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MONTHYEARML20215L9521986-10-27027 October 1986 Requests Relief from 10-yr Inservice Insp Interval. Supportive Info for Relief Request from Specific 1977/ Summer,1979 Edition/Addenda of ASME Section XI Code Requirements Encl.Fee Paid Project stage: Request ML20213G5531987-05-0707 May 1987 Forwards Safety Evaluation Re Util 861027 Request for Relief from Exam Requirements of Section XI of ASME Boiler & Pressure Vessel Code for shell-to-tubesheet & nozzle-to- Shell Welds in Regenrative Hxs.Relief Granted Project stage: Approval 1986-10-27
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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
[Table view] Category:UTILITY TO NRC
MONTHYEARML20059H9391990-09-13013 September 1990 Forwards Amended Response to Notice of Violations Noted in Insp Repts 50-266/89-27 & 50-301/89-26.Corrective Action: Revised Procedures Will Not Be Issued Until After Unit 2 Refueling Outage.Other Changes Anticipated by 901231 ML20059G7211990-09-0505 September 1990 Responds to Generic Ltr 90-03, Vender Interface for Safety- Related Components. Implementing Formal Vendor Interface Program for Every safety-related Component Impractical ML20028G9071990-08-31031 August 1990 Advises That long-term erosion/corrosion-induced Program for Pipe Wall Thinning in Place,Per Generic Ltr 89-08.Program Assures Erosion/Corrosion Will Not Lead to Degradation of Single & two-phase High Energy Carbon Steel Sys ML20059G8741990-08-31031 August 1990 Forwards Revised Security Plan,Per NRC .Summary of Revs Listed.Rev Withheld (Ref 10CFR3,50,70 & 73) ML20064A4711990-08-29029 August 1990 Forwards Semiannual Monitoring Rept,Jan-June 1990, Rev 1 to Process Control Program, Rev 7 to Environ Manual & Rev 5 to Odcm ML20058N6771990-08-0303 August 1990 Forwards Public Version of Revised Procedures to Emergency Plan manual.W/900813 Release Memo ML20058L1471990-08-0303 August 1990 Responds to NRC Re Weaknesses Noted in Insp Repts 50-266/90-201 & 50-301/90-201 Re Electrical Distribution. Corrective Actions:Design Basis Documentation Will Be Developed to Alleviate Weaknessess in Diesel Generators ML20058L5041990-07-30030 July 1990 Discusses & Forwards Results of fitness-for-duty Program Performance Data for 6-month Period Ending 900630 ML20055J2031990-07-25025 July 1990 Responds to NRC Bulletin 89-002 Re Insp of safety-related Anchor/Darling Model S350W Check Valves Supplied w/A193 Grade B6 Type 410 SS Retaining Block Studs.Studs Visually Inspected & No Cracks Found ML20055H7781990-07-24024 July 1990 Forwards Corrected Monthly Operating Rept for June 1990 for Point Beach Unit 2.Correction on Line 18 Regards Net Electrical Energy Generated ML20055H6621990-07-23023 July 1990 Forwards Central Files & Public Versions of Revised Epips, Including Rev 2 to EPIP 1.1.1,Rev 16 to EPIP 4.1,Rev 6 to EPIP 6.5,Rev 20 to EPIP 1.2,Rev 8 to EPIP 6.3,Rev 0 to EPIP 7.3.2,Rev 10 EPIP 10.2 & Rev 11 to EPIP 11.3 ML20058K8941990-07-23023 July 1990 Forwards June 1990 Updated FSAR for Point Beach Nuclear Plant Units 1 & 2.Steam Generator Upper Ph Guideline in Table 10.2-1 Changed from 9.3 to 9.4 ML20044A9091990-07-0606 July 1990 Responds to NRC Bulletin 90-001 Re Loss of Fill Oil in Transmitters Mfg by Rosemount.None of Listed Transmitters Installed at Plant in Aug 1988 Identified as Having High Failure Fraction Due to Loss of Fill Oil ML20055D4421990-07-0303 July 1990 Forwards Reactor Containment Bldg Integrated Leak Rate Test Point Beach Nuclear Plant Unit 1,1990, Summary Rept ML20055D3471990-06-29029 June 1990 Provides Addl Response to Bulletin 88-008, Thermal Stresses in Piping Connected to Rcss. Engineering Evaluations Performed to Assure Code Compliance Due to Unanalyzed Condition of Thermal Stratification Addressed ML20055D6221990-06-29029 June 1990 Provides Suppl to Re Loss of All Ac Power.Test Demonstrated That Ventilation Mod & Recalibration of High Temp Trip for Auxiliary Power Diesel Improved Performance of Gas Turbine Generator as Alternate Ac Source ML20055D2291990-06-22022 June 1990 Informs NRC That Gj Maxfield Promoted to Plant Manager effective,900701 ML20055D6231990-06-22022 June 1990 Advises of Decision to Proceed W/Leak Testing of Sys During Plant Refueling Outage Due to Delay in Delivery of Gamma-Metrics Hardware Fix Kits.Test Revealed That Both in-containment Cable & Detector Assembly Cable Had Leaks ML20044A0011990-06-18018 June 1990 Provides Current Implementation Status of Generic Safety Issues at Plant,In Response to Generic Ltr 90-04 ML20043D6511990-05-25025 May 1990 Discusses Cycle 18 Reload on 900519,following 7-wk Refueling & Maint Outage.Reload SER for Cycle 18 Demonstrates That No Unreviewed Safety Questions,As Defined in 10CFR50.59, Involved in Operation of Unit During Cycle ML20043B1481990-05-18018 May 1990 Advises That Necessary Info Received from Westinghouse Re Revised Administrative Controls for NRC Bulletin 88-002, Rapidly Propagating Fatique Cracks in Steam Generator Tubes. ML20043B1101990-05-17017 May 1990 Documents Status of Evaluations Committed to Be Performed Re IE Bulletin 79-14 Program.Support CH-151-4-H50 Modified During Unit 1 Refueling Outage & Now in Code Compliance. Meeting Proposed During Wks of 900618 or 900716 ML20043A9921990-05-16016 May 1990 Advises of Typo in Item 2.C Re Emergency Diesel Generator Meter Accuracy in Submittal Re Corrective Actions in Response to Concerns Identified During Electrical Insp.Meter Calibr Reading Should Be 3,050 Kw Not 350 Kw ML20043B0481990-05-16016 May 1990 Updates 890330 Response to NRC Bulletin 88-010, Nonconforming Molded Case Circuit Breakers. Util Will Replace Unit 1 Inverter & Battery Charger Circuit Breakers within 30 Days After Receipt & QA Verification ML20043A7631990-05-15015 May 1990 Responds to Notice of Violation & Forwards Civil Penalty in Amount of $87,000 for Violations Noted in Insp Repts 50-266/89-32,50-266/89-33,50-301/89-32 & 50-301/89-33. Addl Employees Added in QA & Corporate Nuclear Engineering ML20042H0201990-05-10010 May 1990 Forwards List of Concerns Identified at 900417 Electrical Insp Exit Meeting to Discuss Preliminary Findings of Special Electrical Insp Conducted on 900319-0412 Re Adequacy of Electrical Distribution Sys ML20043A2181990-05-10010 May 1990 Forwards Nonproprietary & Proprietary Version of Point Beach Nuclear Plant,Emergency Plan Exercise,900314. ML20042G7441990-05-0909 May 1990 Forwards LER 90-003-00 ML20042G7361990-05-0808 May 1990 Forwards LER 90-004-00 ML20042E4571990-04-10010 April 1990 Documents Basis for Request for Temporary Waiver of Compliance of Tech Spec 15.3.7.A.1.e Re Diesel Generator Fuel Oil Supply ML20012F2961990-03-29029 March 1990 Withdraws Tech Spec Change Request 120 Re Staff Organization Changes & Deletion of Organizational Charts,Based on Further Corporate Restructuring within Util ML20012D8301990-03-20020 March 1990 Responds to Generic Ltr 89-19, Safety Implication of Control Sys in LWR Nuclear Power Plants. No Limiting Condition for Operation Required for Overfill Protection Sys at Plant ML20012D4241990-03-0808 March 1990 Forwards Public Version of Revised Epips,Including Rev 17 to EPIP 1.3,Rev 8 to EPIP 3.1,Rev 15 to EPIP 4.1,Rev 1 to EPIP 6.7,Rev 1 to EPIP 7.1,Rev 11 to EPIP 7.2.1 & Rev 11 to EPIP 7.2.2 ML20011F7531990-02-26026 February 1990 Informs NRC of Apparent Inconsistency Between Min Level of Boric Acid Solution to Be Maintained in Boric Acid Storage Tanks Per Tech Specs & Amount of Deliverable Boric Acid Assumed in Safety Analyses ML20006B7091990-01-25025 January 1990 Responds to NRC Bulletin 89-002 Re Check Valve Bolting Insp. All Anchor-Darling Model S35OW Check Valves Inspected for Cracked Internal Bolting During Refueling Outage of Unit.No Indications of Cracks Found ML20006A3381990-01-18018 January 1990 Forwards PDR & Central Files Versions of Rev 16 to EPIP 9.2 & Forms, Radiological Dose Evaluation. ML20006A3411990-01-16016 January 1990 Forwards Rev 16 to EPIP 9.2, Radiological Dose Evaluation to Be Inserted in EPIP Manual ML20005G0901990-01-12012 January 1990 Responds to Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment. Outside of Intake Structure Will Be Inspected for Excessive Corrosion on Semiannual Basis & Forebay & Pumphouse Inspected ML20005G1751990-01-12012 January 1990 Responds to NRC 891213 Ltr Re Violations Noted in Insp Repts 50-266/89-30 & 50-301/89-30.Corrective Action:Procedure RP-6A, Steam Generator Crevice Flush (Vacuum Mode), Initiated ML20005H0551990-01-11011 January 1990 Responds to NRC Bulletin 89-003, Potential Loss of Required Shutdown Margin During Refueling Operations. Util Will Provide Specific Training to All Members Responsible for Refueling Operation to Emphasize Importance of Procedures ML20005G9031990-01-0909 January 1990 Forwards Monthly Operating Repts for Dec 1989 for Point Beach Nuclear Plant Units 1 & 2 & Revised Monthly Operating Rept for Nov for Point Beach Unit 2 ML20005G5641990-01-0808 January 1990 Updates Progress Made on Issues Discussed in Insp Repts 50-266/89-12 & 50-301/89-11 Re Emergency Diesel Generator Vertical Slice SSFI Conducted by Util.By Jul 1990,revised Calculation Re as-built Configuration Will Be Performed ML20005E5441989-12-29029 December 1989 Describes Actions & Insps Completed During Recent U2R15 Refueling Cycle & Proposed Schedule for Completion of NRC Bulletin 88-008 Requirements,Per Util 881221 & 890616 Ltrs. Extension Requested Until 900631 to Submit Data Evaluation ML20005E5451989-12-28028 December 1989 Advises That Addl Info Required from Westinghouse to Meet Util 890621 Commitment to Adopt Administrative Control Re Rapidly Propagating Fatigue Cracks in Steam Generator Tubes Per NRC Bulletin 88-002.Info Anticipated by End of Mar 1990 ML20005E5381989-12-27027 December 1989 Provides Update of Status of Implementation of Resolution of Human Engineering Discrepancies Documented During Dcrdr. Lighting Intended to Document Deficiencies Per NUREG-0700, Eleven Human Engineering Discrepancy Computers Resolved ML19354D5781989-12-21021 December 1989 Certifies Implementation of Fitness for Duty Program Which Meets Requirements of 10CFR26 for All Personnel Having Unescorted Access to Plant Protected Areas.Periodic Mandatory Random Chemical Testing Will Commence on 900103 ML20005D8071989-12-21021 December 1989 Forwards Response to Violations Noted in Insp Repts 50-266/89-29 & 50-301/89-29.Response Withheld (Ref 10CFR73.21) ML20005E2301989-12-21021 December 1989 Forwards Reactor Containment Bldg Integrated Leak Rate Test Point Beach Nuclear Plant Unit 2, Summary Rept,Per 10CFR50,App J.Type A,B & C Leak Test Results Provided ML20042D2391989-12-21021 December 1989 Responds to Violations Noted in Insp Repts 50-266/89-27 & 50-301/89-26.Corrective Actions:Superintendent of Health Physics Discussed Log Book Entry Requirements W/Health Physics Contractor Site Coordinator ML19354D6231989-12-15015 December 1989 Responds to Generic Ltr 89-10 Re safety-related motor- Operated Valve Testing & Surveillance.Util Intends to Meet All Recommendations Discussed in Ltr Except for Item C Re Changing motor-operated Valve Switch Settings 1990-09-05
[Table view] |
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Wisconsin Electnc mcwmr 231 W. MICHIG AN, P O. BOX 2046, MILWAUKEE.W153201 (414)277-2345 VPNPD-86-432 NRC-86-102 October 27, 1986 Mr. H. R. Denton, Director Office of Nuclear Reactor Regulation U. S. NUCLEAR REGULATORY COMMISSION Washington, D. C. 20555 Attention: Mr. George Lear, Director PWR Project Directorate 1 Gentlemen:
DOCKETS 50-266 AND 50-301 ASME SECTION XI, RELIEF REQUESTS
- POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 In accordance with 10 CFR 50.55a(g)(5)(iii), Wisconsin Electric Power Company (licensee) requests inservice inspection relief for the second ten-year inspection interval for Point Beach Nuclear Plant, Units 1 and 2.
Attachment 1 provides the supportive information for the relief request from specific 1977/ Summer, 1979 Edition / Addenda of ASME Section XI code requirements for Unit 1. Attachment 2 provides the supportive information for the relief request from specific ASME Section XI code requirements for Unit 2. Wisconsin Electric requests that the Commission review these relief requests and provide approval as required by the Commission's regulations.
! Enclosed is a check in the amount of $150 for the l application fee required by 10 CFR Part 170.
l l Please contact us if any additional information is needed.
Very trul ours, C. W. Fy Vice Presi ent Nuclear Power /
Enclosures (Check 928681)
Copy to Resident Inspector 0] h l
ATTACHMENT 1 UNIT 1 RELIEF REQUEST Relief Request No. Description RR-1-12 Regenerative Heat Exchanger Class 1 Shell and Nozzle Welds
=
RR-1-12 Component Regenerative Heat Exchanger Exam Area Class 1 Tubesheet to Shell Welds Class 1 Nozzle to Shell Welds Isometric or Component Drawing Fig. A-7 ASME Section XI Category .
B-B B-D ASME Section XI Item Number B2.60 B3.150 ASME Section XI Examination Requirement A volumetric examination of 100% of all tubesheet welds and nozzle welds during the second 10 year interval.
Alternative Examination A volumetric examination of accessible portions of all tubesheet welds and nozzle welds equivalent to one of the three identical sections of the regenerative heat exchanger during the second 10-year interval.
Reason for Limitation The regenerative heat exchanger (RHE) provides the major single source of .
radiation exposure accumulated during a nominal refueling outage inservice inspection project. The " regenerative heat exchanger" is actually three shell-and-tube heat exchangers connected in series. The RHE is designed to recover heat from the reactor coolant system letdown stream by reheating the charging stream during normal operation. The letdown stream flows through the shell of the RHE and the charging stream flows through the tubes.
To ensure adequate coverage of the component welds with a minimum of exposure, the multiple stream concept should be carried out in all the examination catagories. Currently only one of three Class 1 cap-to-shell welds, Class 2 cap-to-shell welds, Class 2 tubesheet-to-shell welds, and two of six Class 2 nozzle-to-shell welds are examined in accordance with allowances in IWB-2500 and IWC-2500 of ASME Section XI. By extending the multiple stream concept to the Class 1 tubesheet-to-shell and nozzle-to-shell welds, a good cross-section of the regenerative heat exhanger would be examined while a significant reduction in radiation exposure from this component would be achieved.
Following are some of the items that have been taken into consideration in the preparation of this request.
- 1. Radiation Levels Currently, the average dose rates at the regenerative heat exchanger are:
1.5 rem /hr general area (at 18")
4.0 rem /hr insulation surface (on contact) 7.0 rem /hr shell surface (on contact under the insulation)
- 2. Total Estimated Man-Rem Exposure Involved In the Examination Considering the tasks associated with conducting an examination on a particular examination area, the following time intervals have been required in the past:
t 0.2 man hours for insulation removal 0.1 man hours for weld cleaning and preparation 0.7 man hours for conducting the examination 0.2 man hours for insulation replacement Using the preceding dose rates and times, the following whole body and extremity exposures can be calculated per examination:
l
Reason for Limitation Page 2 Whole Body (using general area dose rates) :
1.5 rem /hr for insulation removal of 0.2 man hours = 0.3 man-rem 1.5 rem /hr for weld cleaning and preparation of 0.1 man hours = 0.15 man-rem 1.5 rem /hr for the examination of 0.7 man hours = 1.05 man -rem 1.5 rem /hr for insulation replacement of 0.2 man hours = 0.3 man-rem Total Whole Body Dose Per RHE Exam = 1.8 man-rem Extremities (hands, using contact dose rates):
4.0 rem /hr for insulation removal of 0.2 man hours = 0.8 man-rem 7.0 rem /hr for weld cleaning and preparation of 0.1 man hours = 0.7 man-rem 7.0 rem /hr for the examination of 0.7 man hours = 4.9 man-rem 4.0 rem /hr for insulation replacement of 0.2 man hours = 0.8 man-rem Total Extremities Dose Per RHE Exam = 7.2 man-rem The exposure savings per inspection interval, by a reduction of six examinations, would be 10.8 man-rem whole body and 43.2 man-rem extremities.
- 3. Shielding When exposure is utilized to place lead blankets and shields over non-examination areas of the RHE, the general area dose rates are reduced by approximately 50%, but the dose rates are still the highest encountered during an inservice inspection project. Also, the examiner who is conducting the examination does not have the benefit of the shielding.
- 4. Alternative Examinations Instead of examining all three Class 1 tubesheet-to-shell welds and all six class 1 nozzle-to-shell welds, we propose to examine tubesheet-to-shell weld RHE-2 and nozzle-to-shell welds RHE-N1 (inlet) and RHE-N4 (outlet). These welds are all located on the bottom heat exchanger (see Appendix l-A for an outline of the RHE and weld locations).
The bottom shell welds should be the ones to be inspected for two reasons. First of all, the bottom heat exchanger operates at the highest temperature of the three and is therefore the most highly stressed. Typical operating temperatures for letdown flow are 538aF into the bottom shell and 252*F out of the top shell. Secondly, the
. - . - - . _ _.- .~
. j
.~'
Reason for Limitation 4
Page 3 bottom shell welds can generally be more extensively inspected than the other shell welds. This can be seen by looking at the tables contained in Appendix l-B, which show the examination methods performed in the past and the coverage obtainable for each of the welds.
Not only does the information in Appendix l-B show the best welds to examine, it also shows that the coverage of some of the welds for which we are requesting relief is substantially limited. For example, using the terminology in the Appendix, only 25% of weld RHE-N9 can be examined by OL, 45, and 60 techniques. The fact that these limitations exist for some of the RHE welds is another point in favor of granting the relief request.
. 5. Previous Inspection Results Simply stated, all indications which were recorded during inspections
}' to this point were found to be either insignificant or geometric in nature. An insignificant indication is either a non-relevant
- indication or an indication which is equal to or greater than the
- examination recording level but less than the evaluation level.
l 6. Consequences of Weld Failure The consequences of a failure of one of the RHE welds have essentially been addressed in the plant's Final Safety Analysis i Report (FSAR). In the FSAR, to evaluate chemical and volume control
, system (CVCS) safety, failures or malfunctions were assumed I
concurrent with a loss of coolant accident (LOCA) and the consequences analyzed. A LOCA and a concurrent RHE weld failure is j included in the more general catagory of a rupture in the CVCS line
- inside containment. During such an occurrence, the remote-operated valve located near the main coolant loop, upstream of the RHE, is closed on low pressurizer level to prevent supplementary loss of coolant through the letdown line rupture. The RHE would also
, eventually be isolated, with leakage being confined to containment, i
(
in the case of a weld failure without a LOCA.
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i APPENDIX l-A J
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t I
a l
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I I r l
ItET. SENTRT DWC.
A04195-A01-2 & A01-4 CVC -2*LD-1002 1
CLASS 1 al- CLASS 2 l
l RHt-NI2 ,y RHt-N tt -
( RHE-3 RHE-f t
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l MHE-C RHe-12
( , SHELL SUPPORT NO. 4-= =
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SHELL SUPPCRT-* pSRME-Ng RHe-N to NO- I CVC-3-t.0-1001 L
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, Rat-Ne y.l3 , j RHe-wr
('~ 1 f RHt-S RHe-s Rus-r )
( ar SHELL SUPPORT NC. 5 - -
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1 CVC 2 LC-1001 REGENERATIVE HEAT EXCHANGER FIGURE A-7 A-7
_ ___ _ _ _ _ .. _ .._ _ ___ _ _ . . _ . _ . . __.____.._m .__ __ . ___ - - _ _ ___ _. ... . .. m. ..___..___.. . .. _ .
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PoS T OFFICE OR AWER 28S10
- 6220 CULESR A RO AD . S AN ANTONIO. TEM AS US A 78284. e512t 684 SII1.f ELEx 76 7357 /, l' ~l OUAUTV ASSURAhCISYSTEMS TELD M7208 NUC ENGR $NT A A8s0 ENGisettniseo orvits0N TELD 7675M NUC FNGR ENT TELECOF'tR M January 9,1985 Doc. No. 17-7472(22)
Mr. Steve Pullins Wisconsin Electric Power Company
{ //. /4 . A * / f e Point Beach Nuclear Plant h/* [8. f/
6610 Nuclear Road Two Rivers, Wisconsin 54241 Subjact: Summary cf the Regenerative Heae Exchanger (REE)
Examinations Units 1 and 2 Performed at Point Beach Nuclear Plant.
Dear Mr. Pullins:
Enclosed is a summary of the RHE examinations performed to date at Point Beach Nuclear Plant, Units 1 and 2. This information is provided to assist you in the preparation of a relief request to be submitted to the U.S. Nuclear Regulatory Commission. This package consists of two tables, one each for Units 1 and 2. Each table consists of the following: veld number, category, limitation, resson for limitation,Section II examination methoi required, examination method performed and Section II coverage. An explanaticn of the table hesdings and terminology used precedes the tables.
If any additional information is needed, or if we can be of any further assistance, please contact us.
Sincerely,
. y_
Rodn y M. Weber Project Manager Inspection Engineering Section Department of Engineering Services CE/kp t
I Enclosures s.
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TABLE HEADINGS WELD NUMBER - THE NUMBER DESIGNATED TO EACH SPECIFIC WELD BY WISCONSIN ELECTRIC POWER COMPANY CATEGORY - EACH WELD FALLS INTO A SPECIFIC CATEGORY, AS PER ASME 1977/S79 SECTION II CODE LIMITATION - WHEN FULL COVERAGE CANNOT BE ACHIEVED DURING THE EXAM-INATION OF A WELD-REASON FOR LIMITATION - THE SPECIFIC REASON WHY FULL COVERAGE CANNOT BE ACHIEVED.
EXAMPLES: 1) RESTRAINT - WHEN A RESTRAINT IS LOCATED WITHIN OR ADJACENT TO THE EXAM AREA, THEREFORE RESTRICTING FULL COVERAGE
- 2) SUPPORT - WHEN A SUPPORT IS LOCATED WITHIN OR ADJACENT TO THE EXAM AREA, THEREFORE RESTRICTING FULL COVERAGE
- 3) WELD CONFIGURATION - WHEN THE DESIGN OR "AS WELDED CONDITION" 0F THE WELD IN QUESTION PREVENTS FULL COVERAGE 4)N0ZZLE CONFIGURATION - WHEN THE N0ZZLE DESIGN PREVENTS FULL COVERAGE OF IHE EXAM AREA
- 5) TUBE SHEET CONFIGURATION - WHEN THE TUBE SHEET DESIGN PREVENTS EXAMINATION FROM ONE SIDE OF THE WELD
- 6) CAP CONFIGURATION - WHEN A CAP DESIGN OR CAP CURVATURE PREVENTS FULL COVERAGE
- 7) CURVATURE - WHEN THE RADIUS OF A COMPONENT IS SUCH THAT CURVATURE DOES NOT ALLOW PROPER EXAMINATION SECTION II EXAMINATION METHOD - THE SPECIFIC TYPE OF EXAMINATION RM UIRED BY 1977/S79 SECTION XI CODE EXAMINATION PERFORMED - THE TYPE OF EXAMINATION PERFORMED ON THE WELD SECTION II COVERAGE - THESE NUMBERS ARE CALCULATED AS A PERCENTAGE (EXAMINATION AREA COVERED DIVIDED BY EXAMINATION AREA RM UIRED). THE EXAMINATION AREA RMUIRED IS DETERMINED BY THE SECTION XI CODE RM UIREMENTS. THE EXAMINATION AREA I
COVERED IS DETERMINED BY QUANTITY AND TYPE OF LIMITATIONS EXAMPLES: 1)IF A LIMITATION PREVENTED EXAMINATION OF ONE SIDE OF THE WELD AREA, EITHER UPSTREAM OR DOWN-STREAM, THEN THE SECTION XI COVERAGE FOR THAT EXAMINATION IS 50%.
2)IF A LIMITATION PREVENTED THE EXAMINATION OF 4.5 INCHES OF WELD LENGTH ON A WELD 18.5 INCHES LONG, THEN THE SECTION XI COVERAGE IS 75% (14 DIVIDED BY 18.5 = .757) .
l IT SHOULD BE NOTED THAT, WHEN CALCULATING 63%, 64%, 66%, 69%, 74%, 75%,
AND 80%, EXACT NUMBERS WERE AVAILABLE FOR CALCULATION (i.e. EXAMPLE 2 ABOVE). HOWEVER, 25% AND 50% ARE APPROXIMATIONS WHICH WERE MADE USING THE DATA AVAILABLE (i.e. EXAMPLE 1 ABOVE).
IT SHOULD ALSO BE NOTED THAT THERE ARE DIFFERENCES IN COVERAGE AND LIMITATIONS BETWEEN UNITS 1 AND 2. THIS IS DUE PRIMARILY TO THE "AS
BUILT CONDITION" 0F THE WELDS IN QUESTION.
TERMIN0LOGT FULL COVERACE - WHEN 100% OF THE RMUIRED COVERAGE AREA IS EXAMINED FROM BOTH SIDES OF THE WELD DENOTES VISUAL EXAMINATIONS WHICH WERE PERFORMED AS PER RM UIREMENTS OF THE TECHNICAL SPECIFICATIONS
($) -
DENOTES THAT THE WELD WAS EXAMINED ONCE DURING THE FIRST INTERVAL AND ONCE DURING THE SECOND INTERVAL (f)
DENOTES THAT THE WELD WAS EXAMINED TWICE DURING THE FIRST INTERVAL
(+) -
DENOTES THAT THE WELD WAS EXAMINED ONLT DURING THE SECOND INTERVAL UT -
MANUAL ULTRASONIC EIAMINATION VT -
VISUAL EIAMINATION PT -
LIQUID PENETRANT EIAMINATION UP -
DENOTES THE UPSTREAM SIDE OF THE WELD D -
DENOTES THE DOWNSTREAM SIDE OF THE WELD OL -
0 DEGREE LAMINATION SCAN ON THE BASE METAL OW -
0 DEGREE WELD SCAN ON THE WELD METAL 45 -
45 DEGREE SHEAR WAVE SCAN PERPENDICULAR TO THE WELD FROM THE BASE METAL SIDE (S) 0F THE WELD 45T -
45 DEGREE SHEAR WAVE SCAN PARALLEL TO THE WELD FROM THE BASE METAL SIDE (S) 0F THE UELD AND ON THE WELD i
60 -
60 DEGREE SHEAR WAVE SCAN PERPENDICULAR TO THE WELD FROM THE t
BASE METAL SIDE (S) 0F THE WELD
POINT BEACH UNIT 1 NOTE: ALL INDICATIONS WHICH WERE RECORDED ON RHE WERE IVUND TO BE EITHER INSIGNIFICANT OR GEOMETRIC IN NATURE.
SEC.XI WELD REASON FOR NUMBER EXAM EXAM SEC. II CATGY LIMITATION LIMITATION METHOD PERFORMED COVERAGE RHE-1 B-B NO OL UP SUPPORT UT *VT - UT 100% OW, No 45,60 D CURVATURE 45T 50% OL, 45, o0 RHE-2($) B-B NONE UT *VT - UT 100%
RHE-3 B-B NONE UT *VT - UT 100%
REE-4 B-B NO 45,60 UP CURVATURE UT *VT - UT 100% OF, OL, 45T 50% 45, j
60 4
RHE-5 B-B No 45,60 UP CURVATURE UT *VT - UT 100% OW, OL, 45T 50% 45, '
60 RHE-6 B-B NONE UT *VT - UT 100%
RHE-7 B-B NONE UT *VT - UT 100%
- RHE-8 B-B NONE UT *VT - UT
' 100%
RHE-9($) B-B No 45,60 UP CURVATURE UT *VT - UT 100% OW, OL, 45T 50% 45, 60 RHE-10 B-B NONE UT *VT - UT 100%
REE-11 B-B NONE UT *VT - UT 100%
i RHE-12 B-B NONE UT *VT - UT 100%
l RHE-N1 B-D NO OW,45T, WELD.CONFIG. UT UT 100% OL i
60 80% 45 LIMITED 45 SUPPORT RHE-N2(f) B-D NO 45T, 60 WELD CONFIG. UT UT 100% OL, No 45 D N0Z. CONFIG. 0W 50% 45 REE-N3 5-D NO 45T, 60 WELD CONFIG. UT UT 100% OL, No 45 UP N0Z. CONFIG. OW 50% 45 RHE-N4 B-D NO 45T, 60 WELD CONFIG. UT UT 100% OL, No 45 D N0Z. CONFIG. 0W 50% 45 RHE-N5 B-D NO OW,45T WELD CONFIG. UT UT 25% OL, LIMITED OL, SUPPORT 45,60 45, 60 l RHE-N6 B-D NO 45T,60 WELD CONFIG. UT UT 100% OW l NO OL,45 D N0Z. CONFIG. 50% OL, 45 RHE-N7 B-D No 0L,45 UP N0Z. CONFIG. UT UT 100% OW NO 45T, 60 WELD CONFIG. 50% OL, 45 RHE-N8 B-D NO 0L,45 D N0Z. CONFIG. UT UT 100% OW
( NO 45T, 60 WELD CONFIG. 50% OL, 45 I
. RHE-N9($) B-D No CW,45T WELD CONFIG. UT UT 25% OL, LIMITED OL, SUPPORT 45,60 45,60 REE-N10 B-D NO OL,45 D N0Z . CONFIG . UT UT 100% OW NO 45T, 60 WELD CONFIG. 50% OL, 45 RHE-Nil B-D NO OL,45 D N0Z. CONFIG. UT UT 100% OW NO 45T, 60 WELD CONFIG. 50% OL, 45 REE-N12(f) B-D NO 45T, 60 WELD CONFIG. UT UT 63% OL, LIMITED OL, SUPPORT OW,45 OW, 45 SUPPORT ($ ) 1-H NONE UT VT 0%
SUPPORT ($ ) B-H NONE UT VT 0%
SUPPORT ($) B-H NONE UT VT 0%
REE-Nil (+) C-B NO OL,45, N0Z. CONTIG. SURFACE UT-PT 100% OW, 45T N0Z. SIDE AND UT PT 50% 45, 45T SUPPORT 1(+) F-A NONE VT-3 VT-3 100:
SUPPORT 5(+) F-B NONE VT-3 VT-3 100%
l
POINT BEACH UNIT 2 NOTE: ALL INDICATIONS WHICH WERE RECORDED ON RHE WERE MUND TO BE EITHER INSIGNIFICANT OR GEOMETRIC IN NATURE.
- ****** :. :. :. :. ; ; :. ; ; :. :. :. ; :. :. :. ;. ***************** **** *** * *********** s* ** *** * ** **
SEC.II WELD REASON MR EXAM EXAM SEC. XI NUMBER CATGT LIMITATION LIMITATION METHOD PERFORMED COVERAGE RHE-1 B-B NO OL,0W,45, SUPPORT UT *VT 0%
45T,6 0 RHE-2 B-B LIMITED OL, TUBE SHEET UT *VT - UT 50% OL, 45,45T,60 CONFIG. 0W,45, LIMITED OW SUPPORT 45T,60 RHE-3 B-B NONE UT *VT - UT 100%
RHE-4 B-B NONE UT *VT - UT 100%
RHE-5 B-B NO OL,45, CAP. CONFIG. UT *VT - UT 100% OW 45T,60 UP 50% OL, 45,45T,60 RHE-6 B-B LIMITED OL, N0Z. CONFIG. UT *VT - UT 100% OW 45,45T,60 UP 75% OL NO 45,45T, RESTIAINT 25% 45, 60 D 45T,60 RHE-7 B-B NO 0L,45, RESTRAINT UT *VT - UT 100% OW 45T,60 UP 50% OL, 45,45T,60 RHE-8 B-B NO 0L,45, CAP. CONFIG. UT *VT - UT 100% OW 45T,60 50% OL, 45,45T,60 RHE-9 B-B NONE UT UT 100%
RHE-10 B-B LIMITED OL, SUPPORT UT UT 45% OL, 45,60 45,60 NO OW,45T SUPPORT RHE-11 B-B LIMITED OL, SUPPORT UT UT 100% OW 45,45T,60 75% OL, 45,45T,60 RHE-12 B-B NONE UT UT 100%
RHE-N1($) B-D LIMITED OL SUPPORT UT UT 100% OW, NO 45T UP N0Z. CONFIG. 45 NO 60 WELD CONFIG. 66% OL 50% 45T RHE-N2 B-D LIMITED OL SUPPORT UT UT 100% OW, No 45T UP N0Z. CONFIG. 45 NO 60 WELD Q)NFIG. 66% OL 50% 45T RHE-N3 B-D No 45T UP N02. CONFIG. UT UT 100% OL, NO 60 WELD CONFIG. 0W 50% 45T RHE-N4($) B-D NO 45T UP N0Z. CONFIG. UT UT 100% OL, NO 60 WELD CONFIG. 0W 50% 45T RHE-N5 B-D LIMITED OL, RESTRAINT UT UT 75% OL, 45 45 NO OW,45T WELD CONFIG.
RHE-N6 B-D LIMITED OL, RESTRAINT UT UT 75% OL,
45 45 NO OW,45T WELD CONFIG.
, RHE-N7 B-D LIMITED OL RESTRAINT UT UT 64% OL NO OW,45T RESTRAINT 50% 45 NO 45 UP WELD CONFIG.
RHE-N8 B-D LIMITED OL RESTRAINT UT UT 69% OL NO OW,45T RESTRAINT 100% 45 RHE-N9 B-D LIMITED OL, SUPPORT UT UT 74% OL, 0W,45,45T OW,45,45T RHE-NIO B-D NONE UT OT 100%
REE-Nil B-D NONE UT UT 100%
REE-N12 B-D LIMITED OL, SUPPORT UT UT 100% OW 45,45T 75% OL, 45,45T SUPPORT B-H NONE UT VT 0%
SUPPORT B-H NONE UT VT 0%
SUPPORT B-H NONE UT VT 0%
SUPPORT 3(+)B-H NONE UT VT-3 0%
REE-N11(+) C-B LIMITED OL, N0Z. CONFIG. SURFACE UT-PT 100% OW, 45,45T AND UT PT 50% 45, 45T
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ATTACHMENT 2 UNIT 2 RELIEF REQUEST Relief Request No. Description RR-2-12 Regenerative Heat Exchanger Class 1 Shell and Nozzle Welds 4
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RR-2-12 Component Regenerative Heat Exchanger Exam Area Class 1 Tubesheet to Shell Welds Class 1 Nozzle to Shell Welds Isometric or Component Drawing Fig. A-7 ASME Section XI Category l B-B B-D ASME Section XI Item Number B2.60 B3.150 ASME Section XI Examination Requirement A volumetric examination of 100% of all tubesheet welds and nozzle welds during the second 10-year interval.
Alternative Examination A volumetric examination of accessible portions of all tubesheet welds and nozzle welds equivalent to one of the three identical sections of the regenerative heat exchanger during the second 10 year interval.
Reason for Limitation The regenerative heat exchanger (RHE) provides the major single source of radiation exposure accumulated during a nominal refueling outage inservice inspection project. The " regenerative heat exchanger" is actually three shell-and-tube heat exchangers connected in series. The RHE is designed to recover heat from the reactor coolant system letdown stream by reheating the charging stream during normal operation. The letdown stream flows through the shell of the RHE and the charging stream flows through the tubes.
To ensure adequate coverage of the component welds with a minimum of exposure, the multiple stream concept should be carried out in all the examination catagories. Currently only one of three Class 1 cap-to-shell welds, Class 2 cap-to-shell welds, Class 2 tubesheet-to-shell welds, and two of six Class 2 nozzle-to-shell welds are examined in accordance with allowances in IWB-2500 and IWC-2500 of ASME Section XI. By extending the multiple stream concept to the Class 1 tubesheet-to-shell and nozzle-to-shell welds, a good cross-section of the regenerative heat exhanger would be examined while a significant reduction in radiation exposure from this component would be achieved.
Following are some of the items that have been taken into consideration in the preparation of this request.
- 1. Radiation Levels Currently, the average dose rates at the regenerative heat exchanger are:
1.5 rem /hr general area (at 18")
4.0 rem /hr insulation surface (on contact) 7.0 rem /hr shell surface .(on contact under the insulation)
- 2. Total Estimated Man-Rem Exposure Involved In the Examination Considering the tasks associated with conducting an examination on a j particular examination area, the following time intervals have been 4 required in the past:
0.2 man hours for insulation removal i 0.1 man hours for weld cleaning and preparation 0.7 man hours for conducting the examination 0.2 man hours for insulation replacement Using the preceding dose rates and times, the following whole body and extremity exposures can be calculated per examination:
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Reason for Limitation Page 2 Whole Body (using general area dose rates):
a 1.5 rem /hr for insulation removal of 0.2 man hours = 0.3 man-rem 1.5 rem /hr for weld cleaning and preparation of 0.1 i
man hours = 0.15 man-rem 1.5 rem /hr for the examination of 0.7 man hours = 1.05 man-rem 1.5 rem /hr for insulation replacement of 0.2 man hours = 0.3 man-rem Total Whole Body Dose Per RHE Exam = 1.8 man-rem I Extremities (hands, using contact dose rates) :
E 4.0 rem /hr for insulation removal of 0.2 man hours = 0.8 man-rem 7.0 rem /hr for weld cleaning and preparation of 0.1 man hours = 0.7 man-rem 7.0 rem /hr for the examination of 0.7 man hours = 4.9 man-rem
. 4.0 rem /hr for insulation replacement of 0.2 man hours = 0.8 man-rem Total Extremities Dose Per RHE Exam = 7.2 man-rem The exposure savings per inspection interval, by a reduction of six examinations, would be 10.8 man-rem whole body and 43.2 man-rem l extremities.
J
- 3. Shielding When exposure is utilized to place lead blankets and shields over non-examination areas of the RHE, the general area dose rates are j reduced by.approximately 50%, but the dose rates are still the highest encountered during an inservice inspection project. Also, the examiner who is conducting the examination does not have the benefit of the shielding.
, 4. Alternative Examinations
, Instead of examining all three Class 1 tubesheet-to-shell welds and all six class 1 nozzle-to-shell welds, we propose to examine tubesheet-to-shell weld RHE-2 and nozzle-to-shell welds RHE-N1 (inlet) and RHE-N4 (outlet). These welds are all located on the bottom heat exchanger (see Appendix 2-A for an outline of the RHE and weld locations) .
The bottom shell welds should be the ones to be inspected for two reasons. First of all, the bottom heat exchanger operates at the highest temperature of the three and is therefore the most highly
,' stressed. Typical operating temperatures for letdown flow are 538aF into the bottom shell and 252*F out of the top shell. Secondly, the
. _ . _ _ _ _ _ .. . .. - . - - _ . - = -_.
4 i
Reason for Limitation '
Page 3 4
bottom shell welds can generally be more extensively inspected than the other shell welds. This can be seen by looking at the tables I
contained in Appendix 2-B, which show the examination methods performed in the past and the coverage obtainable for each of the 3
welds.
Not only does the information in Appendix 2-B show the best welds to j examine, it also shows that the coverage of some of the welds for ,
L
. which we are requesting relief is substantially limited. For t
example, using the terminology in the Appendix, weld RHE-NS can be examined only by OL and 45 techniques to an extent of 75%. The fact that these limitations exist for some of the RHE welds is another point in favor of granting the relief request.
- 5. Previous Inspection Results
' Simply stated, all indications which were recorded during inspections to this point were found to be either insignificant or geometric in nature. An insignficant indication is either a non-relevant indication or.an indication which is equal to or greater than the j examination recording level but less than the evaluation level.
! 6. Consequences of Weld Failure The consequences of a failure of one of the RHE welds have essentially been addressed in the plant's Final Safety Analysis j Report (FSAR). In the PSAR, to evaluate chemical and volume control
- system (CVCS) safety, failures or malfunctions were assumed i
concurrent with a loss of coolant accident (LOCA) and the consequences analyzed. A LOCA and a concurrent RHE weld failure is i
included in the more general catagory of a rupture in the CVCS line inside containment. During such an occurrence, the remote-operated valve located near the main coolant loop, upstream of the RHE, is ~
closed on low pressurizer level to prevent supplementary loss of I
coolant through the letdown line rupture. The RHE would also eventually be isolated, with leakage being confined to containment, in the case of a weld failure without a LOCA.
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POST OFFICE DR AWER 28510 6220 CULE8 R A ROAD . S AN AN TONIO, tex A S. US A 78284. tS12) 664-5111* TELEX 76 7357 QUAUTV ASSURANCE SYSTEMS TELEX 767209 NUC ENGR $47 A AND ENGINEER NG DiveSION TELEX 787579 NUC ENGR $NT TELECOPtER 804 January 9,1985 Doc. No.17-7472(22)
Mr. Steve Pullins { /). /C . 3 * / fI 6 Wisconsin Electric Power Company Point Beach Nuclear Plant [t/' ((. V 6610 Nuclear Road Two Rivers, Wisconsin 54241
Subject:
Summary cf the Regenerative Heat Exchanger (RHE)
Examinations Performed at Point Beach Nuclear Plant, Units 1 and 2
Dear Mr. Pullins:
Enclosed is a suunnary of the RHE examinations performed to date at Point Beach Nuclear Plant, Units I and 2. This information is provided to assist you in the preparation of a relief request to be submitted to the U.S. Nuclear Regulatory Commission. This package consists of two tables, one each for Units 1 and 2. Each table consists of the following: weld number, category, limitation, reason for limitation,Section II examination method required, examination method performed and Section II coverage. An explanation of the table headings and terininology used precedes the tables.
If any additional information is needed, or if we can be of any further assistance, please contact us.
Sincerely,
[ ,r --
Roda y M. Weber Project Manager Inspection Engineering Section Department of Engineering Services CE/kp Enclosures WQ T
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TABI.E HEADINGS WELD NUMBER - THE NUMBER DESIGNATED TO EACH SPECIFIC WELD BY WISCONSIN ELECTRIC POWER COMPANY CATEGORY - EACH WELD FALLS INTO A SPECIFIC CATEGORY, AS PER ASME 1977/S79 SECTION XI CODE LIMITATION - WHEN FULL COVERAGE CANNOT BE ACHIEVED DURING THE EXAM-INATION OF A WELD REASON FOR LIMITATION - THE SPECIFIC REASON WHY FULL COVERAGE CANNOT BE ACHIEVED.
EXAMPLES: 1) RESTRAINT - WHEN A RESTRAINT IS LOCATED WITHIN OR ADJACENT TO THE EXAM AREA, THEREFORE RESTRICTING FULL COVERAGE
- 2) SUPPORT - WHEN A SUPPORT IS LOCATED WITHIN OR ADJACENT TO THE EXAM AREA, THEREFORE RESTRICTING FULL COVERAGE
- 3) WELD CONFIGURATION - WHEN THE DESIGN OR "AS WELDED CONDITION" 0F THE WELD IN QUESTION PREVENTS FULL COVERAGE 4)N0ZZLE CONFIGURATION - WHEN THE N0ZZLE DESIGN PREVENTS FULL COVERAGE OF IHE EXAM ARIA
- 5) TUBE SHEET CONFIGURATION - WHEN THE TUBE SHEET DESIGN PREVENTS EXAMINATION FROM ONE SIDE OF THE WELD
- 6) CAP CONFIGURATION - WHEN A CAP DESIGN OR CAP CURVATURE PREVENTS FULL COVERAGE
- 7) CURVATURE - WHEN THE RADIUS OF A COMPONENT IS SUCH THAT CURVATURE DOES NOT ALLOW PROPER EXAMINATION SECTION XI EXAMINATION METHOD - THE SPECIFIC TYPE OF EXAMINATION RMUIRED BY 1977/S79 SECTION XI CODE EXAMINATION PERFORMED - THE TYPE OF EXAMINATION PERFORMED ON THE WELD SECTION XI COVERAGE - THESE NUMBERS ARE CALCULATED AS A PERCENTAGE (EXAMINATION AREA COVERED DIVIDED BY EXAMINATION AREA RMUIRED). THE EXAMINATION AREL EQUIRED IS DETERMINED BY THE SECTION XI CODE RM UIREMF%'$. THE EXAMINATION AREA COVERED IS DETERMINED BY (2$ TJV AND TYPE OF LIMITATIONS EXAMPLES: 1)IF A LIMITh'I'J 1H ' OITED EXAMINATION OF ONE SIDE OF THE %.LD al.e, EITHER UPSTREAM OR DOWN-STREAM, THEN THE SECTION XI COVERAGE FOR THAT EXAMINATION IS 50%.
2)IF A LIMITATION PREVENTED THE EXAMINATION OF 4.5 INCHES OF WELD LENGTH ON A WELD 18.5 INCHES LONG, THEN THE SECTION XI COVERAGE IS 75% (14 DIVIDED BY 18.5 = .757) .
IT SHOULD BE NOTED THAT, WHEN CALCULATING 63%, 64%, 66%, 69%, 74%, 75%,
AND 80%, EXACT NUMBERS WERE AVAILABLE FOR CALCULATION (i.e. EXAMPLE 2 ABOVE). HOWEVER, 25% AND 50% ARE APPROXIMATIONS WHICH WERE MADE USING THE DATA AVAILABLE (i.e. EXAMPLE 1 ABOVE).
IT SHOULD ALSO BE NOTED THAT THERE ARE DIFFERENCES IN COVERAGE AND LIMITATIONS BETWEEN UNITS 1 AND 2. THIS IS DUE PRIMARILY TO IEE "AS
BUILT CONDITION" 0F THE WELDS IN. QUESTION.
TERMINOLOGY FULL COVERAGE - WHEN 100% OF THE REQUIRED COVERAGE AREA IS EXAMINED FROM BOTH SIDES OF THE WELD DENOTES VISUAL EXAMINATIONS WHICH WERE PERFORMED AS PER R R UIREMENTS OF THE TECHNICAL SPECIFICATIONS
($) -
DENOTES THAT THE WELD WAS EXAMINED ONCE DURING THE FIRST INTERVAL AND ONCE DURING THE SECOND INTERVAL (f) DENOTES THAT THE WELD WAS EXAMINED TWICE DURING THE FIRS'l INTERVAL
(+) -
DENOTES THAT THE WELD WAS EXAMINED ONLY DURING THE SECOND INTERVAL UT -
MANUAL ULTRASONIC EXAMINATION VT -
VISUAL EXAMINATION PT -
LIQUID PENETRANT EXAMINATION UP -
DENOTES THE UPSTREAM SIDE OF THE WELD D -
DENOTES THE DOWNSTREAM SIDE OF THE WELD OL -
0 DEGREE LAMINATION SCAN ON THE BASE METAL OW -
0 DEGREE WELD SCAN ON THE WELD METAL 45 -
45 DEGREE SHEAR WAVE SCAN PERPENDICULAR TO THE WELD FROM THE BASE METAL SIDE (S) 0F THE WELD 45T -
45 DEGREE SHEAR WAVE SCAN PARALLEL TO THE WELD FROM THE BASE METAL SIDE (S) 0F THE WELD AND ON THE WELD 60 -
60 DEGREE SHEAR WAVE SCAN PERPENDICULAR TO THE WELD FROM THE BASE METAL SIDE (S) 0F THE WELD
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,, POINT BEACH UNIT 1 NOTE: ALL INDICATIONS WHICH WERE RECORDED ON RHE WERE MUND TO BE EITHER INSIGNIFICANT OR GEOMETRIC IN NATURE.
SEC.XI WELD REASON FOR EXAM EXAM SEC. XI
, NUMBER CATGY LIMITATION LIMITATION METHOD PERFORMED COVERAGE RHE-1 B-B NO OL UP SUPPORT UT *VT - UT 100% OW, No 45,60 D CURVATURE 45T 50% OL, 45, 60 RHE-2($) B-B NONE UT *VT - UT 100%
RHE-3 B-B NONE UT *VT - UT 100%
RHE-4 B-B NO 45,60 UP CURVATURE UT *VT - UT 100% OW, OL, 45T 50% 45, 60 RHE-5 B-B NO 45,60 UP CURVATURE UT *VT - UT 100% OW, OL, 45T 50% 45, 60 REE-6 E-B NONE UT *VT - UT 100%
RHE-7 B-B NONE UT *VT - UT 100%
RHE-8 B-B NONE UT *VT - UT 100%
RHE-9($) B-B No 45,60 UP CURVATURE UT *VT - UT 100% OW, OL, 45T 50% 45, 60 REE-10 B-B NONE UT *VT - UT 100%
RHE-11 B-B NONE UT *VT - UT 100%
RHE-12 B-B NONE UT *VT - UT 100%
RHE-N1 B-D NO OW,45T, WELD.CONFIG. UT UT 100% OL 60 80% 45 LIMITED 45 SUPPORT RHE-N2(f) B-D No 45T, 60 WELQ CONFIG. UT UT 100% OL, NO 45 D N0Z. CONFIG. OW 50% 45 RHE-N3 B-D No 45T, 60 WELD CONFIG. UT UT 100% OL, NO 45 UP N0Z. CONFIG. 0W 50% 45 RHE-N4 B-D No 45T, 60 WELD CONFIG. UT UT 100% OL, No 45 D N0Z. CONFIG. 0W 50% 45 RHE-N5 B-D NO OW,45T WELD CONFIG. UT UT 25% OL, LIMITED OL, SUPPORT 45,60 45, 60 RHE-N6 B-D NO 45T,60 WELD CONFIG. UT UT 100% OW NO OL,45 D N0Z. CONFIG. 50% OL, 45 RHE-N7 B-D No OL,45 UP N0Z. CONFIG. UT UT 100% OW
- No 45T, 60 WELD CONFIG. 50% OL, 45 RHE-N8 B-D NO OL,45 D N0Z. CONFIG. UT UT 100% OW NO 45T, 60 WELD CONFIG. 50% OL, 45 e
..- RHE-N9($) B-D NO OW,45T WELD CONFIG. UT UT 25% OL,
.. LIMITED OL, SUPPORT 45,60 45,60 RHE-N10 B-D NO OL,45 D N0Z. CONFIG. UT UT 100% OW No 45T, 60 WELD CONFIG. 50% OL, 45 RHE-Nil B-D NO OL,45 D N0Z. CONFIG. UT UT 100% OW No 45T, 60 WELD CONFIG. 50% OL, 45 RHE-N12(f) B-D No 45T, 60 WELD CONFIG. UT UT 63% OL, LIMITED OL, SUPPORT OW,45 OW, 45 SUPPORT ($) B-H NONE UT VT 0%
SUPPORT ($) B-H NONE UT VT 0%
SUPPORT ($) B-H NONE UT VT 0%
RHE-Nil (+) C-B NO OL,45, N0Z. CONFIG. SURFACE UT-PT 100% OW, 45T N0Z. SIDE AND UT PT 50% 45, 45T SUPPORT 1(+) F-A NONE VT-3 VT-3 100%
SUPPORT 5(+) F-B NONE VT-3 VT-3 100%
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POINT BEACH UNIT 2 NOTE: ALL INDICATIONS WHICH WERE RECORDED ON RHE WERE EUND TO BE EITHER INSIGNIFICANT OR GEONETRIC IN NATURE.
SEC.XI WELD REASON M R EXAM EXAM SEC. XI NUMBER CATGY LIMITATION LIMITATION METHOD PERFORMED COVERAGE RHE-1 B-B NO OL,0W,45, SUPPORT UT *VT 0%
45T,60 RHE-2 B-B LIMITED OL, TUBE SHEET UT *VT - UT 50% OL, 45,45T,60 CONFIG. 0W,45, LIMITED OW SUPPORT 45T ,6 0 RHE-3 B-B NONE UT *VT - UT 100%
RHE-4 B-B NONE UT *VT - UT 100%
RHE-5 B-B NO OL,45, CAP. CONFIG. UT *VT - UT 100% OW 45T,60 UP 50% OL, 45,45T,60 RHE-6 B-B LIMITED OL, N0Z. (X)NFIG. UT *VT - UT 100% OW 45,45T,60 UP 75% OL NO 45,45T, RESTRAINT 25% 45, 60 D 45T,60 RHE-7 B-B NO OL,45, RESTRAINT UT *VT - UT 100% OW 45T,60 UP 50% OL, 45,45T,60 RHE-8 B-B NO OL,45, CAP. CONFIG. UT *VT - UT 100% OW 45T,60 50% OL, 45,45T,6 0 RHE-9 B-B NONE UT UT 100%
RHE-10 B-B LIMITED OL, SUPPORT UT UT 45% OL, 45,60 45,60 NO OW,45T SUPPORT RHE-Il B-B LIMITED OL, SUPPORT UT UT 100% OW
! 45,45T ,6 0 75% OL,
( 45,45T,60 i RHE-12 B-B NONE UT UT 100%
RHE-N1(S) B-D LIMITED OL SUPPORT UT UT 100% OW, NO 45T UP N0Z. CONFIG. 45 NO 60 WELD CONFIG. 66% OL 50% 45T RHE-N2 B-D LIMITED OL SUPPORT UT UT 100% OW, NO 45T UP N0Z. CONFIG. 45 NO 60 WELD CONFIG. 66% OL 50% 45T RHE-N3 B-D NO 45T UP N0Z. CONFIG. UT UT 100% OL, NO 60 WELD (X)NFIG. OW t 50% 45T l
RHE-N4($) B-D No 45T UP N0Z. CONFIG. UT UT 100% OL, l
NO 60 WELD CONFIG. 0W 50% 45T RHE-N5 B-D LIMITED OL, RESTRAINT UT UT 75% OL, 45 45 NO OW,45T WELD CONFIG.
RHE-N6 B-D LIMITED OL, RESTRAINT UT UT 75% OL,
45 -
45
.. NO OW,45T WELD CONFIG.
RHE-N7 B-D LIMITED OL RESTRAINT UT UT 64% OL NO OW,45T RESTRAINT 50% 45 NO 45 UP WELD CONFIG.
RHE-N8 B-D LIMITED OL RESTRAINT UT UT 69% OL NO OW,45T RESTRAINT 100% 45 RHE-N9 B-D LIMITED OL, SUPPORT UT UT 74% OL, OW,45,45T OW,45,45T RHE-NIO B-D NONE UT UT 100%
RHE-Nil B-D NONE UT UT 100%
RHE-N12 B-D LIMITED OL, SUPPORT UT UT 100% OW 45,45T 75% OL, 45,45T SUPPORT B-H NONE UT VT 0%
SUPPORT B-H NONE UT VT 0%
SUPPORT B-H NONE UT VT 0%
SUPPORT 3(+)B-H NONE UT VT-3 0%
RHE-Nil (+) C-B LIMITED OL, N0Z. CONFIG. SURFACE UT-PT 100% OW, 45,45T AND UT PT 50% 45, 45T 1
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