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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:PUBLIC ENTITY/CITIZEN/ORGANIZATION/MEDIA TO NRC
MONTHYEARML20151C9021988-01-11011 January 1988 Comments on 871021 Final Rept NSAC-113, Epri/Westinghouse Owners Group Analysis of DHR Risk at Point Beach, Per NRC Request.Resources Did Not Permit Exam of Plant,Review of Training Procedures & Emergency Guidelines ML20235G5651987-09-15015 September 1987 FOIA Request for Documents Re Test of Wisconsin Electric Power Co Emergency Procedures at Plant ML20238B7731987-08-0707 August 1987 FOIA Request for Records Explaining Status of Listed LERs Omitted from List,Previously Received from Nrc,Of LERs Filed by Commercial Nuclear Power Plant Licensees for Operating Year 1986 ML20236J6131987-06-22022 June 1987 FOIA Request for All Documents Re 235 Gallon Discharge of Facility Radioactive Cooling Water on 870619,per Encl Newspaper Article ML20206P7471987-04-14014 April 1987 Offers Observations & Comments Re Util Results of Exams of Poison Insert Assemblies Removed from Spent Fuel Storage Racks. Util Should Submit Surveillance Plan W/Test Procedures to Determine Condition of Damaged Areas ML20212Q8831987-03-18018 March 1987 FOIA Request for Documents Re Jul 1986 Breach of Security at Plant ML20198M9631985-06-17017 June 1985 Forwards Allegations of Safety Violations of Nuclear Regulatory Law or Westinghouse QA Requirements.Investigation Requested.Related Info Encl ML20112D3251984-10-10010 October 1984 Requests Continued Inclusion on Svc List.Although Formal Steam Generator License Proceeding Complete,Underlying Issues of Steam Generator Tube Degradation & Associated Problems Continue ML20094S6591984-08-10010 August 1984 Comments on Proposed Rule 10CFR50 Re Sufficiency of Justification for Continued Operation for Wisconsin Electric Power Co,Point Beach Nuclear Plant I & Ii.Streamlining NRC Licensing & Regulatory Roles Inadequate in Solving Problems ML20077N9711983-09-0909 September 1983 Requests NRC Position Re Need for License Amend to Allow Return of 114 Spent Fuel Assemblies Originally Removed from Facilities ML20027E3151982-11-0505 November 1982 Forwards Contentions Re Steam Generator Replacement ML20054H9931982-06-22022 June 1982 Objects to Licensee Intention to Replace Two Steam Generators,Per ,W/O Requesting License Amend ML20050A5391982-03-28028 March 1982 Forwards Motion to Compel Answers to First Set of Interrogatories Re full-scale Sleeving.Permission Requested to Undertake Discovery Re Recent Events at TMI & Ginna. Related Correspondence ML20042C5331982-03-24024 March 1982 Requests Time for Commission to Act to Review Aslab Decision Be Extended Until 10 Days After Receipt of Document. Commission 820316 Order Alludes to Aslab Decision ML20042C5391982-03-24024 March 1982 Requests Any Aslab Decision Rendered in Docket.Commission 820316 Order Alludes to Aslab Decision ML20041F9931982-03-12012 March 1982 Opposes Licensee 820127 & 0305 Request to Extend Interval Between Steam Generator Insps & to Rely on full-cycle Insps.Ginna Incident Impels Necessity to Require Immediate Shutdown & Insp ML20041F0851982-03-0404 March 1982 Forwards Attachments to P Anderson 820223 Affidavit Not Under Trade Secret Order of PSC of Wi ML20039E3811981-12-28028 December 1981 Advises That Wi Environ Decade 811119 Notice of Appeal from ASLB Decision Directed to Full Commission Not Aslab.Time Consumed by Addl Layer of Appeal Would Moot Any Effective Relief.Requests Commission Take Jurisdiction ML20039C6931981-12-22022 December 1981 Discusses Licensee 811209 Motion for Dismissal of Wi Environ Decade.Motion Is Really Motion to Compel Discovery.Discovery Cannot Compel Opposing Party to Produce Something Which Does Not Exist ML20011A6691981-10-23023 October 1981 Forwards First Set of Discovery Documents.Documents Are Incomplete Due to Time Limits.W/O Encl ML20010D9671981-08-24024 August 1981 Ack Receipt of NRC 810811 Ltr Responding to Request for Order to Bar Licensee from Increasing Hot Leg Temp of Primary Sys.Nrc Ltr Reinforces 810704 Ltr,In That Licensee & Commission Are Treating Safety Matter as Experiment ML20010D2191981-08-17017 August 1981 Informs of Wi Environ Decade Address Change ML20009E5231981-07-22022 July 1981 Requests Answer to 810704 Petition for NRC to Issue Order Prohibiting Facility from Increasing Power from 75% to 85%. Reasons Should Be Given for Allowing Increase on 810720 ML20009D9481981-07-20020 July 1981 Forwards Petition for Admission as Party,Hearing & EIS Re Facility Steam Generator Tube Sleeving Program.Notice of Representation Encl ML19331D7271980-08-26026 August 1980 Requests Permission to Suppl Wi Environ Decade Previous Filings Supporting Adjudicatory Hearing Re Petitioner Preliminary Contentions.Nrc 800808 Ltr Authorizes Facility Restart W/O Offer for Adjudicatory Hearing ML19337A0791980-08-26026 August 1980 Discusses 800808 Ltr Authorizing Restart & Alluding to Informal Understanding Between NRC & Licensee Re Future Insp.Expresses Belief That Action Thwarts Meaningful Public Participation ML19331B9741980-07-26026 July 1980 Opposes HR Denton 800710 Memo Requesting That Commission Incorporate Intervenors Wi Environ Decade 800329 Request for Hearing W/Prior Requests.Nrc 800512 Order Will Exclude Consideration of Safety Issues from Prior Requests ML19321B3141980-07-26026 July 1980 Opposes Util Request for Amend to Mod Order on Grounds That Seriousness of Tube Degradation Problem Demands Complete Review of 90 Effective Full Power Day Insp Results by NRC Before Operation Permitted to Resume ML19330A8381980-07-22022 July 1980 Requests That Facility Not Be Allowed to Continue Operating W/Faulty & Defective Steam Generator Tubes.Defective & Deteriorated Tubes Should Be Replaced Now.Situation Presents Potential for Another TMI-2 Incident ML20049A2661980-07-18018 July 1980 Requests Submitted on Behalf of League Against Nuclear Dangers,Concerning Relocation of Local PDR to Manitowoc,Wi. Lists Types of Documents & Specific Documents That Should Be Retained at Univ of Wi Library ML19321B1721980-07-14014 July 1980 Ack Receipt of Directors' 800710 Decision Re Facility. Attachments to Decision Jumbled.Requests Complete Set of Attachments ML19330A8361980-07-14014 July 1980 Urges NRC to Conduct Full Probe of Facility Operation During 800730 Prehearing Conference.Safety Assurances Should Be Given to Community.Local Newspapers Deficient in Detailing Concerns ML19317H5161980-06-0505 June 1980 Discusses NUREG/CR-1280 Re Power Plant Staffing.Util Has Neither Unlimited Funding Nor Unlimited Supply of People to Implement Sys Which Navy Has Developed.Lists TMI-related Aspects Which Have Been Overlooked ML19316A7841980-05-12012 May 1980 Discusses NRC 800502 Order Granting Extension Until 800513 to Request Hearing.Requests 11-day Extension to Draft Hearing Request.Nrc Order Only Provides One Day to Prepare Request ML19309H4911980-05-0404 May 1980 Requests Establishment of New PDR in Madison,Wi.Document Room Is Necessary in Madison Because of Significant Decisions Affecting Plant Presently Being Made by State Govt.Existing Document Room Inadequate ML19331B9761980-04-26026 April 1980 Ack Receipt of NRC 800421 Ltr Re Svc of Documents Filed by Nrc.Nrc Failed to Serve Intervenor W/Mod of 791130 Order. Forwards Motion for Extension of Time to Request Hearing. Certificate of Svc Only Encl ML19309A8301980-03-27027 March 1980 Protests Licensees Failure to Serve Filings Re Steam Generator Tube Degradation.Reiterates Request for Relief as Stated in 800226 Ltr & Requests NRC to Direct Licensee to Serve Documents ML19294C0271980-03-0202 March 1980 Requests Clarification of Licensee 800226 Ltr Stating That Five Defective Tubes Found During Oct 1979 Insp Will Be Pulled ML19296D3921980-02-26026 February 1980 Notifies That Intervenor Is Being Served W/Pertinent Documents.Requests That Commission Enforce Ex Parte Rules Against Util & Institute Specific Procedures to Ensure That Future Ex Parte Documents Are Not Considered ML19294B6671980-02-11011 February 1980 Notifies That NRC 800103 Order Modifying 791130 Confirmatory Order Did Not Arrive Until Period for Requesting Hearing Had Expired.No Acknowledgement Received Re 791126 Petition to Intervene ML20125D4411980-01-0808 January 1980 Discusses Licensee Re Steam Generator Tube Degradation.Licensee Deliberately Misrepresented Facts.No Reliable Basis for Concluding That Identified Defects Outside Crevice Are of pre-1975 Origin ML19270H8341979-12-17017 December 1979 Forwards Request for Hearing on NRC 791130 Confirmatory Order for License Mod.Urges Review of 791130 Director'S Decision Per 10CFR2.206 Denying Wi Environ Decade Petition. Raises Question of Inleakage in Tubes During LOCA ML19260B9421979-11-29029 November 1979 Requests That Future Hearing,Re Removal & Storage of Generators,Be Held in Manitowoc,Wi ML19262A7441979-11-26026 November 1979 Forwards Response to Applicant 791123 Ltr.Formal Petition to Intervene Re OL Amend Will Be Filed on 791102 ML19210D9711979-11-14014 November 1979 Forwards Requests for Issuance of Order to Show Cause & to Enjoin Facility Reopening.Requests Notice of Util Application to Increase Limiting Conditions of Steam Generator Tubes ML19290B6671979-11-0707 November 1979 Requests NRC Investigation of Safety Aspects of Steam Tube Generator Leaks.Meeting Should Be Held to Inform Public of Findings ML19282A1741979-04-12012 April 1979 FOIA Request for Internal Files of Facilities ML19289C2121978-11-13013 November 1978 Requests Copies of NUREG-0410 & NUREG-0471 ML20027A1671978-09-25025 September 1978 Requests That Author 780510 Ltr Be Sent to Univ of Wisconsin ML20087K8821975-03-28028 March 1975 Requests Receipt of Util Re Details of 750226 Steam Generator Tube Failure 1988-01-11
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pitoTec36eW January 8,1980 Mr. Harold R. Centon, Director Office of Nuclear Faactor Fegulation U. S. Nuclear Fegulatory Comission Wa shing ton , D. C. 20555 Fe : Point Eeach Nuclear Plant Unit 1 Do cket 50-266 i
Cear Mr. renton:
Peference is made to the steam generator tube degradation matter in rJ1ving Point Beach Nuclear Plant Unit 1 and the licensee 's letter to you dated recember 21 1979, which appears to be in response to our Fequest fer Hearing on Confirm-atory Order, dated Cecember 17, 1979.
There are two issues raised by the licensee 's letter, to -wit : (A) the veracity of its representations to the Staf f and the Commission in the period November 20-28,1979 and (3) the adequacy of its hymthesis dat the five tubes identified in October 1979 to be defective at or ateve the top of the tubesheet are of pre-1975 origin . This letter is to respond to those tw issues. Que stion s relating to any culpability on the part of the Staf f for emitting pertinent in-for ation have been dealt with separately and are not treated here.
(A) VERACITY OF LICENSEE 'S REPFESENTATIONS The matter in controversy concerns the conclusion of the American Physical Society (APS) to the effect that the rupture of between one and ten steam gener-ator tubes during a loss-of-coolant-accident (LCCA) could create essentially un-coolable conditions in the reactor core . (See: Lewis, et al . , "Re po rt to the American Physical Society by the American Physical Society by the Study 7,roup on Light-Water Beactor Safety," 47 Feview o_f >bdern Physics 1, Summer 1975, at App . 1, 58 5-91. )
Point Beach I has been and is experiencing degradation of its steam generator tubes to such an extent as to lead to a concern that the number of in cipient tube f ail-
- ures at any given nement when a LCCA may occur is sufficient to raise the most
( serious questions identified by the APS. (See: Petition o f Wisconsin 's Environ-
[ mental Decade, Inc . , dated Ncvember 14, 1979, In the Matter of Wisconsin Electric Power Company, Decket 50-266, at 3 to 3.)
The licensee in its letter to you dated November 23, 1979, which letter sum-l i
mari:ed its version of a Ibvember 20, 1979 meeting between it, S ta f f, We s tinghouse I
and ourselves, stated as its basis for refuting this concern and for permitting l
the plant to continue operating: f/ O 90017178 <% e opug gp e
M 8001140 g -
Mr. Harold R. Denton January 8,1980 Page 2 "Although Wisconsin's Environmental Cecade petition contained a number of statements which we believe are in error, its major safety concern re-lates to the American Physical Society, Lewis Report, (1975), reference to the potential for steam generator tube failure during a severe LCCA which could adversely affect ECCS performance. Since the present tube degradation problem at Point Beach is confined to the tube sheet crevice area, and since a tube collapse within the tube sheet area cannot occur during a LOCA or o therwis e , the possibility of having secondary side inventory interfere with blowdown and reflood during a LOCA does not exist. In so f ar a s rup ture oj a_ tube above the tubo sheet during ICCA is concerned, there is nothing in the present or foreseeable steam generater tubing characteristics inspec-tion or operating programs that constitutes a change f rem previous conditions. "
( Se e : id,, at 7, emphasis added.)
The Staf f's minutes o f the November 20, 1979, meeting, which were distributed on November 23, 1979, similarly shew the following in this regard:
"The licensee stated that the LOCA steam binding phenomenon for broken tubes is not applicable tc the current Point Beach tube problems, since the tubes are defective below the tube sheet and large leaks cannot occur here.
The rest of the SG tubes (above the tube sheet) are not experiencing problems. "
(Se e id., at 2 to 3.)
The licensee 's representations were adopted by the Staff at the November 28, 1979 meeting of the Commission. Mr. Eisenhut, for the Staf f, stated to the Commissioners :
"Every piece of evidence we have ever seen shows that all of these defects are in the crevice. They are below the upper surface of the tube sheet."
n * * ,
"Therefore, while the steam binding question is a good theoretical question, we believe it is not directly applicable tc this situation, be-cause we really believe that all the degradation we are seeing is actually with tubes in the tube sheet. " ( Se e : Transcript of Public Meeting, 28 Nov-ember 1979, at 85 . See, al so : Transc rip t, at 6, 17, 25, 26, 29 and 39.) 1/
At the same meeting, representatives of the licensee, attorney Gerald Charnoff and executive vice-president Sol Burstein, attended, observed the staf f presenta-tion and then made their own presentation. Mr . Charno f f stated :
"If there is any contention between us, it would go only to the frequency and intensity of the surveillance requirements, a * * *
"[W]e have from the outset of this condition and actually over the years kept the staf f fully informed of the conditions of the tubes." ( Se e : Id . ,
at 54 and 56, emphasis added.)
1/ To the extent required by 10 C.F.R. 9.103, authorization is requested to cite the above-mentioned pertions of the transcript f rem the November 2 3, 1979 public mee ting.
910017179
Mr. Harold R. Denton January 8,1980 Page 3 No correction was proffered to the Commission by the licensee of the Staff's foregoing statements .
Following the N3vember 28, 1979 Commission meeting, the Staff issued its Safety Evaluation Report of the problem, dated :bvember 30, 1979, which stated:
"No crevice indications extending above the tubesheet have been observed to date." (See: Id . , at 10.)
Ob correction was submitted to the Staff by the licensee of this statement.
On December 17, 1979, we submitted a Request fcr Hearing on Confirmatory Order for several reasons. Cne reason was that we had just become aware that prior to its representations during November 20-23, 1979, the licensee had identified five tubes with defects not in the crevice region. A question was raised as to whether the licensee had deliberately mislead the Commission in order to secure approval to continue operation.
By letter dated December 21, 1979,1/ the licensee has submitted its explana-tion for the apparent misrepresentation of this fundamental matter. Es sen tiall y ,
the licensee's justification is premised upon two contentions: (1) a putative dif ference between "intergranular attack" and the kind of degradation in the five tubes with defects at or above the top of the tubesheet and (2) a claim that its prior representations only denied the existence of "intergranular attack" above the tubesheet and not the kind of corrosion found in the five tubes.
We believe that the evidence available shows that neither justification is true and only serves to continue the licensee's policy of mendacity.
(1) Purported Difference Between Intergranular Attack and the Degradation in the Five Tubes The licensee states in its December 21 letter that it "made no attempt to re-late the eddy current inspection results (o f the five tubes] with the presense or absense of IGA [in its Movember 20-2S representationcl ." (See: 11., at 3.)
That is to say, the licensee is attempting to distinguish "intergranular attack" in kind from the degradation in the five tubes with defects at or above the top of the tubesheet such as to explain the failure to mention those five tubes in its November 20-28 representations ostensibly limited to IGA. This purported distinction is a total fabrication. The only dif ference is t.o t in kind but rather in location.
As stated in the S taff's compendium of the issue, there are essentially three kinds of tube degradation which have been observed to date: (1) wastage or thinning (a generaliced form of corrosion attributed to residual acidic phosphates), (ii)
! intergranular stress corrosion cracking (a stress type of corrosion attibuted to caustic impurities) , and (iii) denting (a deformation of the tube wall attributed
( to corrosion products on the carbon steel support plates) . (See: Eisenhut, et l al . , Summary oi Cperating Experience with Recirculating Steam Generators, NUFE G-0523(1979), at 3 to 4.)
l l
1/
90017180 The letter was mailed, to us in a envelep postmarked December 26, 1979.
.- .. .. . -- .. .. - . - . . _ . . ~ - . - - - -
P
~I; Mr. : Harold Denton' i January 8,1980 page 4 e
Thus, "intergranular attack" is not something new and different and uniqpe i to . the tubesheet crevice and recent experience at Point Beach 1. The only new element here is that the location of intergranular stress corrosion within the tubesheet seems to sometimes evince itself in a modified form apparently due .to j the constraining effect of the surrounding wall. In se ce ins tances , the corrosive attack on the grain boundaries appears to be bi-directional and generalized.
instead of along a crack. ( See : Transcript, og. cit . , at 88; Safety Evaluation Pepo rt, op_. cit., at,12.)
Intergranular attack remains intergranular attack, whether above or below the tubeshee t--except that when it is located below the tubesheet, it sometimes ;
may not clearly delineate an attendant, observable crack. .
To the s ame e f fe ct, there is no basis for attempting to characterize the degrad-ation in the five tubes as thinning and not intergranular stress corrosion. For, according to the Staf f's ECT consultant, with whom we talked on the telephone, no eddy current inspection presently available can distinguish between thinning and i IGA in the abrense of a single large crack.
Therefore, no justification exists for the licensee's f ailure to inform the Commission of the five defective tubes in a discussion which it now attempts to characterize as being limited to IGA. And, even if arguendo there were, that kind of hair splitting is inconsistent with a frank and honest exchange of information.
Similarly, the licensee's December 21 claim that it believes "that the defects
- resulted from earlier thinning or cracking rather than to the IGA"(see: Id.,
at 4) has no meaning to the extent that it is meant to imply that dif ferent kinds of. corrosion are involved to support a vintage argument. For there can be no j disputing that the so-called " earlier thinning andcracking" consisted in substantial ;
part of "intergranular attack" and "intergranular corrosion"(see , e.g .: Office of Inspec tion and Enforcement, [3 Ins pection Re po rt No . 050-266/75-03, dated April 11, 1975, a t 4, 5 and 6) , just as tac present so-called " crevice corrosion" is a form of "intergranular attack"(see : Safety Zvaluation Peport, o,,y_. cit . , at 5) .
Thus, the only new element is the location anc not the kind of degradation, and, of course, it is the failure to fully inform as tw location that raises the most serious questions of wanton misrepresentation.
That same re ference to " earlier thinning and crackir.7" may also be meant to imply. that the five tubes were omitted from the November 20-28 representr. cions because those representations at that time we re' estensibly limited to new defects e . and no t ' o ld de fe c ts .
It should be clear that the validity of any such claim is confined to whether
]
the licensee, during the November 20-29 period, construed the five tubes as having i old defects and does not reach the issue of whether those defec ts are, in fac t , I old; 90017181
Mr. Harold R. Denton January 8, 1980 Page 5 In this regard, the licensee's November 23 letter clearly contemplated the five tubes in que stion, ai that time, to be examples of recent crevice corrosion.
(See: Id . , at Enclosure 1, Viewgraph 1.) This is made unmistakably clear in the licensee's Decenter 21 letter which concedes:
"We had included them (i.e. the five tubes) in the ' crevice cor ro sion '
column of Viewgraph 1, in our November 23 letter based upon preliminary information regarding the number of tubes containing defects and, as we have since de termined, this was in error.
n e a *
"The inclusion of these [five] tubes in the ' crevice corrosion' column of Viewgraph 1, attached to our November 2 3 letter, is now, in light of this comparison, incorrect . " (See: Licensee 's December 21, 1979, letter, at 3 and 4, emphasis added.)
That is to say, the licensee's own statements conclusively demonstrate that when it stated in November 20-28, 1979 that all defects were in the crevice, it had no ba si s , a t that time, for believing them to be old defects.
(2) Purported Limitation of Prior Represenations to Intergranular Attack The licensee's statement in its December 21 letter also attempts to purport that its November 20-28 statements alleging that corrosion was confined to the tubesheet was specifically limited to corrosion from intergranular corrosion and, thus other kinds of corrosion were properly omitted.
Even if this kind of dichotomy between kinds of corrosion were true(and the preceeding section shows that it is no t) , it is simply fallacious to contend that the licensee's November 20-28 representations were stated to be narrowly defined to just IGA.
As is cited above, the licensee's oral statement at the November 20, 1979, meeting used the generic term "de fects" and " problems" and was not specifically limited to the te rm " IGA" . And the licensese's written submission of November 23 memorializing its oral presentation uses the term " tube degradation problem" and also was not limited to " IGA" . The licensee's selective excerpts from its November 23 letter in its most recent missive are just that--selective excerpts which omit the incriminating passages .
( B) ADEQUACY OF HYPOTHESIS THAT FWE "UBES HAVE OLD CEFECTS The licensee's Oecember 21 letter supports its hypothesis that the defects in the five tubes in question occurred prior to 1975 by stating that the single frequency eddy current test " signals have not changed thrcugh three of four annual inspections since 1975." (See: Id., at 4.)
Yet according to the Staf f 's consultant on ICT, in a telephone conversation with us, single frequency ICT cannot detect any defects in the region between one-half inch above and below the top surface of the tubesheet. Ihus, it would appear that the single frequency ECT ever the past four years for the five
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Mr. Harold R. Denton
. Jan ua ry . 8, 1980; ,
- Page 6 tubes recently observed to have defects within one-half inch of the tubesheet ;
.has no indicative ~ value whatsoever. 1/ :
Ap'p arently also. in cupport of its hypothesis, the December 21 letter refers !
to the f a:t that the partial multi-frequency ECT examination during the December 11,1979_ outage did not identify any further degradation above the tubesheet, implying that significance can be drawn from this fact. (See: Id., at 4.)
Such an implication is wholly improbable and unwarrented unless there are
. other independent facts to support it. On December 11, the plant had only been operating at less than 30% of full power and at reduced temperatures for less than eleven days since the prior multi-frequency ECT. The . f act th at any significant degradation occurred, which it did in approximately thirty-four tubes , in that exceedingly short space of time is extrerely disturbing. That the thirty-four tubes r
which degraded in less than eleven days did not happen to degrade above the tube-sheet has no signficance.
The 'f act remains that the licensee is asking us to believe that degradation, some of which is - greater than 80% through the wall, remained completely latent without any further corrosion for four or more years. This is highly improbable, to say the least. It is our understanding that the only observed instance of latency has been in f acilities which made a clean changeover following shutdown from phosphate to AVT secondary water treatment with thorough sludge lancing.
At ' Point Beach 1, this was not done (see t . Safety Evaluation Report, og. c it . , at 4: Transcript, eg. cit., at 90), and the amount of phosphate hideout in the sludge pile has been extremely large, apparently the result of excessive slugging of phosphates during the first years of operation to combat condensor in-leakage (see s Office of Inspection and Enforcement, IE In quiry Re port No . 050-266/75-01, dated March 14, 1975, at 2; Licensee 's November 23, 1979 letter, at Enclosure ES-1) .
For the foregoing reasons, it is clear that the licensee deliberately misrepresented the f acts to the Staff and the Commission in a most critical particular during the period November 20-28, 1979, and that there exists no reliable basis, at the present time, for concluding that the identified defects outside the crevice are of pre-1975 origin or will not be repeated.
S incerely, WISCONSIN'S ENVIPONFENTAL DECADE, INC.
Y
-fC~4s U n '7h. f &
KATELEEN M. FALK General Co un sel ec Commissioners
. Gerald Charnoff, Esq.
1/ ..This is as distinguished from multi-frequency ECT which has enhanced
, capability to detect defects in the boundary area at the top of the tubesheet. ,
Multi-frequency ECT was _ first performed at Point Beach in Oc tober 1979. L h