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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 eaara couraur 231 W. MICHIGAN, P.O. BOX 2046 MILWAUKEE, WI 53201 February 23, 1982 I
Mr. H. R. Denton, Director Office of Nuclear Reactor Regulation p U. S. NUCLEAR REGULATORY COMMISSION Washington, D. C. 20555 -
NUE
Dear Mr. Denton:
MAR 011M2a 5 DOCKET NO. 50-266 $ Bet COMPLETION OF FIRST TEN-YEAR INSERVICE INSPECTION INTERVAL /
- POINT BEACH NUCLEAR PLANT, UNIT 1 On December 20, 1981, the first inservice inspection interval for Point Beach Nuclear Plant Unit 1 was completed.
The Unit 1 first ten-year interval was extended from December 20, 1980 to December 20, 1981 to permit inspections to be concurrent with plant outages as allowed in Article IWA 2400 of the 1974 Edition up to and including the Summer 1975 Addenda of Section XI of the ASME Boiler & Pressure Vessel Code.
Enclosures 1 and 2 are a summary of the examinations performed during the first ten-year interval for Unit 1. Upon review of the summary of examinations performed, it is apparent that some deviations from the ASME Section XI Code occurred.
Prior to the third period, inservice inspection was performed in accordance with Technical Specification 15.4.2.B, included in Enclosure 3 for your reference. Third period inservice inspection work was performed at the direction of the NRC in accordance with the most restrictive provisions of either Specification 15.4.2.B or the inservice inspection plan Wisconsin Electric submitted to the NRC on May 20, 1977. The inservice inspection plan submitted to the NRC was written to the 1974 Edition (Summer 1975 Addenda) of ASME Section XI.
All of the Technical Specification and ASME Section XI inservice inspection interval requirements were met with only a few exceptions. Those exceptions are noted and explained in Enclosure 4.
The first ten-year inservice inspection interval require-ments for Unit 1, within the limits of practicality, were completed during the fall 1981 refueling outage. Wisconsin Electric's future intention is to perform the second interval inservice inspection 8
8203010283 820223 PDR ADOCK 05000266 O PDR b I
s Mr. H. R. Denton February 23, 1982 work in accordance with a ten-year plan currently being developed.
However, as noted in the following paragraphs, Wisconsin Electric has yet to receive final NRC approval to implement the inservice inspection requirements of ASME Section XI.
On February 17, 1977, Wisconsin Electric submitted Technical Specification Change Request No. 42 for Unit 1 to the NRC for review and approval. This Technical Specification change replaced Technical Specification 15.4.2.B in its entirety with revised language which followed NRC guidelines. Briefly, this change directs the licensee to perform inservice inspection and inservice testing of ASME Code Class 1, 2, and 3 components in accordance with ASME Section XI as required by 10 CFR 50.55a.
In addition, it directs that containment isolation valves be tested in accordance with Technical Specification 15.4.4 vice ASME Section XI, which fulfills 10 CFR 50 Appendix J requirements.
For your convenience, Enclosure 5 is a copy of Technical Specifica-tion Change Request No. 42 for your review.
Reactor vessel material surveillance shall be performed in accordance with Technical Specification Table 15.3.1 and is not addressed in ASME Section XI.
Reactor coolant pump flywheel inspections shall be conducted in accordance with the inservice inspection plan as follows:
- 1. 100% visual exam overy period.
- 2. Surface exam of the bore and keyway every period.
- 3. 100% volumetric every interval.
The reactor coolant pump flywheel exam requirements are not addressed in ASME Section XI.
Snubber surveillance shall be conducted in accordance with Technical Specification 15.4.13 vice ASME Section XI, Article IWF-5000.
As Wisconsin Electric informed NRC on October 6, 1981, the Unit 1 second ten-year interval plan is being written to the 1977 Edition (Summer 1979 Addenda) of ASME Section XI. The scope of examination of Class 1 and 2 pipe welds shall be in accordance with the 1974 Edition (Summer 1975 Addenda) of ASME Section XI as allowed by 10 CFR 50.55 a(b) (2) (ii) and (b) (2) (iv) . Until Technical Specification Change Request No. 42 is approved, Point Beach Nuclear Plant Unit 1 will again be governed by two sets of conflicting inservice inspection requirements, namely, ASME Section XI and Technical Specification 15.4.2.B.
I s
4 Mr. H. R. Denton February 23, 1982 In order to effectively develop and implement the second ten-year inservice inspection interval plan it is imperative that Technical Specification Change Request No. 42 be approved by the Commission. In light of the five years that this change has been outstanding, we would expect that final approval should be expected in the very near future.
If this is not true, Wisconsin Electric requests at least interim approval of Technical Specification 15.4.2.B.1 of Technical Specification Change Request No. 42. With this interim approval, we will be able to implement in a timely fashion the inservice inspection plan for the Unit 1 second ten-year interval.
Very truly yours,
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Assistant Vid President C. W. Fay Enclosures Copy to NRC Resident Inspector
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ENCLOSURE 1 10-YEAR ISI
SUMMARY
TABLES The ISI summary tables provided herin are a listing by component, category and item number of the_ Technical Specifi-cation and Code examination requirements as well as the status of the examinations. The following is a key to the summary tables:
Block Description (1) Component Component noun name (2) Exam area Area to be examined (3) Cat ASME Section XI category (4) Item No ASME Section XI item number (5) Meth NDE method UT Ultrasonic test PT Dye penetrant test VT Visual test MT Magnetic particle. test RT Radiographic test (6) Reg Exam requirement
- a. TS Technical Specification
- b. C ASME Section XI Code (7) Comp Percent of exam area complete (8) Period 40-month period (9) 10-Yrs 10-year interval Abbre /iations NA Not applicable REM Remainder
. o S
K R
A M
E R
4 T
S R
I @
F O 7
_ S C
- R A
L E A Y V
R 0 E 1 Q S C a b T E T 6 6 N R I
D M 7 O O I C R
E P
D R
I Q S C a b I
I E T 6 6 T R 1
T I D M 7
_ N O O U I C R
E P
D N Q a b O S C C M T 6 6 E
S D M 7 O O I C R
E P
T S 0 R S C a b I T 6 6 F
y$ 5 ysH 4
_ 1 g<o 3 T
N E
N O
P M
O A
' E R 2 A
M A
X E
e
, COMPONENT - REAC'IOR VESSEL UNIT 1 INTERVAL - FIRST "
FIRST PERIOD SECOND PERIOD TIIIRD PERIOD 10 YEARS EXAM AREA E :n RM COM REQ COMP W COM RQ COM REMARKS TS TS TS TS c c c c Lower !!ead to Lower NA 0%
"^
100%
"^
0%
' 100%
(1 of Weld un #
1 Ring Circumferential g) g) g g Weld BA Bl.1 UT NA NA NA 5% (1)
"^
Lower Ring to Lower 0% 100% 0% 100% (1) Of Weld Length Shell Circ Held BA Bl.1 UT (1) NA
' NA 5% (1) i 1
Lower Shell to NA 0% NA 100% NA og 5% (1) 100% (1) Of Weld Length fliddle Shell Cire (1) (1) (1) (1) y Weld BA Bl.1 UT NA NA NA 5% (1)
Lower Longitudinal NA 0% NA 100% NA 0% 10% (1) 100% (1) Of Weld Length Weld BA Bl.1 UT (1) (1) (1) (1)
NA NA NA 10% (1)
Middle Shell to NA NA NA 5% (1) (1) Of Weld Length
, Upper Shell Circ 0% 100% 0% 100%
Weld BB Bl.2 UT (1) (1) g (1) '
5% (1)
Upper Longitudinal NA 0% NA 100%
NA 0% 10% (1) 100%
(1) Of Weld Length Weld BB Bl.2 UT (1) (1) (1) (1)
NA NA NA 10% (1) 25% 25% 33- REfi 33- 100% 166-Closure liead to Plange Weld BC Bl.3 UT 100% 1/3% 1/3% 2/3%
25 - 25 -
REM 100%
i 33-1/3% 33-1/3%
Plange to Shell 25% 25% EM 0%
133- 333-
{ Weld BC Bl.3 UT 100%
25 - 25 - 1/3% 1/3%
33-1/3% 33-1/3%
2 2 2 33-6 (1) 100% = 6 Nozzles
- Nozzle to Vessel 33- 66- 133-Nozzles Notzles Nozzles Nozzles (2) 100% of each weld Welds BD Bl.4 UT 25 - 1/3% 25 - 2/3% 1/3% 1/3% examined 33-1/3% 33-1/3%
i j +
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i COMPONENT - REACTOR VESSEL UNIT 1 INTERVAL - FIRST e FIRST PERIOD SECOND PERIOD THIRD PERIOD 10 YEARS EXAM AREA E :G REMARKS
]
j y y g TS Ts TS Ts c c c c I
2 2 2 6 Nozzle Inside Nozzles Nozzles 66- Nozzles 33- Nozzles (1) 100% = 6 Nozzles Radius Section BD Bl.4 UT 25 - 25 - 2/3% 1/3% 100%
33-1/3% 33-1/3%
a (1) Of Each Group of NA NA NA NA Penetrations of 4
Vessel 100% 100%
l 6-1/4 - 6-1/4 - REM 25%
g) Comparable Size and Penetrations BE Bl.5 VT B-1/3 % (J) 3-1/3%(1) (1) (1) Function.
(1) 100% ='6 Nozzles Nozzle to Safe- 25%
33- 33- 166- (2) 100% of Weld Examined 6 No s) BP Bl.6 UT 3 1/3% 3 -1/3%
i . (1) 100% - 6 Nozzles 25% " 100% 133- (2) 100% of Weld Examined 33- 66- 33-
^
^5- 1/3% 25 - 2/3% 1/3% 1/3% (3) PT Could not be Per-Bl.6 PT REM 100% formed on both SI Nozzles i 33-1/31 33-1/3% due to Inaccessibilitv.
25%
(1) 100% - 6 Nozzles 33- 66- .5 3- 133- (2) 100% of Weld Examined VT 1/3% 2/3% 1/3% 1/3% (3) VT Could not be Per-formed on both SI Nozzles
- NA NA NA NA Due to Inaccessibility. 1 (1) 100% = 48 Studs !
- 25% 100% (2) Bl.7 Applies to Closure 33- 33- 33- Studs in Place.
Bl.7 100%
sur s BGl " ~
! ! (3) Bl.8 Applies to Closure B1*8 REM 100%
Studs Removed.
! 33-1/3% 33-1/3% '
i
! NA NA NA NA (1) 100% = 48 Studs Bl.8 MT' 25 - 0 25 - 0 REM 3% 100% 1 3%
! 33-1/3% 33-1/3%
25% 25% REM 100% (1) 100% = 48 Studs j 33- 33- 33- 100% i l NA l/3' NA 1/3% NA 1/3% NA i
25% " " ""
33- 33- 33-l Closure Nuts BGl Bl.8 UT 100%
25 - 1/3% 25 - 1/3% REM 1/3% 100%
33-1/3% 33-1/3%
i
e o
COMPONENT - REACTOR VESSEL UNIT 1 INTERVAL - FIRST PIRST PERIOD SECOND PERIOD THIRD PERIOD 10 YEARS ,
EXAM AREA :C :c REMARl(S
$ $ TS TS TS TS C C C C NA NA NA NA (1) 100% - 48 Nuts 33- 33-Bl.8 MT 25 - 0 25 - 0 REM 1/3% loog 1/3%
33-1/3% 33-1/3%
25% "
33- 33- 33-100%
VT 1/3% 1/3% 1/3%
NA NA NA NA NA 33-
"^ "^
33-
"^
166-(1) Examine When Connection 100% sassedled Ligaments BG1 Bl.9 UT 1/3% 1/3% 2/3%
NA NA NA (1) 25%
33-25%
33-REM 33-() = Was rs Washers BG1 Bl.10 VT 25 - 1/3% 25 - 1/3% 1/3% 100%
33-1/3% 33-1/3%
NA NA NA NA Not Applicable. All Pressure Retaining Bolting Greater Than Bolting BG2 Bl .11 VT 2" Diameter.
NA NA E E
"^ PP 9 Integrally Welded Support BH Bl.12 UT 25 - 0 25- 100% 0 100%
REM 19%
33-1/3% 33-1/3%
2 2 2 6 (1) 6" x 6" Patch
- " ^ * * #
- C d ng BIl Bl.13 PT O (1) 2 (1) 2 Patches (1) 2 Patches (1) 6 Patches Patches Patches (1) Patches (1) Patches (1) l 2 2 2 6 (1) 6" x 6" Patches Patches Patches 4 Patches 2 Patches 6 Patches Bl .13 VT g 0 (1)
W 2 Patchee II)
(1) 6
(
Patches Patches Patches Patches 6 (1) Gen Area Inspection NA NA Patches MA Patches (2) 6" x 6" Patch Vessel Cladding BIl Bl.14 VT O 0 (2) 2 (2) 2 (2) (3) (2) 2 (2) 6 (3) Be t " " '
Patches Patches Patches Patches ac s I
o COMPONENT - UNIT 1 INTERVAL - PIRST o REACTOR VESSEL PIRST PERIOD SECOND PERIOD THIRD PERIOD 10 YEARS '
REO COMP REQ COMP REO COMP REQ COMP p EXAM AREA g g g TS TS TS TS g g g _
c c c c NA NA NA NA (1) All Interior Surfaces Vessel Interior Bril Bl.15 VT 0% 0% 0% '0% yesselMadeAccessble
" "9 "9*
(1) (1) (1) NA i
NA NA NA NA Not Applicable to PWR.
Interior Attachments BN2 Bl.10 .VT NA NA NA NA NA NA NA (1) When Core Barrel Core Support Removed.
Structures BN3 Bl.li VT gg 100%
93A NA 100%
(1) 10% of Peripheral CRDM NA NA NA NA flousings.
45% 45% (2) 20 Peripheral CRDM Welds BO Bl.10 UT 0 Ilousin s NA NA (3) NA (1) (3) (3) ofPer$,phe3c nniic i m ud 1 CRDM (1) Inspect as Accessible NA NA NA (1) (2) 20 Peripheral CRDM 45% 45% Housings VT (3) of Peripheral CRDM NA NA (3) NA NA (3) llousing Welds NA NA NA NA (1) During System Hy r stade hessure Exempted Components BP Bl .10 VT 100% 100%
100% Test NA B n (1)
A
e a
COMPONENT - REACTOR VESSEL UNIT 1 IHTERVAL - FIRST FIRST PERIOD SECOND PERIOD THIRD PERIOD 10 YEARS ,
REO COMP REQ COMP REQ COMP REQ COMP p pg EXAM AREA g
- C g r, TS TS TS TS g g g C c c c NA NA NA NA (1) All Interior Surfaces 0%
f Vessel Made Accessible Vessel Interior BN1 Bl.15 VT 0% 0% 0%
During Normal Refueling.
(1) (1) Q) NA NA NA NA NA Not Applicable to PWR.
Interior Attachments BN2 Bl.10 .VT NA NA NA NA NA NA NA (1) When Core Barrel Core Suplert Removed.
Structures BN3 Bl.11 VT 100%
NA NA NA (1) 10% of Peripheral CRDM NA NA NA NA Housings.
CRDM Housing 45% 45% (2) 20 Peripheral CRDM Welds BO Bl.10 UT O Housings NA NA (3) NA (1) (3)
(3) Of PQriphewd nniic,nn Me1 CRDM (1) Inspect! as Accessible NA NA NA (1) (2) 20 Peripheral CRDM 45% 45% Housings VT (3) of Peripheral CRDM NA NA (3) NA NA (3) Housing Welds NA NA NA NA (1) During System Hy r stade Pressure Exempted Components BP Bl . l(J VT 100% 100%
NA NA NA (1) i
COMPONENT - PRESSURIZER UNIT 1 INTERVAL - FIRST
- PIRST PERIOD SECOND PERIOD TlilRD PERIOD 10 YEARS ,
M Q MP Q COMP REQ COMP EXAM AREA g y y REMARKS g g g TS TS TS TS c c c c (1) Of Weld Length NA NA NA 13.7% (2) 25 1/3% of all Upper Nead to 13.7% 5% (1)
Upper Shell Circ (1) (1) Shell Welds (5 Total)
Welds (2) (2) (3) 5% - (1) (3) ggnderofShell ,
l (1) Of Weld Length NA NA NA 5% (1) 13.7%
13.7%
NA NA NA NA (1) Of Weld Length Upper Shell to NA NA NA 5% (1) 13.7% 13.7% (2) 25 1/3% of all Lower Shell Circ Shell Welds (1) (1) (3) Remainder of(Shell5 Total)
Weld BB B2.1 UT (2) (2) (3) 5% (1) Welds NA NA 13.7%
"^ (' 13.7%
NA NA NA NA (1) Of Weld Length Lower Shell to NA NA NA 5% (1) (2) 25 1/3% of all 1 .7% 13.7% Shell Welds (5 Total)
Lower IIead Circ Weld BB B2.1 UT (2)
' (2) (3) 5% (1)
I' '
e NA NA NA 5% (1) (1) of Weld Length g 13.7% 13.7%
NA (1) NA NA NA (1)
(1) Of Weld Length Upper Shell NA NA NA 10% (1) (2) 25-33-1/3% of all
. . 12.1% 12.1% Shell Welds Longitudinal
-(1 (1) (3) Remainder of (Shell5 Total)
Weld BB B2.1 UT (2) (2) (3) 10% (1) Welds NA NA NA 10% (1) (1) Of Weld Length VT 12.1% 12.1%
NA NA NA (1) NA (1)
NA NA NA 10% (1)
# ##9 Lower Shell 18.2% 18.2% (2) 25 1/3% of all Longitudinal BB B2.1 UT (1) (2) (3) (1) Shell Welds 5 To (2) 10g (1)
(3) g g nder of(Shelgal)
Weld
COMPONENT - PRESSURIZER UNIT 1 INTERVAL - FIRST
- PIRST PERIOD SECOND PERIOD THIRD PERIOD 10 YEARS REO COMP REQ COMP REQ COMP REQ COMP EXAM AREA g y y REMARKS g g g TS TS TS TS C C C C NA NA NA 10% (1) (1) Of Weld Length VT 18.2% 18.2%
NA III III NA NA NA NA NA NA NA Not Applicable. All N zz e essel Nozzles are Integrally e s BD B2.2 N NA NA NA NA Cast Into the Vessel lleads.
NA NA NA NA = Nozz es Nozzle Inside Radius Section BD B2.2 UT 25 - 25 -
33-1/3** 33-1/3%
NA NA NA NA (1) Performed During IIeater 100% 100% liydrostatic Pressure Penetrations BE B2.3 VT NA NA NA 25% (1) Test.
Nozzle to Safe 25% 25% REM 100% (1) 100% = 5 Nozzles End Welds BP B2.4 UT 25 - 0% 25 - 100% 40% 140%
33-1/3% 33-1/3%
25% 25% REM 100% (1) 100% = 5 Nozzles PT 0% 100% 40% 140%
25 - 25 -
33-1/3% 33-1/3%
25% 25% REM 100% (1) 100% = 5 Nozzles VT 0% 100% 0% 100%
NA NA NA NA Pressure Retaining NA NA NA NA Not Applicable.
Bolts and Studs In Bolting is Less Than Place BG1 B2.5 UT NA NA NA NA 2" Diameter.
Pressure Retaining NA NA NA NA Not Applicable.
Bolts and Studs'When UT Bolting is Less Than Removed BG1 B2.6 MT NA NA NA NA 2" Diameter.
. e r
u n gs s r a o h ne f s S
T s
h t
g h
c iW r
u esl l no t
K es n t D e b oB e a i s R
A M
l e bL a r
. L P dd ea sa6 se1 E cse d " mt eR R i _i t l 6 rs c =
l e e o cr pgm W x f A e%
pna r
- h0 A ii f " ey* st0 tD O 6 PH AO1 tl oo" ) ) )
) )
NB2 1
(
1
(
1
(
1
(
2
(
T ) s S 1
(
e % - %
R P h I M c 0 33 F O % 4 t 0
S 0 a 1 21
- R 1 P A )
L E A Y s 1 V W e 1h (
R 0 h c A ) %
E 1 s c A A A 3c t N % 1 0 T T N N N % t ) a 0 ( 0 N
I 0 a (1 P 0 1 1 P 1
% h 3 c %
D / 1 t 0 O
1W a 0 I
R
- P 1 3
E P
D h R M c M I S c A A A E 1t A A A A E H T N N N R a N N N N R T P 1
T 3 h %
I D / c) 33 N
U O
I P 6 2W y t1 P
a(
3/
1 E
P ) %
%1 h 3 D
N 23( c /
O s c A A A 1t A A A A 1 C T N N N V/r a N N N N 5 -
E S
-- P 23 3
23 s
)
1 e
( h D 2 c)
O I % ta (1 R 0 P E
P _ ) %
T 1 h 3 S c /
R S c A A A // 1t A A A 1 I T N N N 1,- a N N N 5 -
P P 23 3
. R E
3h T T T T T
_ Z V U V V V
_ I 0 1 R 7 8 9 1 1 U E S 2 2 2 2 2
_ S B B B B B
_ E R 1 H 2 2
__ P G B I P G B B B B
_ g g T n d s n
_. N E i e t i N n d g n n O i l n e i
_ P a e i n a N
O A t W d o p
t e
C E e d R R y a m R A l l o
_ e l C C e M rg at rg
_ A un rr l t un
_ X si go e p si E st ep s m st el t p s e el ro nu e x ro PB I S V E PB 1 1i,
COMPONENT - STEAM GENERATOR "A" UNIT 1 INTERVAL - FIRST '
PIRST PERIOD SECOND, PERIOD TIIIRD PERIOD 10 YEARS EXAM AREA E Z M MP REQ COMP EQ COM REMARKS TS TS TS TS C C C C Primary Head to NA NA NA 5% (1) (1) Of Weld Length Tubesheet Weld BB B3.1 UT _ _
8.9% _ _
0% 5.2% 14.1%
(1) 1-2 l-2/g 5% (1)
^ "A of Weld Lenge 8.9% Os 5.2% 14.1%
0T (1) (1) (1) (1)
NA NA NA NA Longitudinal and NA NA NA NA Not Applicable.
Circumferential No Primary Shell Welds.
Welds BB B3.1 UT NA NA NA NA NA NA NA NA Not Applicable. All Nozzle to Shell N zz s are Integrally Helds BD B3.2 UT NA NA NA NA Cast Into Primary Head.
Nozzle Inside
"^ "^ "^ "^ ~
Radius Section BD B3.2 UT 25 - 0% 25 - 0% 100% 100%
EM 100%
33-1/3% 33-1/3%
Nozzle to Safe 25% 25% REM 100% (1) 100% = 2 Nozzles End Weld BF B3.3 UT 25 - 25 -
33-1/3% 33-1/3%
25% 25% REM 100% (1) 100% = 2 Nozzles B3.3 M 25 - 50%
25 _ 0% 100% 150%
REM 100%
33-1/3% 33-1/3%
25% 25% REM 100% (1) 100% = 2 Nozzles VT 50% 0% 100% 150%
NA NA NA NA Pressure Retaining NA NA NA NA Not Applicable. All Bolts and Studs in Bolting is Less Than BG1 B3.4 UT 2" Diameter.
Place NA NA NA NA
r
. e t h e r e t o r O
. p u p r h . s r l n l n u o cy gs o l a l a oS f t a ne f s Ah Ah N .aw esp n i r e
t T T d rP l e l n a u l o S .s .s .d b o" M D c b B K
R es es el i s6 i i A l e l e l e sa h dt s 2 M bL . bL bW sexc ea s .
E a r a r a eR a mt e R cse cse cy c E rs c =
iit iit il c r "6 oo . c l e l e ll A e r f rt A %
pgm pgm pa h - a rd s pna pna pr st e eye s Aii Aii Ag AO1N PHT A tD tD e tl tl tt ) ) ) ) )
oo" oo on 1 2 1 1 2 NB2 N B "2 NI ( ( ( ( (
T S %
R P ) 0 I M 2 0 P O ( 1 S C
- R A
L E )
A Y 1 V ( %
R 0 A A A A A ) ) A % 0 E 1 O s C N N N N N 1 2 N 0 0 T E T ( ( 0 1 N R I 1 P ) 0 D M 2 0 O O ( 1 I C R
E P
D M R A A A A' A A A A A E I Q S C N N N N N N N N N l
i E T T R 1
T P I D M N O O U I C R
E P %
D 3 N Q A A A A A A A A A /
O E S C 1 C R T N N N N N N N N N 5 E 2 3-S 3 P
D M O O I C R
E P 1 3
"A T /
" S O A A A A A A A A A 1 R E S C N N N N N N N N N 5 -
R FI R T 23 O 3 T
A R gg TT T T T T T E UM V U V V V
- N
- E 5 6 7 8 9 0
_ G 1 yg 3 3 3 3 3 3 M B B B B B B A
_ E 1 1 2 2
- T gg G G i l I P G S B B B B B B s g o t T n d n n N i e e i E ns d g n n N
O id l n o p
i P au e i a M t td W d m t e
O A eS e d o C E R v y a C R R d o g l l A enm en l s C d e rg rae rig at e M
A u R unn rr l t un X ss sii go e n si E st n sat ep s m st el e etl t p s e el roh r eo nu e x ro PBW PRB I S V E PB
COMPONENT - STEAM GENERATOR "B" UNIT 1 INTERVAL - FIRST -
FIRST PERIOD SECOND PERIOD TilIRD PERIOD 10 YEARS REQ COMP REQ COMP REO COMP REQ COMP p.
EXAM AREA g g g pg g g g TS TS TS TS
~
C C C C Primary Head to NA NA NA 5% (1) (1) Of Weld Length Tubesheet Weld BB B3.1 UT _ j4 _
0%
g_174 _ 9% (1) REM of 1-2/3% l-2/3% 5% (1) 5% (1)
(1) (1)
NA NA NA 5% (1) (1) Of Weld Length
- dT 0% 9% (1) 0% 9% (1)
NA .NA NA NA Longitudinal and NA NA NA NA Not Applicable.
Circumferential No Primary Shell Welds.
Welds BB B3.1 UT NA NA NA NA Nozzle to Shell
"^ "^ "^ "^ " ^EE ^ ** ^
Welds BD B3.2 UT ** ** * * " "9 " Y NA NA NA NA Cast Into Primary Head.
NA NA NA NA ( -
N zz es Nozzle Inside Radius Section BD B3.2 UT 25 - 0% 25 - 100% Os 100%
EM 100%
33-1/3% 33-1/3%
Nozzle to Safo 25% 25% REM 100% (1) 100% = 2 Nozzles End Weld BP B3.3 UT 25 - 25 -
EM 100%
33-1/3% 33-1/3%
25% 25% REM 100% (1) 100% = 2 Nozzles B3.3 PT 25 - 50%
25 - 0% 100% 150%
REM 100%
33-1/3% 33-1/3%
25% 25% REM 100% (1) 100% = 2 Nozzles VT 50% 0% 100% 150%
NA NA NA NA Pressure Retaining NA NA NA NA Not Applicable. All Bolts and Studs in Bolting is Less Than Place BGl E3.4 UT 2" Diameter.
NA NA NA NA
r
. e
.
r O p u p r h . s r l n l n u o cy gs o l a l a oS f t a ne f s ,
Ah Ah N b w i r t T T d e P n rP e l e a u l o S
K R
.s es l e
.s es l e
.d el l e M"M s h D c dt i
b i
s B
2 A bL . bL bW s xc ea s 3 M a e a es E a r r a mt R cse cse cy c " E rs cn=
iit iit il c 6 oo . co l e l e l l A r f rt A s%
pgm pgm pa h- a rd s a0 pna pna pr s e eye se0 Aii Aii A g A N pitl AR1 tD tD e tl tl t t ) ) ) )
oo" oo on 2 1 1 2 NB2 N B "2 NI ( ( ( (
T S % %
R P ) 0 3 I M 2 0 /
P O ( 1 1 S C
- R A
L E )
A Y 1 V ( %
R 0 A A A A A A ) A % ) 0 E 1 Q S E T c N N N N N N 1 N 0 1 0 T ( 0 ( 1 N R I 1 P 0 D M 0 O O 1 I C R
E P
D M R A A A A A' A A A A A E l O S c N N N N N N N N N N R l
i E T T R 1
T P )
I D M 2
(
N O O U I C R
E P %
D 3 N Q A A A A A A A A A /
E S c 1 O N N N N N N N N N 5 C R T -
E 2 3 S 3 P 3 D M
/
O O 1 I C R
E P %
" 3 B T /
S O A A A A A A A A A 1 R E S c N N N N N N N N N 5 -
R I R T 23 O F 3 T
A R gg TT T T T T T E UM V U V V V N
E G
5 6 7 8 9 'u gg 3 3 3 3 3 i.
3 M B B B B B B A
E J 1 2 2 T gg G G I I P G S B B IB B B B
- s o t g T n d n n N i e e i E ns d g n n N id l n o i O
P au e i p a M t td W d m t e
O A eS e d o C E R v y a C R R d o g l l A enm rae en rig l s at C d e
e r9 M
A u R unn rr go l t p
u" X ss sii e s1 E st n sat ep s m st el e etl t p s e el roh reo nu e x ro PBW PRB I S V E PB
COMPONENT - REGENERATIVE IIEAT EXCHANGER UNIT 1 INTERVAL - FIRST
- FIRST PERIOD SECOND PERIOD THIRD PERIOD 10 YEARS EXAM AREA E m OW W GW RM COM REMARKS TS TS TS TS C C C C NA NA 66-
^ "
NA 33- NA Circumferential = e s 0% 2/3% 1/3% 100%
Welds BB B3.1 UT (1) 25- (1) 25- g REM 100%(1) (3) 5% of Each Circ Weld 33-1/3% 33-1/3% (1) (3) is examined
^ "A NA (1) 00% = 12 Nozzles Nozzle to Shell 66- 33-Welds BB B3.2 6T 25 - 25 - 2/3% 1/3%
M 100%
33-1/3% 33-1/3%
NA NA NA NA . Not Applicable.
Nozzle Inside No Inside Radius Sectior .
Radius Section BB B3.2 UT NA NA NA NA NA NA NA NA Not Applicable.
Nozzle to Safe UT No Safe Ends.
End Welds BF B3.3 PT Pressure Retaining NA NA NA NA Not Applicable.
Bolts and Studs in 9*
BG1 B3.4 UT Place NA NA NA NA Pressure Retaining NA NA NA NA Not Applicable.
Bolts and Studs UT No Bolting.
When Removed BG1 B3.5 MT NA NA NA NA Pressure NA NA NA NA Not Applicable.
Retaining No Bolting.
Bolting BGl B3.6 VT NA NA NA NA NA NA NA NA (1) 100% = 3 Supports.
Integrally Welded 0% 0% 0% 0%
Supports BH B3.7 UT REM 100%
3 1/3% 33 /3%
NA NA NA NA (1) 100% = 3 Supports 0% 0% (2) VT Performed vice UT.
( NA VT NA NA NA
+- ,
t S
K e e e l l l R
A b . b b M ag a a .
E cn c cg R ii i i n ld l l i pd p pt pa p pl Al A A o C B t t t oo o oo NN N NN T
S R P I M F O S C
- R A
L E A Y V
R 0 E 1 O S C A A A A A A T E T N N N N N N N R I
P D M O O I C R
E P ~
D R A A A A A I O S C A l
i E T N N N N N N T R 1
T P I D M N O O U I C R
E P
D N Q A A A A A A O E S C N N N N N N C R T E
S R
E P G D M N O O A I C H R C E
. X P
- E T
.- T S Q A A A A A A A R E S C N N N N N N E I R T F
H E
- V g T T T
_ I V .V V
- T C A 8 9 1 R
E g$ 3 3 3
N B B B E
- G 2 2 E N I P G R B B B T
N E
N O
P t
0
- 0 C s t g
- g d n en
_ n ee rig l i t n po unn ed sii sd mp sat
_ sa em etl el xo reo VC EC P RB
i s
o.
r dt
. r ys e
g 1
1 e T
n g a . ne htir cpru S
K R
hmus eDs x e A tEdr M a eP E e1 m R i l rc s oi ssft ara l et cps
)
2
(
T S
R %
I W 0)
F O 02 6 S C 1(
- R A
L E A Y %
V R 0 0)
E 1 O S T
c A 02 T E N 1 N R I
D M 0)
O O 02 I C 1(
R E
P D
R I
l i
Q S E T c A N
A N
T R 1
T I D M N O O U I C R
E P
D N
O C M S T
c A N
A N
E R S E
G N
A f D @
i O O C I X R E E P
T T A S 0 E R S c A A I
I I T N N F
N W
O D % T T V E
L 9 S E 3 S B E
C X P E B T
N E
N O
P M
O A C E R
A .
M s A e X l E eez bd z uio TSN
, n COMPONENT - CLASS 1 PIPING UNIT 1 INTERVAL - PIRST
- FIRST PERIOD SECOND PERIOD THIRD PERIOD 10 YEARS EXAM AREA g ] g REMARKS g TS TS TS TS c c c c pp c M e. Safe NA NA NA NA
~ Safe End Welds BP B4.1 Under Each Separate PT g g g Component.
Pressure Retaining NA NA NA NA Not Applicable. All Bolts and Studs in n ss h an 2" BG1 B4.2 dT Diameter.
Place NA NA NA NA Pressure Retaining NA NA NA NA Not Applicable. All Bolts and Studs UT Bolting Less Than 2" Removed BG1 B4.3 MT M NA NA Diameter.
Pressure NA NA NA NA Not Applicable.
Retaining All Bolting Less Than Bolting BGl B4.4 VT NA 2" Diameter.
NA NA NA Circumferential 6% 6% 13% 25% (1) 100% = 294 Welds Pipe Welds B4.5 UT 8%
BJ 6-1/4 - 6-1/4 - REM of 8-1/3% 8-1/3% 25%
6% 6% 13% 25% (1) 100% = 294 Welds .
~
. VT 8% 9% 8% 25%
NA NA NA NA NA NA NA NA Not Applicable.
9 . " "" No Longitudinal Pipe Pipe Welds BJ B4.5 UT gg Branch Pipe NA NA NA NA (1) 100% - 4 Welds Connections Greater 0% 0% 0%- 50%
Than 6" Diameter BJ B4.6 UT 6-1/4- 6-1/4- REM 25%
8-1/3% 8-1/3% 25%
. . - , . . ..-.;,,..~~ ,- . . - . . .~. -. _. . - _ _ . - - . . . . - - . .
/ '
" s s / .
COMPONENT - CLASS 1 PIPING ~~
UNIP 1 i INTERVAL - FIRST *
., FIRST PERIOD SECOND PERIOD THIPD PERIOD 10 YEARS EXAM AREA g g g REMARKS
< p g TS TS TS TS C C C C Branch Pipe Connec- (
- NA NA NA NA tions Less Than or 0% 23% 6% 29%
Equal to 6" BJ B4.7 PT 6-1/4 - 6-l/4 - REM,/
Diameter 25%
8-1/3% 8-1/3% 25%
4 NA NA tQ NA (1) 100% = 430 Welds .
Socket Welds BJ B4.8 .PT 0% 15% 10% 25%
6-1/4 - 6-1/4 - pgg 1 y 25%y .
B-1/3% 8-1/3%
25% + -
)
NA NA NA NA (1) 100% - 18 Supports i Integrally Welded Sockets BK1 B4.9 UT 11% l' 11% 39% /
6-1/4 - 6-1/4 - REM of ;
8-1/3% 8-1/3% 25% / //
i NA NA NA NA (1) 100k = 94 Supports
, Support , ,
Components BK2 B4.10 VT 25 - 1% 25 - 6% 93% 100%
100%
! 33-1/3%
33-1/3% ,f, REM e '
/
r
"^ "^ "^ "^ " "9 "Y **
Exempted 100% 100%
Components BP VT essure h st j B4.ll NA 0%
NA 0%
NA (1) 100% (1)
(1)
NA NA NA NA (1) 100% = 13 Sets of Pressure #
Retaining- 0% 69% 31% 1001 Flange Bolting BG2 B4.12 VT 25 - 25 -
Boltin9 REM 100%
33-1/3% 33-1/3%
I F
f
[
l i
COMPONENT - REACTOR COOLANT PUMP "A" UNIT 1 INTERVAL - FIRST FIRST PERIOD SECOND PERIOD THIRD PERIOD 10 YEARS EXAM AREA E m OMP A I N EQ N EQ CN REMARKS TS TS TS TS c c c c NA NA NA NA (1) 100% = 24 Studs Pressure Retaining (2) B5.1 Applies to Studs b5.1 0% 66- 33- 100%
25 - 25 - in Place.
Studs BGl B5*2 UT 100%
33-1/3% 33-1/3%
/ 1/3% (3) g vg@s to Ms NA NA NA NA (1) 100% - 24 Studs (2) If Bolting Removed.
B5.2 MT 01h 0% 0% 0% (3) Bolting Not Removed NA NA NA (2) (3) During This Interval.
NA NA NA (2) (1) 100% - 24 Studs 33- 133- (2) As Accessible for B5.3 VT 100% 0%
5 1/3% Other Reasons.
REM 100%
33 1/3% 33 /3%
NA NA NA NA (1) If Bolting Removed.
Pressure Retaining (2) 100% - 24 Nuts 0% 0% 0% 0% (3)
Nuts BG1 B5.2 MT NA NA NA (1)
(3) Bolting Not Removed Durino This Interval.
(1) As Accessible for NA NA NA (1) Other Reasons.
100% 0% 33- 133-B5.3 VT 25 - 25 -
REM 1/3L 100% 1/3% (2) 100% = 24 Nuts 33-1/3% 33-1/3%
NA NA NA NA (1) If Disassembled Ligaments BG1 B5.3 VT 0% 01, 0% 0% (2) (2) Pump Was Not Disassem-NA NA NA 100%(1) bled This Interval.
A t rally Integrally Welded NA NA NA NA W Id support Lugs BK1 B5.4 UT 0% 0% 0% 0% (2) 100% = 3 Support Lugs NA NA NA 25% (1) (3) Exam Not Practical (1) Of All Integrally NA NA NA NA Welded Supports.
33-33- (2) VT Performed Vice UT VT 0% 1/3%
! P NA NA (1) NA NA (y NA NA 66- NA 33- NA (1) 100% - 3 Support Leos 100%
Support Legs BK2 B5.5 VT 25 - 25 - 2/3% 1/3%
REM 100%
33-1/31 33-1/3%
. . _ . _ _ _ _ _ _ - . . - . .~-
] .
COMPONENT - REACTOR COOLANT PUMP "A" UNIT 1 INTERVAL - FIRST FIRST PERIOD SECOND PERIOD THIRD PERIOD 10 YEARS E % REO COMP REQ COMP REO COMP REQ COMP EXAM AREA REMARKS TS TS TS TS
. C C C C (1) 100% of all Casing
"^ "^ "A "A Welds in One RCP Punp Casing Welds BL1 B5.6 RT 0% 0% 0% 0%
) (2) IB RCP Examined NA NA NA 100%(1)
NA NA NA 100%(1) (1) 100% of All Casing VT 0% 0% 0% 0% Welds in one RCP.
NA NA NA NA (2) IB RCP Examined.
(1) 100% of the Internal
! NA NA NA NA Pump Casing 0% PressureRetaininbP.
Surfaces of One R
! 0% 0% 0%
n em s BR B5.7 W (2) IB RCP Examined.
NA NA NA 100%(1) l NA NA NA NA (1) Performed During j Exempted 100% 100% Hydrostatic Pressure Components BP B5.'8 VT (l) (1) Test NA NA E 100%(1) l (1) Inplace UT i NA (1) (2) NA (2) 100% UT
- (3) III (3) Bore & Keyway (2)
Flvwheel UT pg (4) NA (3) NA NA (4) Top Surface NA NA NA NA (1) Bore & Keyway PT (1) (1}
NA NA NA NA i (1) Inplace VT
- (1) NA NA NA (2) 100% VT fVT (3) (1) (2) (3) VT of Top, Periphery, g
NA NA NA NA and Bore Surfaces
- e I
h
! 1 i :
4 ;-
! E
! f, e- - m
COMPONENT - REACTOR COOLANT PUMP "B" UNIT 1 INTERVAL - FIRST .
FIRST PERIOD SECOND PERIOD THIRD PERIOD 10 YEARS 2: c REO COMP REQ COMP REO COMP REQ COMP EXAM AREA TS TS TS TS h ~
c c c c NA NA NA NA (1) 100% = 24 Studs Pressure Retaining B5.1 .(2) B5.1 Applies to Studs 66- 33- 100% in Place.
Studs BG1 B5*2 UT 25 - 25 -
2/3% REM 1/3% 100% .(3) B5.2 Applies to Studh 33-1/3% 33-1/3% Removed.
NA NA NA NA (1) 100% - 24 Studs (2) If Bolting Removed.
B5.2 MT 0%. 0% 100% 100%
NA NA NA (2)
NA NA NA (2) (1) 100% - 24 Studs 100% Og 33- 133- (2) As Accessible for B5.3 VT W M er Reasons, RM 100g 33 /3% 33 /3%
flA NA NA NA (1) If Bclting Removed.
Pressure Retaining (2) 100% - 24 Nuts 0% 0% 100% 100%
Nuts BG1 B5.2 MT g g g (1) As Accessible for NA NA NA (1) 100% 0% 33- 133- Other Reasons.
B5.3 VT 25 - 25 - (2) 100% = 24 Nuts REM 1/3% 100% 1/3%
33-1/3% 33-1/3%
NA NA NA NA (1) If Disassembled Ligaments BG1 B5.3 VT 0% 0% 100% 100%
NA NA NA 100%(1)
(1) Of All Integrally Integrally Welded NA NA NA NA Welded Supports Support Lugs BKl B5.4 UT 0% 0% 0% 0% (2) 100% = 3 Support Lugs HA NA NA 25% (1) (3) Exam Not Practical NA NA NA NA (1) VT Performed Vice UT.
(2) 100% = 3 Support Lugs VT Og 0% 100% 100%
(3) of all Integrally NA NA NA (3) NA (3) Welded Lugs NA NA 66- NA 33- NA (1) 100% - 3 Support Legs Support Legri BK2 B5.5 VT 100%
25 - 25 - 2/3% 1/3%
REM 100%
33-1/31 33-1/3%
l
I COMPONENT - REACTOR COOLANT PUMP "B" UNIT 1 INTERVAL - FIRST =
3 PIRST PERIOD SECOND PERIOD TilIRD PERIOD 10 YEARS i REO COMP REQ COMP REO COMP REQ COMP EXAM AREA g y y REMARKS g g g Ts Ts Ts Ts l
C C C C (1) 100% of All Casing Welds NA NA NA NA in one RCP.
(2) Exam Done in Accordance Pump Casing Welds BL1 B5.6 RT 0% 0% 100% 100% with 1977 Ed. Summer of NA NA NA 100%(1) 1979 Addenda of Sec. XI.
(Ltr. of 10-6-B1 to Denton)
NA NA NA 100%(1) (1) 100% of All Casing Welds in one RCP.
0% 0% 100% 100%
NA NA NA NA NA NA NA NA (1) 100% of the Internal Pump Casing ,
Pressure Retaining Internals BL2 B5.7 VT 0% 0% 100% 100%
NA NA NA 100%(1) surfaces of One RCP.
l NA NA NA NA .
Components BP B5.8 VT st A NA NA 100%(1)
Not Applicable, Pressure NA NA NA NA pggg All Bolting is Greater an am er.
Bolting BG2 B5.9 VT NA NA NA NA (1) In Place UT NA III (2) (2)
NA (2) 100% UT (3) (1) ,
Flywheel (3) Bore & Keyway UT NA (4) NA (3) NA NA (4) Top Surface NA NA NA NA (1) Bore & Keyway (1) (1) (1)
PT NA NA NA NA (1) NA NA NA (1) In Place VT (2) 100% VT (3) (2) (2) (3) VT of Top, Periphery &
VT NA NA NA NA Bore & Keyway Surfaces 2
COMPONENT - CLASS 1 VALVES UNIT 1 INTERVAL - FIRST
- PIRST PERIOD SECOND PERIOD THIRD PERIOD 10 YEARS REO COMP REQ COf f P REQ COMP REQ COMP EXAM AREA g y y R RKS g g g TS TS TS TS C C C C Pressure Retaining NA NA NA NA Not Applicable. All Bolts and Studs Bolting less than 2" in Place BG1 B6.1 UT NA NA NA NA Pressure Retaining UT NA NA NA NA Not Applicable. All Bolts and Studs Bolting less than 2" When Removed BG1 B6.2 MT NA NA NA NA Diameter.
Pressure Retaining NA NA NA NA Not Applicable. All Bolting BG1 B6.3 VT Bolting less than 2" NA NA NA Diameter.
UA Integrally NA NA NA NA Not Applicable.
Welded No Valve Supports.
Supports BK1 B6.4 UT NA NA NA NA NA NA NA NA Not Applicable.
Support Components BK2 B6.5 VT No Valve Supports.
NA NA NA NA ne Large Gate Va he NA NA NA (1)
- " " # 9# #
- Valve Body Welds BM1 B6.6 UT ,
V#l# # * "" # " *" "# "E NA NA (2)
(3) of Valves of the Same Constructional Design, Manufacturing Method and Manufacturer that Perform Similar Functions.
(3) Only the 10" Velan Gate Valves Have Body Welds.
COMPONENT - CLASS 1 VALVES UNIT 1 INTERVAL - FIRST FIRST PERIOD SECOND PERIOD TillRD PERIOD 10 YEARS ,
EXAM AREA E ,m Op W COM M COM EO COW pggggg3 e TS TS TS TS c c c c (1) VT of one Large Check IJA 2 !!A 1 IJA 4 (1) 7 Valve and One Large Gate Valve Bodies BM2 B6.7 VT Valves Valve Valves. Valves Valve.
11A NA NA (2) (2) VT of one Valve in each Group of Valves of the Same Constructional Desion, Manufacturing Methods and
. Manufacturer That Performs Similar Functions.
(3) Valves Examined -
10" Darling Gate Valve 10" Darling Check Valve 10" Velan Gate Valve 4" Velan Gate Valve 3" Velan Gate Valve 6" Velan Check Valve 3" Co es Vulcan Globe va ve NA NA NA NA (1) During Hydrostatic Exempt Components BP B6.2 VT 100% 100% Pressure Test (1) 100% (1)
NA NA NA (1)
Pressure Retaining 11A NA NA (1) (1) As Accessible for Bolting BG2 B6.9 VT 25 - 25 -
100%
33-1/3% 33-1/3%
ENCLOSURE 2
SUMMARY
OF ASME SECTION XI PRESSURE TESTS ASME Sect XI Class Reference Type of Test Frequency Status 1 IWB' 5210 (a) Hydrostatic pressure test 100% every 10 years 100% complete IWB 5210 (b) Leakage test 100% overy 100% complete refueling outage 2 IWC-2412 (a) Pressure test of exempt 100% each interval 100% complete components l
( }
IWC-2412(b) Not applicable ----- -----
3 IWD-2410 (b) Hydrostatic pressure test 100% every 10 years 75% complete III IWD-2410 (c) Inservice pressure test 100% every period 100% complete II This requirement was adopted during the third period. WE committed to the performance of 33-1/3% of the required Class 3 hydrostatic pressure tests for the first 10-year l interval in our inservice inspection plan submitted May 20. 1977.
l
( As stated in our inservice inspection plan, all Class 2 systems are exempt in accor-dance with IWC-1220