115, Forwards Proprietary & non-proprietary Revised EPIPs to Point Beach Nuclear Plant,Units 1 & 21999-03-0101 March 1999 Forwards Proprietary & non-proprietary Revised EPIPs to Point Beach Nuclear Plant,Units 1 & 2 NPL-99-0114, Provides Results of Wepcs Insp,Replacement & Mechanical Testing of Reactor Internals Baffle Former Bolts During Recent Point Beach Refueling Outage1999-02-25025 February 1999 Provides Results of Wepcs Insp,Replacement & Mechanical Testing of Reactor Internals Baffle Former Bolts During Recent Point Beach Refueling Outage NPL-99-0086, Documents Commitment Change Which Is to Discontinue Actions Contained in Util Ltr Dtd 970613,after NRC Approval of LAR & Lower Containment Leak Rate Limit Is Implemented. Change Is Acceptable IAW Applicable Plant Procedure1999-02-24024 February 1999 Documents Commitment Change Which Is to Discontinue Actions Contained in Util Ltr Dtd 970613,after NRC Approval of LAR & Lower Containment Leak Rate Limit Is Implemented. Change Is Acceptable IAW Applicable Plant Procedure NPL-99-0101, Forwards Proprietary & non-proprietary Version of Rev 20 to EPIP 3.2, Emergency Response Organization Notification & Revised Index.Proprietary Info Withheld1999-02-19019 February 1999 Forwards Proprietary & non-proprietary Version of Rev 20 to EPIP 3.2, Emergency Response Organization Notification & Revised Index.Proprietary Info Withheld ML20203F7301999-02-10010 February 1999 Forwards Revs to Security Plan Sections 1.2,1.3,1.4,2.1,2.5, 2,6,2.8,6.1,6.4,6.5,B-3.0,B-4.0,B-5.0 & Figure R Dtd 990210. Evaluation & Description of Plan Revs Also Encl to Assist in NRC Review.Encls Withheld NPL-99-0067, Submits 30 Day Rept of Changes & Errors Discovered in ECCS Evaluation Models for Pbnp,Unit 21999-02-0202 February 1999 Submits 30 Day Rept of Changes & Errors Discovered in ECCS Evaluation Models for Pbnp,Unit 2 NPL-99-0064, Forwards Revised TS Bases Page 15.4.4,correcting References to Pbnp FSAR Re Reactor Containment Design.Changes Are Administrative Only & Do Not Alter Facility or Operation,As Described in FSAR or Any TS Requirement1999-02-0202 February 1999 Forwards Revised TS Bases Page 15.4.4,correcting References to Pbnp FSAR Re Reactor Containment Design.Changes Are Administrative Only & Do Not Alter Facility or Operation,As Described in FSAR or Any TS Requirement NPL-98-1032, Forwards Revs to Pbnp Security Plan Sections 1.1,1.2,2.1, 2.6,2.8,6.1 & 6.4 & Revs to Pbnp ISFSI Security Plan Sections 1.0 & 7.0,per 10CFR50.54(p).Encl Withheld1999-01-27027 January 1999 Forwards Revs to Pbnp Security Plan Sections 1.1,1.2,2.1, 2.6,2.8,6.1 & 6.4 & Revs to Pbnp ISFSI Security Plan Sections 1.0 & 7.0,per 10CFR50.54(p).Encl Withheld 05000266/LER-1998-029, Forwards LER 98-029-00,describing Discovery of Isolation of Autostart Feature for Svc Water Pumps from Unit 2,safeguards Buses During Modifications1999-01-26026 January 1999 Forwards LER 98-029-00,describing Discovery of Isolation of Autostart Feature for Svc Water Pumps from Unit 2,safeguards Buses During Modifications NPL-99-0031, Informs That Wepc Reviewed Contents of NEI to NRC & Have Verified Info Provided in Ltr Pertaining to WOG Member Plants Is Applicable to Pbnp.Attachment Responds to NRC Questions by Ref to Info in 981211 NEI Ltr1999-01-15015 January 1999 Informs That Wepc Reviewed Contents of NEI to NRC & Have Verified Info Provided in Ltr Pertaining to WOG Member Plants Is Applicable to Pbnp.Attachment Responds to NRC Questions by Ref to Info in 981211 NEI Ltr NPL-99-0004, Provides Status Update on Program Activities & Schedule for Final Resolution of Items Re Verification of Seismic Piping Class Interfaces for Point Beach Nuclear Plant,Units 1 & 21999-01-11011 January 1999 Provides Status Update on Program Activities & Schedule for Final Resolution of Items Re Verification of Seismic Piping Class Interfaces for Point Beach Nuclear Plant,Units 1 & 2 NPL-99-0012, Forwards Proprietary & Nonproprietary Revs to Epips. Proprietary Version of EPIPs Withheld1999-01-0808 January 1999 Forwards Proprietary & Nonproprietary Revs to Epips. Proprietary Version of EPIPs Withheld 1999-09-30
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' Electnc PONER COMPANY Point (koch Nuclear Pkant 6510 tJunior Rd .1 o Rwrt VA 54241 (414) 755 2329 JVO c t*T yp. 10 - L 6 &
PBL 90-0128 April 30, 1990 Mr. Warren Svenson, Project Manager Project Directorate 111-3 1 Whiteflint North 11555 Rockville Pike Rockville, MD 20852
Dear Mr. Svenson:
RPV UNIT 1 VESSEL INDICATIONS On April 27, 1990, a conference call between Wisconsin Electric and th9 NRC took place to discuss the indications found in the Unit I reactor vessel outlet nozzles during the spring 1990 exam. The individuals in attendance are listed on Attachment 1.
As a result of the conference call, the NRC requested and we agreed to provide specific information concerning the code rejectable indications found in the Unit I reactor vessel outlet nozzle-to-shell welds. This infcrmation is provided as Attachment 2.
Based on the discussions between yourself and Hessrs. Elliot, Hum, and Koo of the NRC, we understand that there is no restart issue as long as the indications can be shown to be acceptable by the Handbook of Flaw Indications for Point Beach Units 1 and 2. WCAP-11477, dated June 1987.
This letter and its attachments constitutes the informal transnittal of information you requested, A formal transmittal will be provided to the NRC, via the Public Document Room, within 60 days following the Unit 1 critic lity.
If further information is required or your would like to have a follovup meeting or conference call, let us know as soon as possible.
Very truly yours, hMSY
~
J. J. Zach
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ADOCK 05000266 PDR A wbsWan WIWvasin Dm On7aata q.j [, \ I g g b
'$ s PBL 90-0128 Attachment I ATTENDEES OF APRIL 27, 1990 PHONE CONFERENCE WISCONSIN ELECTRIC J. F. Kohlwey G. R. Sherwood T. G. Malanowski NUCLEAR REGULATORY COMMISSION Warren Swenson Barry Elliot Martin Hum "ill Koo SOUTHWEST RESEARCH INSTITUTE Bill Clayton Hector Diaz Harvey Enoch Roy Niemeyer l
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l TABLE OF CONTENTS
- 1.0 Introduction 1
2.0 Scope of 1990 Unit 1 Examination
- 3.0 Preliminary Results f 4.0 Description of Equipment Failureo 5.0 Evaluation of outlet Nozzle-to-Shell Welds-i i
<- Attachments 2A 1990 Exam Sizing Parameters
! 2B Indication Sizing for Outlet Nozzles A and C ,
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2C Summary of Indications (Historical Correlation) i 2D RPV Nozzle Examination Parameters f 2E Flaw Handbook Plots 4
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1 PBL 90-0128 Attachment 2 Page 1 .
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. 1990 POINT BEACH NUCLEAR PLANT l UNIT 1 REACTOR VESCEL EXAMINATION d
1.0 INTROD'JCTION ,
1 In 1984 Wisconsin Electric Power Company contracted with Southwest Research Institute to examine portions of the Point Beach Nuclear Plant Unit 1
- reactor vessel. During this e'x amination, flaws in the outlet nozzle-to-
- shell welds were identified which were sized in excess of ASME Code section XI allowable limits. These were addressed in Licensee Event Report (LER) No. 84- '2 dated March 28, 1984. ,
2 In 1987 Wisconsin Electric Power Company-again contracted with Southwest Research Institute to cvamine the Point Beach Nuclear Plant Unit 1 reactor
- vessel including-the outlet nozzle-to-sSell welds. The flaws identified Jn i 1984 were again identified and remained essentially unchanged. Part of the 1987 examination was the SI nozzle-to-shell welds. Flaws were identifjed in the SI nozzle-to-shell weld. The evaluation was submitted by our letter
, dated June 2, 1987.
y i
Based on the requirements of ASME-Code.Section XI and the Nuclear Regulatory Commission evaluation of our previous examinations, Wisconsin Electric Power Company planned to ultrasonically examine the outlet J. nozzle-to-shell and SI nozzle-to-shell weld: during our Unitsl. spring 1990-
- refueling outage. This examination was performed by Southwest Research e Institute utilizing the Program and Remote (par) device and the SWRI Enhanced
! Data Acqu M. tion System (EDAS).
i 2.0 SCOPE OF 1990 UNIT 1 EXAMINATION
~
The 1990 examination plan was first to ultrasonically examine the two (2) outlet nozzle-to-shell welds and the two (2) SI nozzle-to-shell welds 'using ASME Code. techniques and then reexamine identified flaws with refined flaw sizing techniques. The refined sizing techniques-vere to be thosez demonstrated to..the NRC at Southwest Research Institute's facilities in January 1989. .
The SWRI Scan Plan provided similar examination techniques to' those. utilized 1
in 1984.and 1987 (Attachment-2D)._ The data analysis system was upgraded-to'use the SWRI EDAS. These initial techniques were:in accordance with ASME Code Section XI 1977 edition with Summer 1979 Addenda'and, Regulatory
. Guide 1.150, Revision 1. The plan provided a second phase to examine identified flaws with-focused beam transducers to define more realistic flaw sizes, e
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Page 2 3.0 PRELIMINARY RESULTS The examination of the 51 noczle-to-shell welds was conducted as planned.
The flaws i&Alified in 1987 were . identified and sized.- All of the flaw '
sizes are within ASME Code Section XI limits.
t The examination of the outlet nozzle-to-shell welds were examined with code techniques as planned'but equipment failures prevented subsequent sizing- ,
with focused beam transducers; Tip diffraction techniques were applied to ,
these welds but the results were inconclusive. ,
Preliminary size data for the outlet nozzle-to-shell welds-bastd on the ,
ASME Code techniques were as_follows: '
a Outlet Nozzle #RPV-2-686-A
- F1tw at 334.49 deg. nozzle azimuth-exceeded code limits.
- 2a = 1.07" j 1 = 2.61" -;
s = 3.17"'
- a/t '= 5.70%
! Hax, a/t = 3.30%
l Outlet Nozzle #RPV-2-686-C
- Five (5) flaws at 237.3'deg. nozzle azimuth sized as -
one (1) flaw exceeded code limits. ,
2a = 1.52"
- 1 = 5.63" s = 2.71" a/t = 8.09% >
' Hax a/t = 2.7C%
s Fou" (4) flaws' at 304.31 deg. nozzle azimuth sized as -
- one (1) flaw exceeded code limits.
4- 2a- =-1.40"
= 6.36" 1 !
s = 3.48" a/t = 7.45" Max. a/t = 2.90" The preliminary information 'above was communicated to the NRC via phone on -
April 27,;1990. At the time of the phone call, data' analysis.and review was. -
still in progress. More detailed flaw descriptions Lave subsequently been prepaied.and.are attached. The above indication sizesLhave changed due to the refined analysis techniques used. Specific indication sizes can-be found in Attachment 2A. '
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PBL 90-0128 Attachment i Page 3
4.0 DESCRIPTION
OF EQUIPMENT FAILURES / PROBLEMS The 199^ examination was conducted with the lower internals in place.
Access to the outlet nozzle-to-shell and 51 nozzle-to-shell welds was through openings in the core barrel. This limited the examination--to be performed by scanning from the nozzle bore.
No significant problems were encountered during the ASME Code scan portion of the project. The focused ultrasonic transducer designed for the SI nozzle-tu-shell weld performed as expected.
Problems occurred during the scan partion which was intended to use focused transducers designed for the outlet nozzle geometry. Two transducers have been manufactured by SWRI. These had previously been utilized at Rochester Gas and Electric's1Ginna Plant-in 1989. One of the transducers was not capable of calibration upcn unpackaging at Point-Beach. The-second tran=dacer was successfully calibrated and mounted for sizing the -
outlet nozzle-to-shell welds flaws. Partially through the scan of the first flaw, this second transducer developed an internal electrical fault.
No replacement transducers were readily available. No further. focus beam scanning was possible since no spare transducers were available.
5.0 EVALUATION OF OUTLET N0ZZLE-TO-SHELL WELD FLAWS The attached provides a detailed description of the'the three (3) outlet nozzle-to-shell weld flaws which had preliminary sizing results exceeding-ASME Code allowable. These are identified as Indication No. 6 for weld RPV-2-686-A and Indication Nos. 2 and 5 for weld RPV-2-686-C. Each indication is composed of several small flaws in close proximity. Each individual flaw has been sized and depicted as a rectangle'as-provided in -
the ASME Code. Attachment 2B is a description of the sizing and Attachment 2C is a correlation with previous examinatic . .
It should be noted that the rules of ASME Section XI have been applied to determine if flaws should se combined or treated separately. -Using these rules, Indication No. 2 in RPV-2-686-C is evaluated as two (2)' separate flaws exceeding the ASME Code allowable a/t ratio, Wisconsin Electric Power company has plotted each of these flaws in accordance with the Westinghouse Flaw Evaluation Handbook Point Beach Units 1 and 2' Reactor Vessels (WCAP-II477). Copies of these plots are-in Attechment 2E. Based upon the plots, Wisconsin Electric Power Company-
-has determined that'all of these flaws will be acceptable by-fracture mechanics as provided in IWB-3600 OfzASME Code Section XI.
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. ATTAC!!M' J NT 2) D PT BEACH UNIT 1 OUTLET NOZZLE RPV-2-686-A 1990 EXAM SIZING PARAMETERS _ INDICATION NO. 6 2a = 0.49 " Reflector A at 329.7 de0rees I= 0 51
a= 0.2S "
S= 3.28 t - clad = 9.4 att = 2.61 %
all = 0.48 i alt max = 6.26 %
2a = 0.20 " Reflector B at 331.5 degrees I= 0.41 nozzle azimuth. -
i a= 0.10 *
. S= 3.56
- i t - clad = 9.4 "
alt = 1.06 %
all = 0.24 i alt max = 3.62 %
, 2a = 0.86
- Reflector C at 334.9 degrees -
!= 1.92 " nozzle azimuth. Sized at a= 0.43 " 1/2 max amplitude for 2a.
j S= 3.12 t - clad = 9.4
all = 0.22 alt max = 3.46 %
2a = 0.86 " Reflector 60 at 334.5 riegrees I= 2.42 " nozzle azimuth. Sized at a= 0.43
- 1/2 max amplitude for 2a. This S= 3.12 flaw is 2 flaws sized as one, t - clad = 9.4 * (Flaws B and C combined) alt = 4.57 %
all = 0.18
, alt max = 3.14 %
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. Page 5 PT BEACH UNIT 1 OUTLET NO22LE RPV-P.-686-C 1990 EXAM SIZING PARAMETERS INDICNDON NO. 5 2a = 1.10
- Reflector A at 304.3 degrees I= 1.07
- nozzle azimutn. Sized at a= 0.55 " 1/2 max amplitude for 2a.
S= 3.64 t - clad = 9.4
all = 0.50 alt max = S.5 %
2a = 0.81 Reflector 8 at 309.2 de0rees I= 1.2d nozzle azimuth. Sized at a= 0.41 "
1/2 max amplitude for 2a.
S= 3.89 1 t - c'ad = 9.4 "
., a/t= 4.31 %
e all = 0.33 a/t may = 4.4 %
s 2a = 0.77
- Reflector C at 313.4 dogrees ,
I= 1.46 " nnzzle azimuth. Sized at a= 0.3P
- 1/2 max amplitude for 2a.
S= 3.85 j t - clad = 9.4 alt = 4.10 %
all = 0.26 alt max = 3.78 %
_. 2a = 0.45 " Reflector D at 316.7 degroes I= 0.49
- nozzle azimuth, a= 0.23 "
- S= 3.96 I- clad = 9.4
i all = 0.40 alt max = 6.02 %
i 2a = 1.10 " Indication SE al 304.3 degrees I= 5.02
- no:zle azimuth. Sized at a= 0.55
- 1/2 max amplitude ter 2a. This S= 3.64 flaw is 3 flaws sized as one.
t - clad = 9.4 " (Flaws A, B, C combined) alt = 5.85 %
all = 0.11 alt max = 2.66 %
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- _ _ _ _ _ _ _ _ _ _ _ _ a i= g l
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Pt Beo.ch 1 Excm 4R'6 -5 1 Inci No' 5D & 5E '
---- i
""** 30 Apr 90 a _ _
R P \f 6 8 6 _G. ls
Attachn.ent 2A Page 9 PT BEACH UNIT 1 OUTLET NOZZLE RPV-2-686-C 1990 EXAM SIZING PARAMETERS INDICATION NO 2 2a = 0.74
- Reflector A at 237.3 degrees I= 1.07
- nozzle azimuth a= 0.37
- S= 3.01 1 - clad = 9.4 alt = 3.94 %
all = 0.35 a/t max = 4.6 %
2a = 0.53 " Reflector 8 at 239.3 degrees I= 0.57
- nozzle azimuth, a= 0.27
- S= 3.22 i
t - clad = 9.4 "
alt = 2.82 %
all= 0.46 alt max = 6.01 %
Ea = 0.88
- Reflector C at 241.9 degrees I= 0.89
- nozzle azimuth.
a= 0.44
- S= 3.22 1-c'TJ= 9.4 alt = 4.68 %
all = 0.49 alt max = 6.38 %
2a = 0.81 Reflector D at 246.1 degrees I= 0.58 " nozzle azimuth, a= 0.41
- S= 2.75 t - clad = 9.4
- alt = 4.31 %
all= 0.50 alt max = 6.5 %
2a = 0.50
- Indication E at 24E1 degrees I= 0.25 " nozzle azimuth, a= 0.25 '
S= 2.71 t - clad = 9.4
all = 0.50-alt max = 6.5 %
i
.. . . . _ _ _ _ _ _ _ _ _ - - . . _ _ _ _ - - - . - - - J
" Attachment 2A
,, Page 10
- PT BEACH UNIT 1 OUTLET NOZZLE RPV-2-686-0 1990 EXAM SIZli 'ARAMETERS INDICATION NO. 2 I 2a = 0.97 ' . Indication 2F at 237.3 degroes I= 3.2
- nozzle azimuth. This flaw is
- a= 0.49
- S= 3.01 (Haws 2A,28,20 combined) t - clad = 9.4 "
alt = 5.16 %
! all = 0.15 alt max = 2.9 %
$ 2a = 0.94
- Indication 2G at 246.1 degress I- 1.40
- nozzle azimuth. This flaw is I
a= 0.47
S= 2.69 (Flaws 2D and 2E combined) t - clad = 9s" alt = 5.00 %
all = 0.32 4 alt max = 4.3 ' 4 l
t d
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Ind. Dimension 3 ia Ind.
No.
2a a i s "
L-- _
kG A .74 .37 1.07 3.01 F l B .53 .27 .57 3.22 C .88 .44 .89 3.32 D .81 .41 .58 2.81 E .5 .25 .5 e.71 6.63 6.07 <; 95 6.19 F .97 .49 3.2 3.01 i s.63 G .94 .47 1.46 2.69 2
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site- Pt. Beach 1 }} n o , \ O, ._____ _Ex ap__# 4 R L._ _
"**- 28 Apr 90 2F~l 2G RPV-2-686-C
4 '
ATTACHME!1T 2D Pt. Beach Unit 1 April 29,1990 Indication Sizing For Outlet Nozzles "A" and "C" In 1990 three indications were preliminarily sized as rejectable in outlet nozzles "A" and "C". Two of these were in nozzle "C" and one was in nozzle "A". After a more extensive review, these three
, Indications were re-sized and in some cases separated into several
- indications. During this review it was determined that instead of three rejectable indications there were four, but of somewhat smaller 3 dimensions.
Nozzle "A" The rejectable indication in outlet nozzle "A" was located at a nozzle azimuth of 334.5 degrees with an amplitude of 347% DAC. This indication actually consisted of two reflectors which, when compared with Tig. IWA-3330-1 of ASME Code Section XI, 1977 edition with Addenda through the summer 1979, must be sized as one. This indication was i
preliminarily sized to 50% DAC in both the length and through wall dimension which yielded a "2a" dimension of 1.07" and length ("1") of 2.42".
Section V, 1977 S79 Addenda paragraph T-441.8.2 (3) (4) states that the through-wall dimension for reflectors exceeding 100% DAC shall be recorded at the 50% maximum amplitude positions. Paragraph T-4 41. 8. 2 ( 5 ) states the length dimension shall be recorded at the 50%
DAC positions for each end of the reflector.
Based on this information, the preliminary sizing was considered to be in error and the indication was re-sized to the proper criteria.
The re-sized indication has the dimensions of u 16" for "2a" and an "1" i of 2.42". This indication exceeds the allowablo limits of Section XI 1977 Summer 79 Addenda table IWA-3512-1.
Hpzzlo "C" one of the rejectable indications detected in outlet nozzle "C" was located at a nozzle azimuth of 237.3 degrees w_th an amplitude of 139% DAC. This indication was preliminarily sized by including five reflectors which were in close proximitf and determining the through-wn'1 and length dimecsions at 50% DAC. This indication as preliminarily sizad D.A 1 through-vall "2a" of 1.49" and a length "1" of 5.63".
l
" Attacimwnt 2B
~
,, Page 2 Indication Sizita For Outlet Nozzles "A" and "C" Page 2 A careful review of the grouping criteria of Fig. IWA-3330-1 1977 Section XI Summer 79 Addenda indicates that these five reflectors should be sized as two indications instead of one. One of these indications consists of three reflectors with a max amplitude of 139%
DAC, and the other consists of two reflectors with an amplitude of 92%
DAC. Considering that the amplitude of the larger of the indications was in excess of 100% DAC, the through-wall sizing was recalculated using the 50% maximum positions instead of 50% DAC. The=re-sized indication "1" of consists of three reflectors and has a "2a" of 0.97" and an 3.2".
The indication consisting of two reflectors has a "2a" of 0.94" and an "1" of 1.46". Both indications exceed the allowable limits defined by Table IWA-3512-1.
The second indication in outlot nozzle "C" preliminarily sized as rejectable was located at 304.3 degrees. This indication consisted of four reflectors grouped as one with a maximum amplitude of 255% DAC, a "2a" of 1.37" and an "1" of 6.36".
Again, a revieti of the grouping criteria of fig IWA-3330-1 indicates that the four reflectors should be considered two jndications with the larger of the two containing three of the reflectors. The larger of the two indications with an-amplitude of-139% DAC was sized to the 50% maximum criteria for the through-wall dimension and 50% DAC ,
for the length dimensions. The dimensions of this indication are "2a"
= 1.10" and "1" = 5.02". This indication is still exceeds the allowable limits specified in Section XI 77 S79 Addenda table IWB-3512-1.
The second indication consisting of one reflector is acceptable, s
,. ATTACllME!1T 2C l
SUMMARY
OF INDICATIONS Outlet Nozzle "A" 4
Y Ext from
- Flaw Azimuth (X) 1984 1987 1990 BPV C. L. ME 45 X X X 64 7.1
- 60 X NOT SEEN X 67.5 9.1 102.5 X X X 67.68 9.2
- 104 R R X 66.2 7.7 104.7 X X X 66.2 7.7 104.8 X X X 66.2 7.7 106.5 X X X 65.28 9.45 107 X X X 64 9.08 109 X X X 63.8 9.03 112.5 X X X 62.9 8.72 218 X X X 67 7.6 233 X X X 67.42 8.79 235 X X X 67.3 8.79
~
237 X X X 67.48 7.8 329.7 X X X 67 16 8.68
, f 334.5 X X R 67.5 8.68 339.5 X X X 68.28 8.58
)
- This indication was sized as rejectable in 1984 and 1987 but acceptable in 1990. Basis for the 1990 acceptability is a = 0.44" with c.n af t% of 4.68 and an 1 of 0.61 which yields ar. a/1 of .5 and an acceptable a/t% of 6.5. The 1984 and 1987 sizing was based on combin-ing 2 indications. The data taken in 1990 showed these to be separated sufficiently to be sized as individual indications.
i This indication is sized in 1990 as rejectable and includes the indication reported in 1984, at 339.54 Deg. The 1987 data detected the indication at 80% of DAC but had no analysis scans.
R denotes Rejectable indication.
i
,, Attachment 2C
.. Page 2 s
SUMMARY
OF INDICA"' IONS Outlet Nozzle "C" Y Ext from .
Flaw Azimuth 1984 1987 110.Q RPV C. L. BE I
211 X X X 69.01 8.0 222.5 X X X 68.06 8.19 i
236 X X X 69.02 7.82
% 237.3 X X R 69.02 7.82
]
& 246 X X X 69.02 7.82
& 249 X X X 69.02 7.82 l l
*0# 311 R X X 68.91 8.01
*# 314 X R X 68.91 8.01
*0 316 X X X 68.91 8.01
*0 319 X X X 68.91 8.01
*0 321.5 X X X 68.91 8.01 The detection examination in 1990 located an indication'at 304.3 deg. which includes all of these indications. The 1990 sizing of the rejectable indication includes 3 reflectors sized as 1, which are 304.31, 311, & 314 degrees.
9 In 1984 these 4 indications were sized individually. The indica-tion at 311 was sized as rejectable.
# In 1987 a flaw was sized as rejectable at 314 deg which included the indication at 311 degrees. ~ The sizing was based on the two flaws being in close proximity and therefore considered one flaw.
% The rejectable indication in 1990 as sized includes the indica-tion found in 1987 at 236 degrees. The 236 degree indication found in 1987 was detected at 160% DAC but no analysis scans were run.
& These indications were sized individually in 1984.
R denotes-Rejectable Indic1tions.
i
. , -- ._ - . .- .- - ~ . ~ -- . . .
Attachmerit SC Page 3
SUMMARY
OF IriDICATIONS Safety Injection Nozzle "A" Y Ext from Flaw Azimuth 1102 1990 RPV C. L. 1E O R X 10.80 5.75 L t 11 X X 72.28 5.89 26 R X 73.C4 6.87
~
40 R X 68.00 5.53
'g 43 X X 58.00 5.53 h' 60 X X 73.96 6.87 166 X X 70.40 4.67 '
172 X X 73.92 6.78
- 180 >* X 73.92 6.78 L 215 X X 73.92 61 '" ,,
221 NOT SEEN X 71.04 5.
230 X 72.00 6.75 283 NOT SEEN X 6.56 4.6 NOT SEEN X 71.72 5.17 R unnotes Rejectablo indications
ATTACMIENT 2D l PT BE CH UNIT 1 RPV NOZZLE EXAMIN TlON PARAMETERS OUTLET NOZZLE A 1984 1932 0 193_0 SEARCH UNIT SIZE Detection 1.0" rd,2.25 mhz - 1.0' rd,2.25 mhz 1.0" rd,2.25 mb7 Sizing 1.0" rd,2.25 mhz - 1.0' rd,2.25 mhz. 1.0" rd,2.25 mhz SCANNING INCREMENT Detection 0.6 * 'O.7" 0.75" Sizing 0.21' 0.1 " 0.1 "
SCANNING DIRECTION Detection Circumferential Circumferentici Circumferential-Sizing Axial Axial . - Axial 9UTLET NOZZLE C 1984 1987 1990 SEARCH UNIT SIZE Detection 1.0" rd,2.25 mhz 1.0' rd,2.25 mhz 1.0' rd,2.25 mhz Sizing 1.0" rd,2.25 mhz
. 1.0" rd,2.25 mhz ' 1.0" rd,2.25 mhz ,
SCANNING INCREMENT '
Detection 0.6' O.7 * ' O.75 ~
Sizing - 0. 21." - 0.1 " 0.1 "
, SC/ NNING DIRECTION Detection Circumferential Circumferential -- Circumferential -
Sizing Axial Axlal- Axial - -
1987 1990 SAFETY INJECTION NOZZLE A SEARCH UNIT SIZE
. Detection 0.5' rd,2.25 mhz? 0.75" rd,2.25 mhz Sizing 0.5' rd,2.25 mhz 0.75*. rd,2.P' inhz /1' A3' focused -
SCANNING INCREMENT l Detection : 0.3 * '
O.2f(at w$1d cl)
Sizing - 0.3"?
- 0.25' (Cooe) / 0.05" (focused)
SCANNING DIRECTION - -
Detection : Circumferential - ' Axial
- S' zing _ Circumfereatial' . Axial t
, . +_ -.e - .yn.,.
~
. ~ t
- Attachment 2E Page 1 OUTLET NOZZLE RPV-2-686-A INDICATION NO. 6 i
SURFACE / EMBEDDED !
FLAW DEM ARTATION LINE .
0.13 . . .... .
a . . . _ . . . . . _ . . . .
M .~
12 lil Tiii .i:I.i :ii EVBEDDED FLAW 1 [' 9R , FLAWS WITH a
. 21stsi " '"
...: +38 p jCONFIGUR ATION rA. . ."*
' " ' " ' ' " ' " * ~ ..
^ ^ ' '
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EE . .::.J . ..T ". . . . .
NOT ALLOWABLE 4
g 3g
- 5: --
4:n '/ :-
'ik:.' :- !! 3 :[.ii:-l ~'.7 03 !E:i::: ?
. 5:
!!M - ::= . n. I:I !5 *i:9 5 i ~ if[ii5 !!$ l i !!I:Iihl '-
I piir:.- -
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=*I
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=.= -. . . . .
. W:=:
,+ .
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-- a/t ~ = 0.100
.., PiEGION W!ST CC "": y .: 2Wd**'"
2 ::ngn . ...-
O '
@ CONSIDERED g :: SURFA CE [.fi:ii.: ijffpr"~171 ii[:'~' .3.:~i i:U '-- --
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r
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= -
- ir ri Ei N ALL EMBEDDED FLAWS sii:i !!h! fi- /Mii !=ci ! -i: ~
H g.. . Miiii (ON THIS 5 JE OF n.jii :=ip/ :' /n un r .. :: -
. . . :n rii; .
DEMARKATION LINE) 0.03
- 7. . " .~ ::7 5.. ARE ACCEPTABLE PER n f. /-
i:1!:: iiirn- :u:: : en g:: ir-i CRITERIA OF IWB 3600
!"-i
- h. . I. IN AS LONG AS 2a 40.25 0.02 !
- f. ild /f n
Sr:=:!gs :uili:n wr agrie a: ::=: '-- t t
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- n.
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Figure A-7.3 Evaluation -Chart for Outlet Nczzle to SFall Weld (0-ientation No.1)
X Inside Surface Surface Flaw X Longitudinal Flaw X Outside Surface 1 Embedded Flaw X Circumferential Flaw me.me no A-57
attachment 2E Page 2 OUTLET NOZZLC RPV-2-686 C INDICATION NO. 2 s SURFACE / EMBEDDED
,. FLAW DEM AR CATION LINE , .
0.13 . .__. . . _ . . . . . _ . _ . _
i: lie-liii :M
' id! -
- ii EMSEDDED FLAW EUI i:f2" ":f:
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- = NOT ALLOWABLE
- f. "- "'""
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\
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g; ;; ,3;gpg ;;tg;
;;3g;; u h 0.07 E- "y.:sunrace: : ::: g:::::' :.g: ' Ui . ..._.. : 3.g;;3 = e pg
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~':"'=*= '=~ * *"" N" = =::~.:
o ~ " ~
- ** E M: . E". .
Z
>'" g*gg NWS IN MS MM N h N
- a/t = 0.100 REGION MUST BE : ,u. = .:.ju . : :"
pf 6N')
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" " G*""
yyW,"'iik 2/~~
~
5 CONSIDERED g
D 0.05
- sunFAcE m rLAwS
- E*::* = mr r-[i l'". . . .?. . .N.}.
f i.g
- g. a.:7: - -
12
[ 2G(gVe, gg) 4 iipe. .:ifa.isyf!:i mim: .= t.- :in i- i :ifi i % ALL EMBEDDED FLAWS
-i Z 0.04 - -
=e";. . .
- i[Ei m Ci: ==:' i in :-
(ON THIS SIDE OF
.T : " . :)p~/"". .
~.1=T2: -I :.
=
DEMARKATION LINE)
~4"I.:P ... '
7' Ti .. . ' '
ARE ACCEPTABLE PER m:li:i ";/n. . /'^ . e iiirin :1!!hi : =
O.03 .-.
- c. ::ui fi:f!"F CRITERIA OF IWB 3600
= . . . .yif-
=ja rv 4 "".:a : upn .u . . . .
AS LONG AS .2af,0.2$
- ~ - - " - "
0*02 =
. . . .=iff . e si2js i. . q _
-a igi:n . i t-
- ii:/["'". .
~
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14 r .- -
if/: =l;; -
i" Hit?= ': JP : -
F bi li: ,iiii:iii i:lii . Elli
, 0 }
0 0.05 0.10 0.15 0 '20 0.20 DISTANCE FROM SURFACE d)
I r
1 Figure A-7.3 Evaluation Chart for Outlet Nozzle to Shell Weld (Orientation No.1) l X Inside Surface Surface Flaw X Longitudinal Flaw X 0:.tside Surfat= X Embedded Flaw X Circumferential Flaw !
A-57 !
1 i l l
l
. o *t' *
.. Attachment 2E
.' Page 3
- I OUTLET NOZZLE RPV-2-686-C INDICATION NO. 5 J
SURFACE / EMBEDDED FLAW DEM ARCATION LINE .
0.13 . .... . . . . u...._. . . ._,
iEilii.U.iii N
'iid.1 !i- EMBEDDED FLAW .*[ D. .~". "=
_ FLAWS WITH 8
%. . 3..- ,.. 4 coNricu..m.A..r.io..N 7 ... , . _n .
.n. .gj;3.i.
-. . . . 4. ... ...;
i..
' 0'12 EEiiiii -
iii- ! au . 1 n=:...: ~-n ~~~=:: nz: ABOVE THIS LINE ARE
.~. M.M'i:t
(~.=2:: 2 1 :.- NOT ALLOWABLE z"(=.x i= '
'H J)" '
\=; i "'i .= ?i 4 "' =
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en ::
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0.07 3:' in= =su
**~~ a/L = 0*167
$ n + n:n: 2.lilif i;ME s+Mii -3:Mi iisi: Wii_d. W
, :c jruws m ms :@! M @@hMMW Mi -
a
{ 0'06 gG,',0],M,u E
7 sE g
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~
f.r;i.fii:'. E
'Fe: - - - -
- h'i ruws
- -fi i= fn/.Z "i
- iitn ="-: . b. .r
' /iI j 0.04
" ~
INii Ei Sh
" dE I"i s' # N ALL EMBEDDED FLAWS
==r -fiTf7Elii nri i -i i lii ..
Off:.:. (ON THIS SIDE Or "l!/ .:g:i[iEijii: 2:n /
DEMARKATION LINE)
- 0.03 ARE ACCEPTABLE PER
.. ..;..=
fay:.. : uy. . :=:'.:,. -. . . .u- :-.g ...: .
- - :- - .: . . .4 n. CRITERIA OF IWB 3600 0.02
- 7.. A .
P5 g . .: .
==4n 2 F...
- u- ~
.mgn u -.
Tp" 5 .' . :.~ .' .*: ." '
AG LONG AS .2a.(.O.25 r 4- . 1"33 =a: im :. -
. u " tj e: ut;n =i :s12 - t
=f. rQ . .{.
. . .n.; =.}5;
~
,. pl = .. . . . ; iji -
iff
.:- 25 .1. .
.li a ,
0 F!* ....r qn-p 0 0.05 0.10 0.15 0.20 0.25 DISTANCE FROM SURFACE (f
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Figure A-7.3 Evaluation Chart for Outlet Nozzle to Shell Weld (Orientation No.1)
X Inside Surface Surface Flaw X Longitudinal Flaw X Outside Surface X Embedded Flaw _X_ Circumferential Flaw me m.cano A-57
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