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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
[Table view] |
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649FL / W W Wisconsin's Environmental Decade 114 North Carroll Street, Suite 208, Madison, Wisconsin 53703 (608) 251 7020 IC'EIE 230 W. Wells St., Suite 309, Milwaukee, WI 53203 (414) 272-1607 UJI*hC 324 W. Wisconsin Ave., Suite 1, Appleton,WI 54911 (414)734 5403
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- FROM: Stephen Proudman n.caud mina Wisconsin Environmental Decade, Inc.
Environmental Qualification Standards Commenter DATE: August 10, 1984 St.FF
"*$',*" e',$** RE: Comments on the suf ficiency of the Justification f or Sa >**"' Continued Operation for Wisconsin Electric Power T,M, E'n'let Company's Point Beach Nuclear Plant I & II c= tar 'ao "=* 49 Fed. Reg. 8445 (March 7, 1984)
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6 INTRODUCTION:
In the wake of the accident at TMI II, the Nuclear Regulatory Commission ordered all reactors to comply with environmental qualification standards by June 30, 1982. This ruling was incorporated into all reactor licenses to assure that safety and q uality control measures would be upgraded and rigorously maintained to prevent any f uture accidents. In 1982 the NRC changed the rules which amended the licenses of all 72 operating nuclear power plants to suspend that deadline.
In extending the compliance deadline, the NRC made a finding that each plant could be operated saf ely pending completion of environmental qualification. According to NRC records this finding was based upon utility filings called " justification f or continued operation" (J CO's ) . According to the Union of Concerned Scientists findings, most of the reactor equipment associated with cooling and emergency cooling systems did not meet environmental qualification standards. The purpose of the JCO's was to demonstrate that a plant was safe enough to operate despite the difficulties in equipment.
In a oversight of democratic principles the NRC provided no opportunity to comment on the sufficiency of the JCos. UCS sued the NRC and won a decision which ordered the NRC to provide an opportunity for public comment on this' procedure.
I am grateful to the UCS in their efforts to allow for independent review of this most critical process which directly concerns the health and welfare of the general public and surrounding ecosystems near each operating reactor.
COMMENTS:
The comments I w ill make are based on my review of the Technical Evaluation Report (TER) prepared f or the NRC by the Franklin Research Center (FRC); the Safety Evaluation Report (SER) by the NRC staff that addresses the TER; and later i qualification documents. Due to geographical limitations I was unable to trace many key documents made available to the public by the NRC in their Document Reading Room in Washington, D.C.
l The most common problem I had in my review was that some inf ormation was withheld f rom the FRC report because the licensee (in this case Wisconsin Electric Power Co.-WEPCO), claimed the inf ormation was " proprietary" in nature, which I assume means l' that the information contained trade secrets of some sort. This
~
made it difficult, if not impossible, to comment on the adequacy of the qualification review. In an industry which is at this point in time struggling to survive even under immense subsidizations from the federal government I fail to understand how the NRC can allow any utility to withhold inf ormation in a t
critical review of safety requirements. The review of each j component in question remains incomplete, in my opinion, until 2
equitable access to information is_provided.
The order and organization of the records was poor in many instances making the job of reading and following the presented logic a very difficult task. In many cases I could not even read the licensee's response to NRC evaluations thus making my commentary impossible.
I must make a comment on the scope of the TER review. The NRC asked WEPCO to submit a list of all safety related components including documentation to show that they were qualified. "SCEW sheets" were provided which contained inf ormation on the conoition for which equipment was qualified as well as the conditions to which the equipment could be exposed during an accident. According to UCS, the NRC's evaluation never questioned the licensee's assertions or examined the basis f or the assertions. They only looked at areas where equipment qualifications did not appear to meet the requirements of an accident condition. This means that WEPCO's statements in 1981 that equipment was qualified due to whatever justification were never reviewed by the NRC or FRC. The review sDly covered equipment that WEPCO identified as deficient. This is a gross assertion and makes the scope of the TER review gravely deficient at best. .
As I understand the role of the NRC, it is to regulate and license the reactors of the nuclear industry. It's role has been reevaluated af ter the seriousness of the accident at TMI II was realized through new and continued research findings by engineering experts. Unf ortunately the type of gross experiment is not an adequate learning lesson f or a technology which can have serious and undetermined (the debate continues) biological effects in forms of life.
8 At a nuclear-fuel-cycle conference held in Atlanta in April 7, 1984, NRC member Frederick Beinthal was optimistic in assertions that "the NRC in the 1990's could retreat into something like a Federal Aviation Administration f or nuclear power pl a n t s. " According to Beenthal the problem with the industry is simply stated, "the technology of nuclear power is proven, but the institutions that generate and regulate the power need fixing." I would say this may be only partly true. After i reviewing this TER I am of the opinion that if the technology
, were proven then this would not be evidence of such a large
- number of unqualified components in reactors such as the Point Beach plants. If the confidence is then f or j ustification then why is this evaluation process full of discrepencies and
- misleading inf ormation? On the human side of the industry, if the confidence exists for demonstrating sound competent management then why is the industry in such financial trouble and why does it take a lawsuit to allow the general public to become
! involved in process concerning the public's safety?
. I realize af ter completing this review that the bureaucratic entanglements are enormous, however, strenmlining the NRC's 1
3 . - _ - - - - .- . - -
licensing and regulatory roles is not an adequate answer to eliminating problems involving individual components governing the mechanics of a reactor's safety systems. This is a technical problem needing' straightf orward attention and adequate documentation for proof of suf ficiency.
The following list is an item by item description of safety-related components which were f ound to not be qualified by the FRC. For these components many justifications for continued operation were submitted af ter the TER was filed. Comments are included for each item.
lism 21: Electric Motor located in Auxiliary Building FUNCTION: Safety injection pump motor.
CATEGORY:
. Qualification for deficiency improvement not established.
.No adequate documentation of qualification.
. Aging degradation evaluated inadequately.
. Qualified life or replacement schedule not established.
COMMENT:
. Unable to read licensee response to NRC SER.
.FRC comments on licensee response:
.WCAP-8754 was cited by licensee as evidence of qualification. FRC says this is not an adequate analysis that de te rmine s an actual in plant service life for the safety injection motor pump.
lism 25: Electric Motor located in the Auxiliary Building.
FUNCTION: Containment spray pump motor CATEGORY--Qualification Not Established
. Documentation evidence of qualification inadequate.
. Inadequate agency degradation evaluation
. Qualified life or replacement schedule not established.
. Criteria regarding radiation not satisfied.
COMMENT:
In the licensee's response concerning the motor's qualifications f or perf orming under high humidity, the rational used was based on an assumption that the location of the motor is such that high humidity Js got szpssted in that part of the auxiliary building. This is not an acceptable scientific judgment.
4
21ss 26: Electric Motor located in the Auxiliary Building FUNCTION: Component Cooling Water Pump Motor CATEGORY: Qualification f or deficiency improvements not established.
.No adequate documentation of qualification.
. Aging degradation evaluated inadequately.
. Qualified life or replacement schedule not established.
. Criteria regarding radiation not satisfied.
COMMENT:
The laboratory test report of this vital component in the reactor's cooling system (s) was not used in full in the qualification process. Reasons for receiving only parts of the research report are the size of the report and the " proprietary" classification of the reports. This does not allow for a thorough review by outside reviewers, 1133 22: Electric Motor in the Auxiliary Building FUNCTION: Residual Heat Removal-Pump Motor CATEGORY: Qualification not established.
. Documentation of evidence inadequate.
. Aging degradation evaluated inadequately.
. Qualified life or replacement schedule not established.
. Program not established to identify aging degradation.
. Criteria regarding radiation not satisfied.
COMMENT:
The ref erence report WCAP-8754 includes unacceptable test date which establishes a qualified life (r' inning hours) under an assumed radiation level (temperature) for this motor.
There is no analysis, according to the PRC that determines the actual in-plant service life.
There was no maintenance schedule submitted, for the record, for the bearings / lubricant.
r 1133 28: Electric Motor in Containment FUNCTION: Containment air accident from cooler motor.
CATEGORY: Qualification not established.
. Aging degradation evaluated inadequately.
. Qualified life or replacement schedule not established.
. Criteria regarding aging simulation not satisfied.
. Criteria regarding radiation not satisfied.
5
COMMENT:
For Items 28,29,53 [Containent Emergency Fan Cooler Motor, Splices, and Bearing Lubricants] deficiences were found in a combination of eight areas of qualification. The proposed resolution by WEPCO (November 23, 1983) is for additional analysis and documentation. No other record is available to document what action was taken, therefore the component remains unqualified.
lism 22: Electrical Cable Splice in Containment.
FUNCTION: Electrical splice f or containment air accident ft.n coolers.
CATEGORY: Qualification not established.
. Documentation of evidence is inadequate.
COMMENT:
Licensee is siting a document for a similar motor (which cable splice is connected to) as the evidence for qualification. No tests were done directly involving this component.
l Most of the Licensee response is illegible, which makes commenting difficult.
, lism 3Q: Resistance Temperature Detector in Auxiliary Building.
FUNCTION: Measures RHR Suction and Discharge Line Temperature Conversion.
CATEGORY: Qualification not established.
. Aging degradation evaluated inadequately.
COMMENT:
The licensee has not satisf actorily stated that the installed model is equivalent to currently manuf actured models.
It is also not clear whether any environmental qualification tests have been done f or this item.
Itsa 31: Motor control center located in the Auxiliary Building.
l FUNCTION: 480 Volt Electrical Power distribution.
~
CATEGORY: Qualification not established.
COMMENT:
Unable to read licensee's response to the NRC's SER.
Jtem 22: Electrical Thermocouple Cable located in containment.
___ ___ ._ _________6__ _ _ _ _ _ _ _ _ ,
FUNCTION: Reactor core thermocouple cable connection.
CATEGORY: Qualification not established.
COMMENT:
Licensee states the item is not environmentally qualified even though the TMI Action Plan requires it to be. The licensee then says it intends on qualifying the item, if possible, by the environmental qualification deadline but there is no record of this action.
lism 3H: Electrical instrument cable in containment building.
FUNCTION: Conducts acoustic signal transmission.
CATEGORY: Qualification not established.
COMMENT:
The licensee has referenced a report for RSS-6 coaxial cable. However, the manuf acturer has stated that although the cable passed the test it is not suitable for the application because the signal alterations and temperature resistance capability are not adequate.
Itsm 32: Electrical Control Cable located inside and outside containment.
FUNCTION: Electrical distribution.
CATEGORY: Qualification not established.
' COMMENT:
No test report was submitted by the licensee to be reviewed by an independent reviewer. According to the FRC evaluation the licensee stated that the PORV block values which the cable supplies power to are not safety related equipment and theref ore the cable does not require qualification. However, according to NUREG 0737, Item I I .7.1 indicates that power supplies require upgrading to maintain the ability to either open or close the PORV block values. The licensee should insure that the cable is also qualified.
Itsm 12: Electrical instrument cable located inside and outside containment.
FUNCTION: Instrumentation Cable.
CATEGORY: Equipment not qualified. Adequate similarity between equipment and test specimen not established.
COMMENT:
N e i'th e r SCEW sheet nor the licensee's provide 7
I sufficient information to establish that the installed equipment is the same as the equipment tested. It is not saf e to assume that one piece of equipment which is similar to another can have test results which apply to both.
2123 5Q: Lubricant located in the Auxiliary Building - safety injection
FUNCTION: Safety injection pump motor bearing lubricant.
CATEGORY: Qualification not established.
. Documented evidence of qualification inadequate.
. Adequate sim ila r i ty between equipment and test specimen not established.
, . Aging degradation evaluated inadequately.
. Program is not established to identify aging degradation.
. Criteria regarding aging simulation not satisfied.
. Criteria rege ng peak temperature exposure not adequate.
. Criteria regar._ag radiation not satisfied.
COMMENT:
BaBed on the FRC report very little documentation exists on the lubricant, particularly it's f unction under high temperature and radiation conditions. No f urther documentation was provided.
Item 51: Lubricant located in the Auxiliary Building component cooling pump area.
FUNCTION: Component cooling water pump bearing lubricant.
CATEGORY: Equipment qualification not established.
. Documented evidence of qualification inadequate.
. Adequate sim ila r i ty between equipment and test specimen not established.
l
. Aging degradation evaluated inadequately.
. Program to identify aging degradation not established.
' . Criteria regarding aging simulation not satisfied.
. Criteria regarding peak temperature exposure inadequate.
COMMENT:
The manufacturer of the grease has never subjected their products to tests involving exposure to radiation.
ADDITIONAL COMMENTS:
Major inadequacies in all of the above-mentioned evaluation categories. There is no real documented evidence of necessary tests according to the PRC's report. How then, can another JCO approval be given?
8
lism 52: Lubricant located outside. containment.
FUNCTION: Pump and motor bearing lubricant.
CATEGORY: Equipment qualification not established. Same as for Item 50.
lism 53: Lubricant located in containment.
FUNCTION: Fan cooler motor bearing lubricant.
CATEGORY: Equipment qualification not established.
. Adequate similarity between equipment and test specimen not established.
. Qualified life or replacement schedule not established.-
. Criteria regarding peak temperatue exposure inadequate.
lism 51:- Lubricant located in containment.
FUNCTION: Valve motor operator lubricant CATEGORY: Equipment qualification not established.
. Documented evidence of qualification is inadequate.
. Adequate simila rity between equipment and test specimen not established.
. Aging degradation evaluated inadequately.
. Qualified life or replacement schedule not established.
. Program to identify aging degradation not established.
. Criteria regarding aging simulation not satisfied.
. Criteria regarding peak temperature exposure inadequate.
. Criteria regarding radiation not satisfied.
COMMENT:
Checksheets 5F through SI were withheld due to the
" proprietary" nature of information they contained. This makes the job of commenting very difficult, lism 55: Lubricant located outside containment.
FUNCTION: Pump motor bearing lubricant.
CATEGORY: Equipment qualification not established.
. Documented evidence of qualification inadequate. .
. Adequate sim ila ri ty between equipment and test
, specimen not established.
. Aging degradation evaluated inadequately.
. Program to identify aging degradation not established.
. Criteria regarding aging simulation not established.
. Criteria regarding peak temperature exposure 9
inadequate.
. Criteria regarding radiation not satisfied.
COMMENT:
Checksheets 5F thru SL were removed due to proprietary nature of their contents. This makes the task of commenting extremely difficult.
21sm 56: Lubricant located in containment.
FUNCTION: Motor operated valve and geared limit switches lubricant.
CATEGORY: Equipment qualification not established.
. Documented evidence of qualification inadequate.-
. Adequate similarity between equipment and test specimen not established.
. Aging degradation evaluated inadequately.
. Qualified life or replacement schedule not established.
. Program to identify aging degradation not established.
. Criteria regarding aging simulation not safisfied.
. Criteria regarding peak temperature exposure inadequate.
COMMENT:
Proprietary information withheld making comments difficult.
lism 61: Motorized valve actuator located in containment.
FUNCTION: Actuates pressurizes PORV block valves.
Equipment qualification not established.
CATEGORY: Documented evidence of qualification inadequate.
. Adequate similarity between equipment and test specimen not established.
. Aging degradation evaluated inadequately.
. Qualified life or replacement schedule not established.
t COMMENT:
Proprietary information withheld. Not enough information to make comments.
1 Jigm 62: Motorized valve actuator located in containment.
I FUNCTION: Actuates reactor vessel safety injection line valves.
CATEGORY: Equipment qualification not established.
. Documented evidence of qualification inadequate.
Sua
o 4
. Adequate similarity between equipment and test specimen not established.
. Aging degradation evaluated inadequately.
. Qualified life or replacement schedule not established.
COMMENT:
Proprietary information withheld. Not enough information to make comments.
lism fia: Motorized valve actuator located in containment.
FUNCTION: Actuates RHR inj ection line valves. Actuaces cold by saf ety injection line valves.
CATEGORY: Equipment qualification not established.
. Documented evidence of qualifications inadequate.
. Adequate similarity between equipment and test specimen not established.
. Aging degradation evaluated inadequately.
. Qualified life or replacement schedule not established.
COMMENT:
Proprietary inf ormation withheld making commentary incomplete.
lism 65: Motorized valve actuator located in the component cooling heat exchanges area.
FUNCTION: Actuates steam-driven auxiliary feedwater turbine steam supply line valves.
CATEGORY: Equipment qualification not established.
. Documented evidence of qualification inadequate.
. Adequate si m il a r i ty between equipment and test specimen.
. Aging degradation evaluated inadequately.
. Qualified life or replacement schedule not established.
COMMENT:
Proprietary inf ormation has been withheld. Comments cannot be made based on available information, lism 66: Motorized valve actuator located in the Auxiliary Building.
FUNCTION: Actuates component cooling water supply lines to RHR heat exchanges valves.
CATEGORY: Equipment satisfies all requirements except 11
qualified life or replacement schedule justified.
. Aging degradation evaluated inadequately.
. Qualified life or replacement schedule not established.
COMMENT:
Proprietary information withheld. Not enough information available for which to comment.
lies 24: Electric Motor located in the Auxiliary Building.
FUNCTION: Safety injection pump motor.
CATEGORY: Equipment qualification not established.
. Documented evidence of qualification inadequate.
. Adequate similarity between equipment and test specimen not established.
. Aging degradation evaluated inadequately.
. Program identifying aging degradation not established.
. Criteria regarding radiation not satisfied.
COMMENT:
According to FRC WEPCO has not provided an analysis that determines an actual inplant service lif e f rom the data provided in reterence report WCAP-8754. WEPCO has not submitted any qualification documentation that would establish a qualified lif e f or the motor to the lead splice and bearing lubrication sy stem.
ADDITIONAL COMMENTS:
There are a total of 22 other components of not qualified status in Project No. 506. They are Item Nos: 25, 26, 27, 28, 29, 30, 32, 36, 39, 42, 50-56, 61, 62, 63, 65. This reviewer did not have ample time to complete a thorough review of these components and their deficiencies.
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