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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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Wisconsin
,Electnc CNW scoli A. PATULSKl p ,,, , , , SITE VICE PRESIDENT 6610 Nuclear Rd.. Two Rivers. WI S4241 (920) 755-6214 NPL 98-0470 10 CFR 2.201 June 4,1998 Document Cor. trol Desk U. S. NUCLEAR REGULATORY COMMISSION Mail Station PI-137 l Weshington, DC 20555 Ladies / Gentlemen:
DOCKET 50-301 REPLY TO A NOTICE OF VIOLATION NRC INSPECTION REPORT 50-301/98005 i POINT BE ACH NUCLEAR PLANT. UNIT 2 !
In a letter from Mr. John Grobe dated May 5,1998, the Nuclear Regulatory Commission forwarded the results of an inspection conducted by your staff at our Point Beach Nuclear Plant. The inspection was conducted from December 16,1997, through March 9,1998. The inspection report included a ,
Notice of Violation which identified four violations of NRC requirements. j We have reviewed the Notice ofViolation and, pursuant to the provisions of 10 CFR 2.201, have prepared a written response to the four violations requested by your letter of May 5,1998. Our written response to these violations is included as an attachment to this letter.
We believe that the attached reply is responsive to the Notice of Violation and fulfills the requirements identified in your May 5,1998, letter.
New commitments that have not been previously docketed are identified by italics.
I l ifyou have any questions or require additional information regarding this response, please contact /
me.
Sincereg, .. b 3 M
kWw (JScott A. Patuiski Site Vice President Point Beach Nuclear Plant Attachment cc: NRC Resident Inspector NRC Project Manager NRC Regional Administrator PSCW 9906090317 990604 <
PDR ADOCK 05000301 4'Msen EwWuzuur O PM i
A'ttachment to NPL 98-0470 Page1 4
DOCKET 50-301 REPLY TO A NOTICE OF VIOLATION NRC INSPECTION REPORT 50-301/98005 POINT BEACH NUCLEAR PLANT. UNIT 2 During an NRC inspection conducted from December 16,1997, through March 9,1998, four violations of NRC requirements were identified. Inspection Report 50-301/98005 and the Notice of Violation (Notice) transmitted to Wisconsin Electric on May 5,1998, provide details regarding the violations.
In accordance with the instructions provided in the Notice, our reply to the violation includes, as appropriate: (1) the reason for the violation, or if contested, the basis for disputing the violation; (2) the corrective action taken and the results achieved; (3) corrective action to be taken to avoid further violations; and (4) the date when full compliance will be achieved.
As requested in the NRC's May 5,1998 letter, in addition to responding to the four cited violations, our response also includes a discussion ofissues associated with welding audits conducted in support of our Unit 2 Steam Generator Replacement Project (SGRP).
Violation 11 "10 CFR 50, Appendix B, Criterion IX, " Control of Special Processes," requires, in part, that measures shall be established to assure that special processes, including welding, and heat treating, are controlled and accomplished by qualified personnel using qualified procedures in accorciance with applicable codes, and standards.
The 1995 Edition of the American Society for Mechanical Engineers Code,Section IX, Paragraph QW-409.1, requires that "A che.nge in the type of current or polarity, an increase in heat input, or an increase in volume of weld metal deposited per unit length of weld, [is not allowed] over that qualified."
(a) Contrary to the above, in November and December of 1996, weld procedure WPS GT-SM/1.1-1 PB, Revision 4, used to fabricate steam generator replacement main steam and feedwater welds, did not meet the requirements of QW-409.1. Specifically, this weld procedure authorized welding with an increase in heat input over that which had been qualified.
This is a Severity Level IV violation (Supplement I).
(b) Contrary to the above, in November of 1996, weld procedure WPS GT-SM-BU/1.3-1 PB, Revision 1, used to perform welding on the steam generator feedwater nozzle weld, did not meet the requirements of QW-409.1. Specifically, this weld procedure authorized welding with an increase in heat input over that which had been qualified.
This is a Severity Level IV violation (Supplement 1)."
Attachment to NPL 98-0470 Page 2
. 1 pa==a=== to Violation 1.m:
We concur this is a violation of NRC requirements as characterized in the inspection report.
- Welding Procedure Specification (WPS) OT-SM/1.1-1PB was utilized during the PBNP Unit 2 Steam Generator Replacement Project to perform pipe-to-pipe welds on the main steam and feedwater piping i systems. GT-SM/1.1-IPB Revision 3, and earlier revisions, allowed welding on applications which did not require post-weld heat treatment (PWHT). Revision 3 permitted maximum allowable heat inputs of 28.8 kj/in for the GTAW process and 85.8 kj/in for the SMAW process. Revision 3 of this WPS was supported by PQRs GT-SM/1.1-Q4 and Q1 and Q2. ;
During the Unit 2 steam generator replacement outage, it was necessary to revise
. WPS GT-SM/1.!-lPB to perform unanticipated welds required by a minor steam generator fit-up problem. Revisicn 4 to this WPS was developed to allow welding on either non-PWHT or PWHT applications. In changing the WPS from Revision 3 to Revision 4, the maximum allowable heat inputs were increased to 47.4 kj/in for the GTAW process and reduced to 52.8 kj/in for the SMAW process. Revision 4 to this WPS is supported by PQR GT-SM/1.1-Q5, which was qualified specifically for PWHT.
While incorporating PWHT requirements into Revision 4 of the WPS, pertinent information for non-PWHT welds was not carried forward from the previous revision. Revision 4 of this procedure was written to allow both PWHT and non-PWHT welds, but the heat input limits listed in the revised J procedure were those qualified for PWHT welds. These heat inputs were higher than those for the non-PWHT applications. Under Revision 4, welds not requiring PWHT could have been welded utilizing the GTAW process with heat inputs as high as 47.4 kj/in. This condition resulted in a welding procedure that was not qualified for non-PWHT welds because available qualification records limited GTAW heat inputs to 28.8 kj/in for non-PWHT welds. Revision 4 of the procedure should have contained a note to limit heat inputs for non-PWHT welds.
Corrective Actions Taken: i This ASME Code variance was self-identified by Morrison Knudsen in January 1997 in Quality Finding Report (QFR) 01 associated with Assessment C-96-022. Subsequent to the issuance of i
- QFR 01, PQR GT-SM/1.1-Q6 was developed. This PQR qualifies a maximum heat input of 83.3 kj/in for the GTAW process and 98.8 kj/'mfor the SMAW process for weld applications which do not i require PWHT, These higher heat input limits bound the heat inputs of any non-PWHT welds made to Revision 4 of WPS GT-SM/1.1-1PB during our Unit 2 steam generator replacement project. PQR ,
GT-SM/1.1-Q6 qualified the non-PWHT welds with heat inputs well in excess of the maximum heat f inputs listed in Revision 4 of GT-SM/1.1-1PB.
In addit. ion, WPS GT-SM/1.1-IPB Revision 5 has been issued by Morrison Knudsen to reference PQR GT-SM/1.1-Q6 and to include appropriate heat input restrictions for welds not subject to PWHT.
Revision 5 brings WPS GT-SM/1.1-1PB into full Code compliance.
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Attachmmt to NPL 98-0470 l Page 3
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The development of PQR GT-SM/1.1-Q6 assures that non-PWHT welds made during the PBNP Unit 2 Steam Generator Replacement Project pursuant to Revision 4 of WPS GT-SM/1.1-IPB are i fully qualified.
Wisconsin Electric's audit team reviewed this Code compliant issue during Audit 97-130, which was completed in October 1997. - WPS GT-SM/1.1-IPB Revision 4 was reviewed during the audit. The PQRs were compared to the essential, supplementary-essentia;, and non-essential variables contained in the WPS. The PQRs attached to the WPS reviewed during the audit did not include PQR l GT-SM/1.1-Q5, so the WPS allowances for heat input of 47.4 kj/in with the GTAW process and PWHT was questioned. Upon receipt of PQR GT-SM/1.1-Q5 from Morrison Knudsen during the ,
audit (October 3,1997), this PQR was reviewed and had been made with PWHT and a heat input of l 47.4 kj/in. for the GTAW process. ASME Section IX was not interpreted to indicate that the maximum heat input to be specified in the WPS was limited based on the weld made with or without PWHT. Therefore, the audit team failed to identified this issue as a Code nonconformance.
Corrective Actia== to be Takan: j I
There are no additional corrective actions planned to be taken.
Date Of Full Cornnilanca:
Full compliance with NRC requirements was achieved concurrent with Wisconsin Electric's review and acceptance of PQR GT-SM/1.1-Q6 and WPS GT-SM/1.1-IPB Revision 5. :
i Da==a=== to Vial = flan 1.h:
We concur this is a violation of NRC requirements as characterized in the inspection report.
1' WPS GT-SM-BU/1.3-IPB Revision I allowed heat inputs above those qualified in referenced PQR GT-SM-BU/1.3-Ql. WPS GT-SM-BU/1.3-IPB Revision 1 allowed welding with a maximum heat input of 73.3 kj/in for the GTAW process and 85.8 kj/in for the SMAW process. The maximum heat inputs supported by the referenced PQR are 46.3 kj/in for the GTAW process and 54.3 kj/in for the SMAW process. Because of the heat input disparity between the WPS and the PQR, WPS GT-SM-BU/1.3-IPB, Revision 1 was not fully Code compliant.
WPS GT-SM-BU/1.3-IPB Revision I was used during the PBNP Unit 2 replacement project but not for any permanent plant weldments. This buttering welding procedure was used on the main feedwater nozzles, but the buttering was subsequently machined off, and therefore, was not part of the
' final weldment.
1 The feedwater nozzle extension is a P3 type msterial. The feedwater pipe that was to be welded to the extension is a P1 type material. The welding of thisjoint would have required PWHT. The purpose of the buttering procedure was to allow the P3 to P1 postion of the weld to be accomp ished by !
buttering the feedwater nozzle extension with a P1 type weld filler material. The weld to be made in '
the field would then be a P1 to P1 weld which would not require PWHT. Such buttering would allow
Attachment to NPL 98-0470 Page 4 -
the PWHT to be performed in the fabrication shop, thereby eliminating the need to PWHT the weld inside the containment building.
After buttering the feedwater nozzle extensions, using WPS GT-SM-BU/1.3-IPB Revision 1, and prior to machining the weld preps, informational radiographs were performed. Results of the radiographs indicated discontinuities that would have necessitated repair. As a result of these indications, a decision was made to remove the buttering by machining to the original weld preparation configuration. This machining removed all weld metal which was deposited using WPS GT-SM-EU/1.3-1PB Revision 1. The feedwater nozzle extension to feedwater pipe weld was subsequently made using a different qualified WPS.
Corrective Actions Takent This Code compliant issue was identified by Morrison Knudsen in their Quality Finding Report (QFR) 01 and associated Assessment 96-C-022. Morrison Knudsen dispositioned this finding by validating that the buttering weld material had been removed and that WPS GT-SM-BU/1.3-IPB Revision I was therefore not used on any permanent plant weld applications. Verification that WPS GT-SM-BU/l.3-1PB Revision I was not used for permanent plant welds was documented in Morrison Knudsen's letter dated June 6,1997.
In preparation for Wisconsin Electric's Audit 97-130, this buttering procedure was discussed and acknowledged to have been removed and was not part of a permanent plant eldment. Therefore, the scope of the audit did not review the issue in further detail other than to verify that the buttering weld meterial was removed.
WPS GT-SM-BU/1.3-1PB was canceled by Morrison Knudsen on May 28,1998, and is no longer in use.
Corrective Actions to be Taken:
No additional corrective actions are planned to be taken.
Date Of Full Comnli==ce:
Full compliance was achieved upon verification that WPS GT-SM-BU/1.3-IPB Revision I was not used for permanent plant welds and upon cancellation of WPS GT-SM-BU/1.3-IPB on May 28,1998.
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'Attcchment to NPL 98-0470 Page5 s
Violation 2:
"10 CFR 50, Appendix B, Criterion V, " Instructions, Procedures, and Drawings" requires that l
activities affecting quality shall be prescribed by documented instructions and procedures and shall be accomplished in accordance with those instructions and procedures.
Contrary to the above, activities affecting quality were not performed in accordance with documented I
procedures, in that, on December 9 and 10,1996, post weld heat treatments were applied to two main steam weals, FW-6 on steam generators A and B, which had a material thickness of 1.3 inches; however, the procedure prescribing heat treatment, WPS GT-SM/1.1-1PB Revision 4, contained no instructions for material thickness below 1.5 inches.
This is a Severity Level IV violation (Supplement I)."
D=na== to Vinlatlan 2 l-We concur this is a violation ofNRC requirements as characterized in the inspection report.
- Performance of PWHT on two main steam pipe welds were not prescribed in WPS GT-SM/1.1-lPB, Revision 4. The WPS lacked specific instructions to perform PWHT for main steam welds made on pipes of material thickness of less than 1.5 inches.
The original plan for welding of the main steam piping consisted of three welds for each steam ;
generator. Field Welds 2 and 3 joined P1 and P1 type base materials approximately 1" thick along the
- horizontal run of the of the main steam pipe. These welds were made utilizing WPS GT-SM/1.1-1PB and did not require PWHT. Field Weld 1 joins the elbow of the main steam piping to the steam generator outlet nozzle. This weldjoined P1 and P3 type base material, approximately 1.35 inches thick, utilizing WPS GT-SM/1.3-1PB which required PWHT.
As the result of an unanticipated minor steam generator fit-up problem, it was necessary to install a small pipe pup piece, of approximate 4" length, between the steam generator outlet nozzle and the main steam elbow. This resulted in an additional weld, Field Weld 6, thatjoined the pup piece to the main steam elbow. Field Weld 6 joined P1 to P1 type base material which did not require PWHT.
Due to the close proximity of Field Welds 1 and 6, it was determined to not be possible to PWHT Field Weld I and not affect Field Weld 6. A decision was made to PWHT both welds at the same time. The decision to PWHT Field Weld 6 prompted Revision 4 of WPS GT-SM/1.1-1PB to include PWHT. Revision 4 was supported by PQR GT-SM/1.1-Q5.
WPS GT-SM/1.1-1PB Revision 4, which was used to make Field Weld 6, provided PWHT instructions for welds 1.5" thick and greater, but was silent on PWHT instructions for welds less than
' l.5". The wall thickness for Field Weld 6 was approximately 1.35".
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- The WPS revision was written to include PWHT Code requirements. ASME Section IX requires that i the WPS ad kesses all essential and non-essential variables. PWHT is an essential variable. While the l
' WPS did address ASME Section 111 mandated PWHT requirements, it was silent on PWHT guidance l for thicknesses less than 1.5", At the time of the WPS revision, it was known that PWHT was not i l
" Attachment to NPL 98-0470
- Page 6 t
required by the Code for material thicknesses ofless than 1.5", therefore, we believed that the WPS was not required to address PWHT for welds less than 1.5".
Corrective Actions Taken:
An additional review of WPS GT-SM/1.1-IPB Revision 4 was performed to re-confirm compliance with applicable Code requirements regarding PWHT. From this review, we reached the same conclusion summarized in the NRC inspection report. We concluded the WPS and affected welds are in conformance with Code requirements and Field Weld 6 is fully qualified.
Wisconsin Electric Audit 97-130 evaluated this issue and determined that although the WPS was silent for PWHT of base material below 1.5", a Heat Treatment Record was prepared for this weld which provided instructions for the PWHT process. Wisconsin Electric's audit team did not consider this issue a Code compliant issue.
We have also reviewed the PWHT instructions associated with Field Weld 6. The Violation
. description implies that adequate controls were not in-place to perform the PWHT for Field Weld 6 because the WPS did not give specific guidance for. material thicknesses for less than 1.5". Weld Data Card 3081-B-10 and Heat Treatment Record 3081-B-10 used for Field Weld 6 provide appropriate instructions necessary to correctly perform the PWHT.
Corrective Actions to be Taken:
No additional corrective actions are planned to be taken.
i Date of Full Compliance Full compliance was achieved upon our confirmation that the WPS and affected welds are in conformance with Code requirements and that PWHT instructions were provided in the applicable Heat Treatment Record. !
I Violation 3: I "10 CFR 50, Appendix B, Criterion XVII," Quality Assurance Records," requires, in part, that
. sufTicient records shall be maintained to furnish evidence of activities affecting quality.
Contrary to the above, as of March 9,1998, records for the welding processes used on Unit 2 steam ,
generators, were not sufficient to furnish evidence of activities affecting quality in the followmg
. instances:
(a) . Weld Date Card (WDC) 3042-A-2 and WDC 3042-B-2 for steam generator A and B feedwater nozzle welds, listed a weld procedure which was not used to fabricate the weld.
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(b) WDC 3081-B-7 for a feedwater weld, did not record the correct weld procedure revision used j to fabricate the weld.
(c) WDC 3081-A-2 for a main steam weld, did not record the correct weld procedure revision used to fabricate the weld.
This is a Severity Level IV violation (Supplement 1)."
P==a== to Violation 3:
Documentation associated with welding activities perfonned during the PBNP Unit 2 Steam I Generator Replacement Project were managed as quality records in accordance with the SGT Ltd. and PBNP Quality Assurance Programs. These programs were implemented during the project to assure the accuracy, retrievability, and maintainability of records for activities associated with quality. We j acknowledge that the three examples cited in Violation 3 represent a failure to fully meet our standards and the standards 10 CFR 50 Appendix B, Criterion XVII for accuracy and retrievability of l records, i i
The cited examples can be characterized as either a deficiency to clearly identify the welding procedure specification used for a particular weld or as a deficiency to assure that the correct revision number for the welding procedure specification was identified on the Weld Data Cards.
Corrective Actions Taken:
l Condition Report 98-1351 was created on March 31,1998 to document the apparent deficiencies in the permanent plant records cited in Violation 3 and recommended that the permanent plant records be ]
corrected as necessary. Each of the Weld Data Cards cited as examples in Violation 3 have been !
! reviewed in detail.
i l Weld Data Cards for the project were generated by the SGT Ltd. Project Welding Engineer and l l reviewed and approved by SGT Ltd., Wisconsin Electric, and ANI personnel in accordance with
- project quality execution procedures. At the time the Weld Data Cards were generated, the Project ,
l Welding Engineer could authorize the use of one or more qualified welding procedure specifications l to make the weldment. The authorized welding procedure specification (s) were listed on the Weld Data Cards. For Weld Data Cards 3042-A-2 and 3042-B-2, both WPS GT-SM/3.3-2PB (a manual j
process) and WPS GTM/3.3-IPB (an automated process) were listed on the Weld Data Cards as an
~ acceptable procedure for use. At the time the weldment is made, construction supervision was
. empowered to use either of the acceptable procedures listed on the Weld Data Card. !
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Attachment to NPL 98-0470
- Page 8 For the welds made by the subject Weld Data Cards, the manual process, WPS GT-SM/3.3-2 PB was used. Traceability to WPS GT-SM/3.3-2 PB was validated through a review of the filler material identification numbers listed on the Weld Data Cards. The filler material identification numbers listed on the subject Weld Data Cards correspond to the manual process, WPS GT-SM3.3-2PB. For Weld Data Cards which may have listed more than one authorized WPS, a similar validation can be made to determine which WPS was used. However, we acknowledge that relying on such validation process to historically determine from permanent plant records which WPS was used is not a best practice.
The second and third cited examples associated with Violation 3 regard Weld Data Cards which apparently did not record the correct weld procedure specification revision. As described earlier, due to emerging work activities associated with a minor steam generator fit-up problem, it was necessary to revise some of the WPSs during the replacement project while work was in progress. Insufficient care when issuing a revised WPS to assure work already in progress reflected the correct WPS revision contributed to this deficiency.
Weld Data Card 3081-B-7 was generated for the welding of Field Weld 7, which was made on the vertical run of the feedwater line to lower the horizontal run into the steam generator. This was a work scope change which was controlled by Work Package Change Notice 14. Weld Data Card
. 3081-B-7 documents the use of Revision 3 of WPS GT-SM/1.1-1PB. Revision 4 of this WPS was issued on November 28,1996.
A myiew of the Weld Data Card indicates that SGT Ltd. Nonconformance Report (NCR) 209 was written because the original Weld Data Card was lost. Weld Data Card 3081-B-7 was reconstructed in accordance with NCR 209 by review of the Quality Control Daily Inspection Reports, Weld Filler Material Withdrawal Slips, and NDE Reports.- In review of NCR 209 and associated documents, it has been determined that this weld was fit and tacked on November 28,1996. The weld also appears to have been completed on this date as no Weld Filler Material Withdrawal Slips associated with this weld were believed issued any later han November 28,1996.
We believe that the use of Revision 3 as documented on Weld Data Card 3081-B-7 is correct.
Revision 4 of WPS GT-SM/1.1-IPB was approved on November 28,1996, the same date as the apparent completion of the weld. It is believed that Revision 4 was not posted to the controlled document stations until after completion of the subject weld. In addition, Revision 4 was developed for the purpose of adding PWHT requirements to the WPS. The weld completed by Weld Data Card '
3081-B-7 did not require PWHT.
Weld Data Card 3081'-A-2 was issued for main steam Field Weld 2, which is on the horizontal run of -
the main steam line. This weld was fit and tacked on November 23,1996. The revision of WPS GT-SM/1.1-IPB that was in effect at that time was Revision 2 and was so documented on the Weld Data Card. Records indicate that the WPS was revised to Revision 3 on the same day that the welding began. By reviewing the Weld Data Card, the record indicates that work on this weld
. continued past the Revision 3 issue date of November 23,1996. While it appears that Revision 2, when documented on the Weld Data Card was correct, the Weld Data Card should have been changed to document Revision 3 of WPS GT-SM/1.1-IPB when it was issued.
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~ Attachment to NPL 98-0470 Page 9 Revision 3 of WPS GT-SM/1.1-IPB changed the amperage ranges for the GTAW process. The change from Revision 2 to Revision 3 gave a wider amperage range on the low end. Therefore there ;
were no hardware impacts based on the conclusion that Revision 3 did not have any affect on the maximum allowable heat inputs.
Corrective Actions to be Taken:
Work is in progress to complete actions associated with Condition Report 98-1351. We are in the process ofreviewing each Weld Data Card usedfor the PBNP Unit 2 Steam Generator Replacement Project to assure that each WeldData Card clearly depicts which WPS was usedfor the weldandto assure that the proper WPS revision is documented. Permanentplant records will be modified i appropriatelyfor any identified deficiencies. We expect this review to be completed byJuly 15,1998.
Date Of Full Compliance:
Full compliance will be achieved by July 15,1998 with the close-out of Condition Report 98-1351.
Audit Adequacy Issues Wisconsin Electric performed Audit 97-130 to evaluate the issues identified in Morrison Knudsen Quality Finding Report 01 and associated Assessment C-96-022 and to address the issues stated in the NRC's letter to Wisconsin Electric dated August 5,1997.
As stated in the scope of Audit Report 97-130, the audit addressed the following points:
- 1. Timeliness of reporting the QFR C-96-022 to Wisconsin Electric. The QFR was written in January 1997 but was not reported to Wisconsin Electric until August 1997.
- 2. Review of other QFRs or quality records for issues which have not been shared with Wisconsin Electric.
- 3. Review of welding procedures, weld data cards, procedure qualification records, and other information as necessary to assure ASME Code requirements were met.
The audit team restricted their scope of evaluation of Morrison Knudsen to only those procedures and activities affecting PBNP.
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Attachment to NPL 98-0470 Page 10 -
The primary focus ofItem 3 of the above listed audit scope was to review the welding procedure specifications to determine that they were properly qualified in compliance with ASME Code requirements and the procedure qualification records supported their qualification. Weld Data Cards were reviewed to ensure:
- 1. Proper WPSs were used for each weld based on the base materials and thickness.
- 2. Filler materials were appropriate for thejoint and were in compliance with WPS requirements.
- 3. Weld heat input was monitored and met WPS requirements.
4.- Post-weld heat treatment was performed when required.
in addition to review of the WPSs, PQRs and weld records pertaining to the project, QFR C-96-022 was reviewed in detail, as well as 21 other Morrison Knudsen audits dating back to 1993.
. The results of Audit 97-130 were summarized in our letter to the NRC on October 16,1997. In that letter, we concluded that all permanent welds met or were subsequently demonstrated to meet relevent qu'ality assurance standards and applicable ASME Code requirements.
Violations 1.a. and 1.b. of this subject NRC inspection report depicted two specific Code violations.
Both of these were identified as apparent Code violations in Morrison Knudsen's Assessment C-%-022. Wisconsin Electric's audit team reviewed both of these issues.
Our audit team failed to recognize that WPS GT-SM/1.1-IPB Revision 4 failed to meet Code requirements. The auditors reviewed PQR GT-SM/1.1-Q5 during the audit to assess heat input restrictions. ASME Section IX was not interpreted to indicate that the maximum heat input to be {
specified in the WPS was limited based upon the weld being made with or without PWHT Therefore, !
the auditors believed that PQR GT-SM/1.1-Q5 properly dispositioned this issue. We now acknowledge that WPS GT-SM/1.1-lPB was not fully qualified until development of PQR GT-SM/1.1-Q6.
The Wisconsin Electric audit team acknowledged that WPS GT-SM-BU/1.3-1PB was not Code compliant. The audit team dispositioned this issue by verifying that the buttering weld material was removed and was not a' permanent plant weld.
, Subsequent to Audit 97-130, and concurrent with the NRC inspection of these issues, Wisconsin Electric documented additional minor welding procedure discrepancies. Condition Report 98-0149 was written to document that WPS FC/3.3-IPB contained a footnote that was inconsistent with ASME Section IX requirements. The footnote was not applicable to welding performed at PBNP and therefore, had no impact on the weldment. However, this WPS has been revised to assure it is fully L Code compliant.
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" Attachment to NPL 98 0470 PageiI t
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- Condition Report 98-0339 was written to document a PWHT temperature variance. WPS GT-SM/1.1-1PB Revision 4 lists an authorized PWHT temperature of 1150 *F +/-25 F. A review of the PWHT strip charts for this weld demonstrated that actual field PWHT deviated from the range defined within the WPS. However, the PWHT temperatures remained well within those required by ASME Code. The WPS applied a conservative temperature range. An expanded review of other SGRP work packages was conducted as a result of this Condition Report. This review identified that WPS GT-SM/1.1-3PB specified a similar PWHT range. PWHT strip chart records confirm that actual PWHT temperatures were not maintained within the WPS specified range; but again, were well within the heat range requirements required by the Code. These procedure discrepancies will be fully -
dispositioned with the close-out of Condition Report 98-0339. l Because some inconsistencies exist between the conclusions drawn in our Audit Report 97-130 and the Bndings in the NRC inspection report, Quality Condition Report (QCR) 98- 0130 was written on March 30,1998. This QCR noted these inconsistencies and expressed the need to assure that audits include necessary substantiating evidence to document conclusions. This QCR has been assigned to our Quality Assurance Group for assessment and to determine what corrective actions may be needed to improve special audits in the future.
The QCR 98-0130 assessment is expected to befully completed by July 31,1998. Recommended corrective actions will be administeredin accordance with the PBNP Corrective Action Program. 1 l
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