ML20069D593
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MONTHYEARML20205H9841976-07-0606 July 1976
[Table View]Forwards Draft Amends 18 & 23 to Licenses DPR-24 & DPR-27, Respectively, & Safety Evaluation.Amends Revise Tech Specs to Add Surveillance Requirements & Place Limit on Max Weight of Spent Fuel Shipping Cask Used Project stage: Draft Approval ML20041C7351982-02-25025 February 1982 Forwards Tentative Schedule for Submittal of 6-month & 9-month Repts on Outstanding Response Items Concerning NUREG-0612 Re Control of Heavy Loads,Per NRC 820201 Request Project stage: Request ML20054G6221982-06-16016 June 1982 Forwards Response to NRC Question Attachment 1-5 Re Interfacing Lift Point Evaluation.Info Provided as Revised Pages to 9-month Response to NUREG-0612, Control of Heavy Loads Project stage: Other ML20054L0981982-06-30030 June 1982 Submits Addl Info for Draft Technical Evaluation Rept on Util Response to NUREG-0612, Control of Heavy Loads, Per 820520 Telcon Project stage: Draft Other ML20069D5931982-09-16016 September 1982 Forwards Response to NRC Question Attachment 1-1 Re Manufacturer Design Info on Single Failure Proof Cranes & Revised Response to NRC Attachment 1-5 Concerning Interfacing Lift Point Evaluation Project stage: Other ML20065S1291982-10-22022 October 1982 Requests Expeditious Review & Approval of Revision 3 to Ederer,Inc Generic Rept EDR-1, Nuclear Safety-Related Extra-Safety & Monitoring (X-SAM) Cranes to Assist in Completing Auxiliary Bldg Crane Upgrade in Timely Manner Project stage: Other ML20066K0641982-11-22022 November 1982 Forwards Revised Pages 10,11 & 11a to Response to NRC Question 2.3-4-b Re Control of Heavy Loads,Including Results of Reactor Pressure Vessel Head Drop Analysis.Info Should Be Included in 9-month Response Project stage: Other ML20072K8201983-06-17017 June 1983 Control of Heavy Loads (C-10),Point Beach Nuclear Plants Units 1 & 2, Draft Final Technical Evaluation Rept Project stage: Draft Other ML20080M9231983-09-28028 September 1983 Forwards Addl Info Requested in 830810 Telcon Re Franklin Research Ctr 830617 Draft Technical Evaluation Rept on Util Response to Phase 1 of NUREG-0612, Control of Heavy Loads at Nuclear Power Plants Project stage: Draft Other ML20086T8821984-03-0202 March 1984 Control of Heavy Loads (C-10) Wisconsin Electric Power Co Point Beach Nuclear Plant Units 1 & 2 Project stage: Other 1982-06-16 |
| ML20069D593 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 09/16/1982 |
| From: | Fay C WISCONSIN ELECTRIC POWER CO. |
| To: | Clark R, Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| REF-GTECI-A-36, REF-GTECI-SF, RTR-NUREG-0612, RTR-NUREG-612, TASK-A-36, TASK-OR TAC-07727, TAC-08074, TAC-7727, TAC-8074, NUDOCS 8209210319 | |
| Download: ML20069D593 (4) | |
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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
[Table view]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. 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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. 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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 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
[Table view]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 Category:UTILITY TO NRC MONTHYEARML20059H9391990-09-13013 September 1990
[Table view]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 |
Text
Wisconsin Electnc powra coursur 231 W. MICHIGAN, P.O. BOX 2046, MILWA'!KEE WI 53201 September 16, 1982 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 SUBMITTAL OF OUTSTANDING INFORMATION NUREG-0612, CONTROL OF HEAVY LOADS POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 Your letters dated December 22, 1980 and February 3, 1981 requested that Wisconsin Electric Power Company review the handling of heavy loads at the Point Beach Nuclear Plant and provide information as requested in Enclosure 2 to the December 22 letter. Our transmittals of September 30, 1981 and January ll, 1982 submitted our six and nine-month responses, respectively, which included the majority of the information requested in your letters. Our February 25, 1982 letter provided a proposed schedule for the completion of those outstanding information items.
Enclosed for your review is Wisconsin Electric's response to NRC Question Attachment 1-1, " Manufacturer and Design Informa-tion on Single-Failure-Proof Cranes". This information is provided in the form of a revised page 3 f.or inclusion in our nine-month response.
Also enclosed for your review is a revised response to NRC Question Attachment 1-5, " Interfacing Lift Point Evaluation".
[033
)
8H20 9 210 3 lCl i
r Mr. H. R. Denton September 16, 1982 This information is provided in the form of a revised Appendix D for inclusion in our nine-month response.
Please contact us if you have any questions.
Very truly yours, Assistant Vice President C. W. Fay Enclosures Copy to NRC Resident Inspector Subscribed and sworn to before me this /$1 day of September 1982.
M8 Wh4 Y=.
N5tary PulgitTc, State of Wisconsin
~
My Commission expires / /ff[
7,
Revision 1
~
2.3- NRC QUESTION 2.2-3 Identify any cranes listed in 2.2-1, above, which you have evaluated as having sufficient design features to make the likelihood of a load drop extremely small for all loads to be carried and the basis for this evaluation (i.e., complete compliance with NUREG-0612, Section 5.1.6 or partial compliance supplemented by suitable alternative or additional design features). For each crane so evaluated, provide the load-handling-system (i.e., crane load-combination) information specified in Attachment 1.
RESPONSE
The auxiliary building crane will be modified to meet the guidelines of NUREG-0612, Section 5.1.6, or partial compliance supplemented by suitable alternatives or additional design features. Dependent upon equipment delivery, it is expected that the auxiliary building crane upgrade modifications can be completed within two years.
The information requested on Single-Failure-Proof Handling Systems in Attachment 1 to the NRC letter of December 22, 1980, is provided below.
Information on Single-Failure-Proof Handling System 2.3.1 NRC QUESTION ATTACHMENT l-1 Provide the name of tha manufacturer and the design-rated load (DRL). If the maximum critical load (MCL), as defined in NUREG-0554, is not the same as the DRL, provide this capacity.
RESPONSE
Ederer Crane, a division of Ederer Incorporated, will be supplying a single-failure-proof replacement trolley for the auxiliary building crane. The trolley will be Ederer's X-SAM type and will have a Design Related Load (DRL) and Maximum Critical Load (MCL) of 100 tons.
2.3.2 NRC QUESTION ATTACHMENT l-2 Provide a detailed evaluation of the overhead handling system with respect to the features of design, fabrication, inspection, testing, and operation as delineated in NUREG-0554 and supple-mented by the identified alternatives specified in NUREG-0612, Appendix C. This evaluation must include a point-by-point comparison for each section of NUREG-0554. If the alternatives of NUREG-0612, Appendix C, are used for certain applications in 1.09/11 Rav. 2
/ 2 o 2. -
APPENDIX D Interface lift points were evaluated in accordance to NUREG-0612, Section 5.1.6 and the results are tabulated below in Table Dl.
TABLE D1 EQUIPMENT WEIGHT MATERIAL / REQUIRED CALCULATED UTS (KSI) SAFETY SAFETY FACTOR FACTOR Concrete Hatch 6,250 A-36/58 10 11.52 Covers Large Filter Cask 5,000 A-36/58 10 17.40
(' Small Filter Cask 2,000 A-36/58 10 43.50 Resin Cask 48,000 A240 Type 304 10 11.44
/75 Spent Fuel Pool 3,000 A-36/58 10 29.00 Gate (Watergate)
O 136/51
.
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