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MONTHYEARML20058G8861982-07-28028 July 1982 Forwards Response to NRC 820619 Request for Addl Info Re Proposed Reactor Vessel Water Level Instrumentation Sys Required by NUREG-0737,Item II.F.2 Project stage: Request ML20062K9821982-08-31031 August 1982 Steam Generator Repair Rept Project stage: Request ML20065H7941982-09-29029 September 1982 Requests Relief from ASME Section Xi,Inservice Insp Requirements Re Frequency of Reactor Vessel Interior Exam Project stage: Other ML20070Q8531983-01-19019 January 1983 Forwards Instrumentation Error Analysis of Reactor Vessel Water Level Indication Sys,Completing Response to NRC 820619 Request for Info Project stage: Request ML20069A7331983-03-0404 March 1983 Forwards Class III Fee Re 830119 Request for Relief from Certain ASME Section XI Inservice Insp Requirements Project stage: Request 1982-09-29
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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] |
Text
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lHsconsin Becinc meacoum 231 W. MICHIGAN, P.O. BOX 2046, MILWAUKEE, WI 53201 February 18, 1983 Mr. H. R. Denton, Director Office of Nuclear Reactor Regulation U. S. NUCLEAR REGULATORY COMMISSION Washington, D. C. 20555 Attention: Mr. R. A. Clark, Chief Operating Reactors Branch 3 Gentlemen:
DOCKET NOS. 50-266 AND 50-301 REV16ED RESPONSE REGARDING ENVIRONMENTAL QUALIFICATION OF SAFETY-RELATED ELECTRICAL EQUIPMENT POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 On December 27, 1982, Wisconsin Electric received the Safety Evaluation Reports (SER's) regarding the Environmental Qualification of Safety-Related Electrical Equipment at Point Beach Nuclear Plant, Units 1 and 2. On January 26, 1983 we transmitted our response to the SER's in which we reaffirmed the justifications for continued operation for Point Beach equipment items in NRC Qualification Category I.B, " Equipment Qualification Pending Modifications". This letter also contained an attachment which provided justification for continued operation for Point Beach equipment items identified in the SER's to be in NRC Qualification Category II.A, " Equipment Qualification Not Established". Due to the large-total volume of the SER's (approxi-mately 1,00~0 pages) and the short time available for the requested response (30 days) , the attachment to our January 26 letter contained several minor inaccuracies regarding the designation of the lubricants used in safety-related motors, pumps, and valve operators as well as the associated inspection and maintenance intervals. These inaccuracies were only identified after a detailed review of the attachment by the Point Beach Maintenance and Construction Superintendent. A revised justification for continued operation which corrects these inaccuracies and provides additional information is provided as an attachment to this letter.
These minor revisions do not change our judgment that Point Beach, Units 1 and 2, can continue to operate without undue risk to the public health and safety. We believe that the environ-mental qualification documentation already provided can be supplemented
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Mr. H. R. Denton February 18, 1983 for all Point Beach equipment items assigned to NRC Qualification Category II.A. This supplemental documentation will demonstrate environmental qualification to the provisions of the DOR Guidelines. It is our intention to request a meeting with your staff, specifically Equipment Qualification' Branch personnel, so that this' supplemental documentation can be reviewed. We will make arrangements for such a meeting through our NRC Project Manager as soon as the required additional documentation is assembled.
This letter is affirmed in accordance with the provisions of 10 CFR 50.54(f). We would be pleased to respond to any questions you may have in'this' matter.
Very truly yours, b f Vice Presi ent - Nuclear Power C. W. Fay Attachment Copy to NRC Resident Inspector Subscribed and sworn to before me this 4/gday of February 1983.
dWS WYb:_!& w Notary PdMlic, State of Wisconsin My Commission expires M.- /; /4 %Y.
. l Revision 1 2/18/83 1
JUSTIFICATION FOR CONTINUED OPERATION EQUIPMENT ITEMS IN NRC QUALIFICATION '
. CATEGORY II.A POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 SER Item PBNP Equipment No. Unit Description Justification for Continued Operation 24 1&2 Safety Injection 1. An analysis in the equipment qualification Pump Motors file justifies an in plant service life of (Westinghouse forty years as explained in Note T of our Thermalastic Epoxy October 11, 1981 response. Periodic in-Class B Insulation) service tests of the pumps performed monthly and meggar checks of the stator and lead wire insulation resistance performed at refueling intervals in accordance with the i PBNP maintenance call-up system should detect any unexpected degradation in the motor or associated leads.
- 2. The motor-to-lead splices were con-structed with silicon rubber tape (Scotch #70 or equivalent) insulation with a vinyl tape overall. Scotch #70tapegassatisfactorily tested for radiation (2x10 Rads gamma) and steam exposure in WCAP 7829. In addition, FRC Report F-C3694 documents the qualifica-tion including thermal aging of a similar silicon rubber insulation material used on instrumentation cable.
- 3. The motor bearing system consists of two split-sleeve-type, ring-oiled, radial journal bearings with a housing to keep out dirt and moisture. The motor bearings are lubricated with American Oil Co. ISO-Vg.
No. 68 or equivalent. This type of lubricant hasbeentestedsatisfactorilyforintegrated radiation doses in excess of 10 Rads gamma which exceeds the requirements for these motors.
The oil is replaced at two year intervals in accordance with the PBNP maintenance call-up system. The oil level and the bearing vibration and temperature are checked during operational checks of these pumps performed at monthly intervals in accord-l ance with PBNP inservice testing require-ments. The aging of the bearing / lubricant system is addressed by satisfactory service for over 12 years at PBNP.
i I
, . . . _ . , . _ _ - . _ _ . . _ , , _ _ . . _ , . _ _ , . _ , . _ _ _ _ - . . _ . . _ _ _ , . - . ~ . _ . , _ . . . ,
.m. ~- - ,__-r --, . . _- _ -
~
These motors (including the motor-to-lead splices and bearing / lubricant system) meet the qualification criteria of the D0R Guide-lines including the. aging criteria as clari-fied by NRC Generic Letter 82-09, Item 9.
Therefore, these motors are considered quali-fied to the provisions of the DOR Guidelines.
Additional documentation will be provQfed at a later time.
25 1&2 Containment Sprcy 1. See response to Item 24, Paragraphs 1 and Pump Motors 2, for justification for continued operation (Westinghouse Pre- regarding the thermal aging / service life of mium Moisture Re- the motor and the qualification of the motor-sistant Class B to-lead splices, respectively.
Insulation)
- 2. The motor bearing system consists of two shielded, anti-friction, radial, grease-lubricated, ball bearings with housings to keep out dirt and moisture. The bearing housing is greased at approximately three year intervals in accordance with the PBNP maintenance call-up system with a petroleum-based, lithium-soap-thickened grease. This type of lubricant has been tested satisfac-torily for 1 tegrated radiation doses in excess of 10 9Rads gamma which exceeds the requirements of these motors. These standby motors are checked for proper operation monthly including temperature and vibration measurements of the bearing system in accord-ance with PBNP inservice testing requirements as well as checked at refueling intervals by an operations refueling test. The aging of the bearing / lubricant system is addressed by satisfactory service for over 12 years at PBNP as well as tests of anti-friction bear-ings documented in WCAP 7829.
These motors (including the motor-to-lead splices and bearing / lubricant system) meet the qualifcation criteria of the DOR Guide-lines including the aging criteria as clari-fied by NRC Generic Letter 82-09, Item 9.
Therefore, these motors are considered qual-ified to the provisions of the D0R Guide-lines. Additional documentation will be pro-vided at a later time.
26 1&2 Component Cooling 1. See response to Item 24, Paragraphs 1 and Pump Motors 2, for justification for continued operation (Westinghouse Pre- regarding the thermal aging / service life of mium Moisture Re- the motor and the qualification of the motor-sistant Class B to-lead splices, respectively. No periodic Insulation) inservice tests are performed, however, be-
cause these motors are normally' operated for .
one month on and then one month off on a con-tinuous rotating basis.
- 2. The motor bearing system consists of two shielded, anti-friction, radial, grease-lubri-cated ball bearings with housings to keep out dirt and acisture. The bearing housing is greased at approximately one year intervals in accordance with the PBNP maintenance call-up system with a petroleum-based, lithium-soap-thickened grease. This type of lubricant has been tested satisfactorily for jntegrated radiation doses in excess of 10 Rads gamma which exceeds the requirements for these motors.
The operating component cooling pumps are checked for proper operation at least once per shift (about once every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />) as required by the auxiliary operator's log sheets. The standby pumps are started and the operating pumps secured by a periodic check on a monthly-basis. The aging of the bearing / lubricant system is addressed by satisfactory service for over 12 years at PBNP as well as tests of anti-friction bearings documented in WCAP 7829.
These motors (including the motor-to-lead splices and bearing / lubricant system) meet the qualification criteria of the DOR Guide-lines including the aging criteria as clar-ified by NRC Generic Letter 82-09, Item 9.
Therefore, these motors are considered qual-ified to the provisions of the DOR Guidelines.
Additional documentation will'be provided at a later time.
27 1&2 Residual Heat 1. See response to Item 24, Paragraphs 1 and Removal Pump Motors 2, for justification for. continued operation
! (Westinghouse Therm-regarding the thermal aging / service life of
. alastic Epoxy Class the motor and the qualification of the motor-l B Insulation). to-lead splices, respectively.
- 2. The motor bearing system consists of two shielded, anti-friction, radial, grease-lubricated, ball bearings with housings to keep out dirt and moisture. The bearing housing is greased at approximately one year intervals in accordance with the PBNP main-tenance call-up system with a petroleum-based, lithium-soap-thickened grease. This type of lubricant has been tested satisfactorily foy integrated radiation doses in excess of 10 Rads gamma which exceeds the requirements
of these motors. These mot. ors are checked for proper operation monthly including temper-
- 3. ature and vibration measurements of the bear-ing system in accordance with PBNP inservice testing requirements as well as checkee at refueling intervals by an operations refueling test. The motors are also operated each refuel-
+
ing during Residual Heat Removal system opera-tion. The aging of the bearing / lubricant system is addressed by satisfactory service for over 12 years at PBNP as well as tests of anti-friction bearings documented in WCAP 7829.
These motors (including the motor-to-lead splices and bearing / lubricant system) meet the qualification criteria of the DOR Guidelines including the aging criteria as clarified by NRC Generic Letter 82-09, Item 9. Therefore, these motors are considered qualified to the provisions of the D0R Guidelines. Additional documentation will be provided at a later time.
28 1&2 Containment Emer- 1. An aging analysis was performed which gency Fan Motors justifies an in plant service life (Westinghouse of forty years based on the qualifica-Thermalastic Epoxy tion tests documented in WCAPs 7829 Class F (Class A and 8754. Meggar checks of the motor and Temp. Rise) Insula- lead insulation resistance at refueling tion). intervals and disassembly, cleaning, inspection, and overhaul of the motor, as necessery, at every third refueling are performed in accordance with the.P8NP maintenance call-up system. This mainten-ance should detect any unexpected degrada-tion of the motor o- leads. The motor-to-lead splice and bearing / lubricant system qualification are addressed in items 29 and 53, respectively. These motors are con-l sidered qualified to the provisions of the DOR Guidelines.
- 2. The effects of plateout of Beta emitters l
on the stator insulation materials does not i have to be considered since the motor is totally enclosed. The only time the contain-ment atmosphere enters the enclosure is in the first ten seconds or so of an accident when a pressure equalization valve opens to admit enough air and/or steam to equalize pressure between the containment and the enclosure (see WCAP 7829, Figure 18). It is physically unrealistic for any radioactive fission products to have been released to the containment atmosphere in that time.
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l 29 1&2 Motor-to-Lead These splices were remade several years Splices for Item ago at PBNP to conform to the splices 28 -tested and qualified by WCAP 7829. Wes-tinghouse Drawing No. 206C391 is the basis ;
for this splice. . Separate effects tests for radiation and steam exposure were also conducted satisfactorili on the individual splice materials. Therefore, the splice is considered qualified to the DOR Guide-lines.
1
, ' 42 1&2 Okonite Instru- Documentation on our purchase orders estab-mentation Cable lish that the cable tested in FRC Test Report F-C3694 (Group II cables, Item 4A) is similar to our cable. The differences were analyzed and determined to have no effect on the qualification status of these cables. Our cables have a PVC jacket in lieu of an overall glass braid. The insula-tion material is identical as confirmed by a telephone conversation with Dr. Jack Lasky of Okonite Company. Therefore, this cable is considered qualified to the DOR Guide-
- lines. Additional documentation will be pro-l vided later.
, 50 1&2 Safety Injection These pumps have one anti-friction, oil-Pump Bearing lubricated, radial, ball bearing and one anti-Lubricant (Ameri- friction, oil-lubricated, thrust ball bearing can Oil Co. Indus- with housings to hold the oil and to exclude trial No. 68 oil) dirt and moisture. This type of oil has been tested satisfactorily 7for integrated radiation doses in excess of 10 Rads gamma which exceeds the requirements for these pumps. The oil l 1evel and the bearing vibration and tempera-l ture are checked during operational checks of the pumps performed at monthly intervals in accordance with PBNP inservice testing re-quirements as well as during operation refueling tests. The oil is replaced at two year intervals in accordance with the PBNP maintenance call-up system. The aging of the bearing / lubricant system is also addressed by satisfactory service for over 12 years at PBNP as well as tests of anti-friction bearings documented in WCAP 7829.
T.he bearing / lubricant systems meet the qual-ification criteria of the DOR Guidelines including the aging criteria as clarified by the NRC Generic Letter 82-09, Item 9.
Therefore, these bearing / lubricant systems are considered qualified to the provisions i
of the DOR Guidelines. Additional documenta-I tion will be provided later.
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51 1&2 Component Cooling These pumps have one anti-friction, oil-Pump Bearing Lubri- lubricated, radial, hall bearing and one cant (American Oil anti-friction, oil-lubricated, thrust, ball Co. Industrial No. bearing with housings to hold the oil and to 46 oil) exclude dirt and moisture. This type of oil hasbeentestedsatisfactorilyforintegrated radiation doses in excess of 10 Rads gamma which exceeds the requirements for these pumps. The operating pump (one of two for each PBNP unit) is checked once each shift in accordance with the auxiliary operator log sheets. The standby pump is started and the operating pump secured at monthly intervals in accordance with the PBNP per-iodic check system. The oil is replaced at one year intervals in accordance with the PBNP maintenance call-up system. The aging of the bearing / lubricant system is also addressed by satisfactory service for over 12 years at PBNP as well as tests of anti-friction besrings documented in WCAP 7829.
ihe bearing /iubricant systems meet the qualification criteria of the DOR Guide-
< lines including the aging criteria as clarified by the NRC Generic Letter 82-09, Item 9. Therefore, these bearing / lubricant systems are considered qualified to the pro-visions of the DOR Guidelines. Additional documentation will be provided later.
52 1&2 Containment Spray These pumps have one anti-friction, oil-and RHR Pump Bear- lubricated, radial ball bearing and one anti-ing Lubricant friction, oil-lubricated, thrust, ball bearing (American Oil Co. with housings to hold the oil and to e>clude Rykon Industrial dirt and moisture. This type of oil has been No. 32 oil) tested satisfactorily 7for integrated radiation doses in excess of 10 Rads gamma which exceeds the requirements for these pumps. The oil level and bearing vibration and temperature are checked during operational checks of the pumps performed at monthly intervals in accordance with PBNP inservice testing re-quirements as well as operations refueling tests performed at refueling intervals. In
! addition, the RHR pumps are operated during I refueling outages during operation of the RHR l
system. The oil is replaced at one year in-tervals on the RHR pumps and three year inter-vals on the containment spray pumps, which are used for standby service only. The aging of the bearing / lubricant systems is also addressed by satisfactory service for over 12 years at PBNP as well as tests of anti-friction bearings documented in WCAP 7829.
The bearing / lubricant systems meet the qualification criteria of the DOR Guidelines including the aging criteria as clarified by the NRC Generic Letter 82-09, Iter 9.
Therefore, these bearing / lubricant systems are considered qualified to the
. provisions of.the DOR Guidelines.
Additional doccmentation will be provided later.
53 1&2 Containment Emer- The containment emergency fan cooler motors gency Fan Cooler use open anti-friction, grease-lubricated, Bearing Lubricant radial ball bearings with sealed housings.
(Chevron SRI The bearings are air-cooled by the same inte-grease) gral, air-to-water heat exchanger assembly which provides closed-cycle cooling and protection from accident environments for the motor. The bearings are checked and greased at refueling intervals with Chevron SRI grease in accordance with the PBNP maintenance call-up system.
The motors are disassembled including cleaning, inspection, and regreasing of the bearings every third refueling. The motors and fans are checked for proper operation including checks for noise, vibration, air and cooling water flow, and running current on a monthly inter-val in accordance with PBNP periodic l check and Technical Specification require-ments. In addition, the motors are normally running at approximately one-third design load and a vibration switch i
alarms in the control room if vibration exceeds a pre-set level. The bearing lubricant tested in the qualification tests documented by WCAP 7829 was Westing-house Style No. 773A773 which is Chevron BRB #2 grease. Chevron and Westinghouse both discontinued this grease several years ago but Chevron now supplies SRI grease which is documented to be equivalent (actually better) than BRB #2 grease.
The Chevron BRB #2 grease was tested for irradiation and " working" to simulate the conditions in containment following a design-basis LOCA as documented in the PBNP FSAR, pp. 6-3-16 through 19. The resultsshowthatthegreasewasstigl suitable after irradiation to 1.8x10 Rads gamma which exceeds the requirements of these motors. Based on the above e
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l l documentation and the satisfactory service at PBNP for over 12 years, it is concluded that the bearing / lubricant system will. perform its safety function satisfactorily. Additional documentation will be provided later.
. 2. The fan bearings consist of open anti-friction, grease-lubricated, spherical roller bearings with sealed pillow-block housings. The bearings and seals are
> disassembled, cleaned, inspected, and regreased at refueling intervals and the be.arings are greased once in between refuelings in accordance with the PBNP maintenance call-up system. The same.
grease is used for the fan bearing as described in paragraph 1 for the motor bearings (i.e., Chevron SRI). The grease used in the labyrinth seals of the bearing housings and qualified by WCAP 7829 was Westinghouse Style No. M-53701TT which is E.I. Dupont de Nemours & Co.,
Inc. Krytox 240 AC Fluorinated grease.
Based on the above documentation and the satisfactory service at PBNP for over 12 years, it is concluded that the bearing / lubricant system will perform its safety function satisfactorily.
Additional documentation will be provided later.
54 1&2 Limitorgue Valve These greases are petroleum-base greases Motor Operator with lithium or calcium-soap-thickeners and Lubricant (Ameri- extreme pressure (EP) additives. A number can Oil Co. Amolith of similar greases were yadiation tested
- 1 EP or AMDEX #2 satisfactorily to 2.7x10 Rads and higher as EP greases) documented in an ASLE paper. This radiation level exceeds the requirements of these motor operators at PBNP. These operators are checked for proper operability at refueling intervals and/or quarterly in accordance with PBNP inservice testing requirements. These oper-ators are overhauled including replacement of greases at five year intervals in accor-dance with PBNP maintenance call-up system.
The greases have shown excellent service in over twelve years of operation at PBNP.
Similar greases have been used in numer-ous qualification tests of Limitorque
c.
operators under LOCA and SLBA conditions.
Therefore, continued safe operation of PBNP is assured until additional documentation is generated regarding similarity and aging.
, 55I 1&2 Pump Motor See response to Items 25, 26, and 27 regarding
! . Bearing Lubricant the motor bearing / lubricant system qualifica-(American Oil Co. tion.
Amolith #2 grease) 56 1&2 Limitorque Valve Mobil 28 grease is a synthetic lubricant Operator Geared which has been g radiation tested satisfac-Limit Switch torily to 3x10 Rads mixed gamma / neutron Assembly Lubricant radiation and tested satisfactorily in (Mobil Oil Co. bearings at temperatures of 580*F. These No. 28 grease) operators are checked for proper operabil-ity at refueling intervals and/or quarterly in accordance with PBNP inservice testing requirements. These operators are overhauled including replacement of greases at five-year intervals in accordance with the PBNP maintenance call up system. This grease is listed as an acceptable lubricant by Limitor-que for qualified Model SMB valve operators.
Therefore, this lubricant is considered qual-ified for use on all Limitorque valve oper-ator geared limit switch assemblies at PBNP.
61 1&2 Power Operateo This item is not required to mitigate a LOCA Relief Valve or HELB accident and is not considered Blocking Valve safety-related. Therefore, lack of quali-Limitorque Motor fication documentation does not affect Operators (Peer- plant safety.
Less Motor with Class B insulation) 62 1&2 Safety Injection These valves are administrative 1y maintained Line Valve in their required shut position for safety Limitorque Motor injection and are,therefore, not normally Operators (Peerless required to operate on receipt of a safety Motor with Class B injection signal. These valves may be insulation) opened within 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br /> of a small-break LOCA to aid in coolant mixing to prevent boron precipitation. As discussed in Mr. Sol Bursteins' letter to your staff l
dated May 7, 1975 regarding "ECCS Long Term 1 Cooling," boron precipitation is not a problem at PBNP even if these valves failed to open within 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br /> of a LOCA. There-l fore, PBNP can continue to operate safely i until this item is resolved.
.~ 1 63 1&2 Safety Injection Tnese valves are administrative 1y mairi-Line Valve tained open during normal operation which Limitorque Motor is their required position upon receipt Operators (Reli- of a safety injection signal. If these ance Motors with valves were initially closed, they would l Class B insulation) open immediately upon receipt of a safety injection signal. Their required operating
, time should be 1/2 hour and not 14 f.ours as stated on the SCEWs. Similar valve operators operated satisfactorily for 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> in simulated LOCA conditions as documented in WCAP 7410L. Therefore, PBNP can continue to operate safely until this item is resolved.
65 1&2 Auxiliary Feedwater Limitorque has confirmed that the valve Pump Steam Supply motor operators at PBNP.are identical Valve Limitorque to those tested in Limitorque Test Operators (Peerless Report No. 80003 except for the Peerless Motor with Class B motors. A Limitorque analysis has deter-Insulation) mined that Peerless motors with Class B insulation are equivalent to the Reliance motors with Class B insulation environmentally tested as documented in Limitorque Test Report No. B0003 and Westinghouse WCAP 7410-L.
Since the temperature / pressure profile used for qualification of these valves is extremely conservative, the operators are judged to be able to perform their safety function based on a combination of the two test reports. Since these valves are located in an area normally maintained between 65*F and 85*F and based on their satisfac-tory service for over 12 years at PBNP, no significant thermal aging degradation has occurred up to this point. Therefore, the continued safe operation of PBNP is assured l until this item is resolved.
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