ML20062F282
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| ML20062F282 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 08/10/1982 |
| From: | Bachmann R NRC OFFICE OF THE EXECUTIVE LEGAL DIRECTOR (OELD) |
| To: | Bloch P, Kline J, Paxton H Atomic Safety and Licensing Board Panel |
| References | |
| NUDOCS 8208120009 | |
| Download: ML20062F282 (2) | |
Similar Documents at Point Beach | |
|---|---|
Category:CORRESPONDENCE-LETTERS
MONTHYEARNPL-99-0564, Forwards Response to NRC Request During 990720 Meeting,To Provide Addl Details to Several Questions Re Amend Currently Under Review by Staff Pertaining to CR Habitability1999-10-19019 October 1999
[Table view]Forwards Response to NRC Request During 990720 Meeting,To Provide Addl Details to Several Questions Re Amend Currently Under Review by Staff Pertaining to CR Habitability ML20217A5911999-09-30030 September 1999 Advises of NRC Plans for Future Insp Activities at Facility for Licensee to Have Opportunity to Prepare for Insps & to Provide NRC with Feedback on Any Planned Insps Which May Conflict with Plant Activities.Plant Issues Matrix Encl 05000266/LER-1999-007, Forwards LER 99-007-00 for Point Beach Nuclear Plant,Unit 1. Condition Would Be Outside App R Design Basis for Plant.New Commitments within Rept Indicated in Italics1999-09-30030 September 1999 Forwards LER 99-007-00 for Point Beach Nuclear Plant,Unit 1. 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 Category:INTERNAL OR EXTERNAL MEMORANDUM MONTHYEARML20212F5461999-09-23023 September 1999
[Table view]Notification of 991004 Meeting with Utils in Rockville,Md to Update Status of Nuclear Mgt Company & Provide Details of Member Licensees Impending License Transfer Applications & Operating Agreement ML20211C7301999-08-20020 August 1999 Notification of 990901 Meeting with Util in Rockville,Md to Discuss Licensee Planned Application for Conversion of Current TS to Improved Standard TS Prior to Submittal ML20207H6571999-07-12012 July 1999 Notification of 990722 Meeting with Util in Rockville,Md to Discuss Ongoing Improvement Initiatives,Status of Formation of Nuclear Mgt Company & Control Room Habitability & Potassium Iodide Issue ML20210A7751999-07-12012 July 1999 Canceled Notification of 990722 Meeting with Wepco in Rockville,Maryland to Discuss Stated Topics Re Point Beach NPP ML20196L1461999-07-0707 July 1999 Notification of 990720 Meeting with Wisconsin Electric Power Co in Rockville,Md to Discuss Control Room Habitability at Plant ML20212J1211999-06-20020 June 1999 Discusses Closeout of GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity, for Plant,Units 1 & 2 ML20205L0961999-04-0909 April 1999 Notification of 990426 Meeting with Util to Discuss Licensee Plans to Submit Improved Standard TS for Plant,Units 1 & 2 ML20154R3691998-10-19019 October 1998 Notification of 981029 Meeting with Listed Utils in Rockville,Md to Discuss Proposed Consortium of Utils ML20236N5891998-05-12012 May 1998 Provides Summary of VSC-24 Status.Informs That NRC Weld Team Completed Insp of UT Process That Will Be Used to Insp Both Currently Loaded Casks & Casks That Will Be Loaded in Future ML20216C0551998-05-0808 May 1998 Summarizes 980508 Telcon on 980508 Between T Malanowski & B Sasman of Wepc & L Gundrum & P Patnaik,Nrr Re Status of Evaluation & Resolution of Outliners for GL-87-02 & USI A-46.Forwards Summary of Status for A-46 Outliners ML20217Q7151998-05-0101 May 1998 Notification of 980604 Meeting W/Util in Rockville,Md to Discuss Util TS Change Request 204 Re Control Room Habitability for Plant,Units 1 & 2 ML20236N5271998-04-23023 April 1998 Advises That a Howe Informed That Time-of-Flight Improvement Over P-scan & That Insp Going Well.Team Still Needs to Come to Closure of Some Issues Re Sizing of Flaws ML20236K9301998-03-26026 March 1998 Forwards Status on VSC-24 Weld Issues for Info Purposes. Future Events & Dates Subject to Change.Provides Outline of Internal Plan to Complete CAL Items.Requests Maintaining Guide as Internal Planning Guide ML20236M1921998-02-23023 February 1998 Informs That VSC-24 Owners Group Wants to Postpone Insp of UT Exam Procedure for VSC-24 Closure Welds by 2 Weeks to Week of 980316 Due to Unsuccessful Paint Job on mock-up ML20211D6721997-09-15015 September 1997 Provides NRR Concurrence to Remove Big Rock Point from SALP Program,To Extend Current Point Beach SALP Cycle from 15 to 19 Months & to Extend Current LaSalle County Station SALP Cycle to Approx Six Months Following Restart of Either Unit ML20211D7411997-08-26026 August 1997 Informs of Intent to Extend Current Point Beach SALP Cycle from 15 Months to 19 Months ML20149L1801997-07-25025 July 1997 Notification of 970805 Meeting W/Wisconsin Electric Power Co & Westinghouse Electric Corp in Rockville,Md to Discuss Design of New Reactor Fuel ML20137Y8721997-04-18018 April 1997 Forwards List of Discussion Items for Plant to Review in Preparation for 970428 Meeting ML20137X1511997-04-17017 April 1997 Notification of 970428 Meeting W/Wepco in Rockville,Md to Discuss Dose Assessment Analysis Performed in Support of Current License Amend Requests for Pbnp ML20147F5461997-03-24024 March 1997 Submits Steam Generator Tube Insp Results for Facility ML20138Q5391997-03-0404 March 1997 Forwards Documents from 970131,mgt Meeting Between Plant & NRC to Be Sent to PDR ML20134K7501997-02-12012 February 1997 Notification of 970224 Meeting W/Util in Rockville,Md to Discuss Equipment Qualification Based on Recently Revised Containment Analysis ML20138J7671997-02-0505 February 1997 Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licenseing Exam on 970409. Ltr W/Copy to Chief,Operator Licensing Branch Must Be Submitted to Listed Address in Order to Register Personnel ML20147C4881997-01-30030 January 1997 Forwards Four Documents Given to Region III Staff at Meeting on 970124 W/Plant Mgt to Be Placed in PDR ML20129B3411996-08-0505 August 1996 Discusses Review to Estimate Production of Hydrogen by Radiolysis in Sf Storage Cask,Concluding That Radiolysis Not Significant Contributor to Hydrogen Gas Production at Point Beach & Not Expected to Be Source for Other Sf Storage Sys ML20059G7481994-01-11011 January 1994 Notification of 940131 Meeting W/Util in Rockville,Md to Discuss Wepco Upcoming Insp of Control Rod Drive Vessel Penetrations ML20059B1831993-10-25025 October 1993 Notification of 931103 Meeting W/Util in Rockville,Md to Discuss Diesel Generator Installation Project ML20057F1691993-10-0808 October 1993 Notification of 931008 Meeting W/Util in Rockville,Md to Discuss TS Amend Request Re Reactor Coolant Sys Flow ML20059B3261993-09-14014 September 1993 Forwards Llnl 1993 Probabilistic Seismic Hazard Estimates for Plant,Per Util 930908 Request ML20056F3431993-08-10010 August 1993 Provides Summary of Plant IPE Submitted on 930630,per GL 88-20, Individual Plant Exam for Severe Accident Vulnerabilities ML20056E9361993-08-0909 August 1993 Discusses Safety Significance of Corrective Actions Taken by Licensee in Response to IE Bulletin 86-003 ML20125B6091992-12-0303 December 1992 Requests Review of Due Date.Request for Revised Due Date Must Have Prior Approval from Appropriate Associate Director or NRR Deputy Director & Must Include Valid Justification ML20128A1971992-12-0101 December 1992 Advises of Closeout of TACs M71758 & M71759, Point Beach 1 & 2 - Reactor Vessel Upper Shelf Energy, Per GL 88-11 & Rev 2 to Reg Guide 1.99, Radiation of Reactor Vessel Matls ML20059A5511990-08-17017 August 1990 Notification of 900905 Meeting W/Util in Rockville,Md to Discuss Util Plans for Installation of Addl Emergency Diesel Generators & Extra Station Batteries ML20059B3281990-07-19019 July 1990 Discusses Author Observation of INPO Evaluation Process at Clinton Nuclear Power Plant on 900514-25.Recommends That NRC Observe Addl INPO Evaluations.Description of INPO Process & List of Qualifications & Experience of INPO Members Encl ML20248C7551989-08-0303 August 1989 Notification of 890810 Meeting W/Util in Rockville,Md to Discuss Plant Reactor Vessel Integrity ML20206J4561988-11-22022 November 1988 Notification of 881201 Meeting W/Util in Rockville,Md to Discuss Containment Liner Leak Chase Channel Venting ML20151H8881988-04-12012 April 1988 Requests That Div of Reactor Safety Take Lead in Regional Followup Re Problem at Plant & Potential Generic Implications ML20151A2271988-03-28028 March 1988 Forwards Info Package Re Backround Info for Commissioner Carr 880404 & 05 Visits to Kewaunee & Point Beach Sites, Respectively ML20155K2001988-03-0909 March 1988 Discusses Topics for Senior Mgt Meeting & Submits Partial Listing of Facilities Where Vendor Support Has Been Problem,Vendor Involved & Component/Issue of Interest. W/Copyrighted Matl IA-88-165, Discusses Topics for Senior Mgt Meeting & Submits Partial Listing of Facilities Where Vendor Support Has Been Problem,Vendor Involved & Component/Issue of Interest. W/Copyrighted Matl1988-03-0909 March 1988 Discusses Topics for Senior Mgt Meeting & Submits Partial Listing of Facilities Where Vendor Support Has Been Problem,Vendor Involved & Component/Issue of Interest. W/Copyrighted Matl ML20154H0451988-03-0202 March 1988 Notification of 880331 Meeting W/Numarc in Rockville,Md to Discuss Differences Between Sandia & NUMARC Analyses of DHR at Plant ML20147C7031988-03-0101 March 1988 Forwards Corrected Summary Rept on Multi-Plant Action D-05 Re Upper Plenium Injection,Recommendation Concerning Generic Priority & Items for Senior Mgt Attention ML20149G7871988-02-11011 February 1988 Forwards Proprietary WCAP-11666 Re Evaluation for Vibration Induced Fatigue of Steam Generator Tubes.Licensee Committed to Enhanced Primary to Secondary Leakage Reduction Program, Per Util & NRC 871125 Approval.Rept Withheld ML20237D8041987-12-17017 December 1987 Discusses Steam Generator Temp/Pressure Limitations Based on Info from Plant Resident Inspectors.Plant Tech Specs Do Not Adequately Address Max Permissable Pressure for Corresponding Temp ML20237B2681987-12-11011 December 1987 Requests That Encl 10CFR50.App I Evaluations,For Listed Facilities Not Already Covered by Repts in Dcs,Be Entered Into DCS Sys on Microfiche ML20236S3591987-11-16016 November 1987 Forwards Licensee Responses to 10CFR21 Notification Re Potential Violation of Component Cooling Water Containment Isolation Function,Per 871106 Request ML20236P7451987-11-13013 November 1987 Reviews Latest Performance Indicators to Determine Whether Indicators Can Be Used to Ascertain Quality Performance.Five of Six Plants Achieving Very Good Quality Performance While One Plant Achieving Good Quality Performance ML20236F0781987-10-28028 October 1987 Forwards NRR Input for SALP Board Meeting Scheduled for 871123 Re Plant ML20236A5401987-10-15015 October 1987 Forwards Draft NRR SALP Input Covering Licensing Activities for Apr 1986 - Sept 1987.Performance Rating of Category 2 Assigned.Comments Received by 871023 Will Be Considered for Incoporation in Final Repts 1999-09-23 Category:MEMORANDUMS-CORRESPONDENCE MONTHYEARML20212F5461999-09-23023 September 1999
[Table view]Notification of 991004 Meeting with Utils in Rockville,Md to Update Status of Nuclear Mgt Company & Provide Details of Member Licensees Impending License Transfer Applications & Operating Agreement ML20211C7301999-08-20020 August 1999 Notification of 990901 Meeting with Util in Rockville,Md to Discuss Licensee Planned Application for Conversion of Current TS to Improved Standard TS Prior to Submittal ML20210A7751999-07-12012 July 1999 Canceled Notification of 990722 Meeting with Wepco in Rockville,Maryland to Discuss Stated Topics Re Point Beach NPP ML20207H6571999-07-12012 July 1999 Notification of 990722 Meeting with Util in Rockville,Md to Discuss Ongoing Improvement Initiatives,Status of Formation of Nuclear Mgt Company & Control Room Habitability & Potassium Iodide Issue ML20196L1461999-07-0707 July 1999 Notification of 990720 Meeting with Wisconsin Electric Power Co in Rockville,Md to Discuss Control Room Habitability at Plant ML20212J1211999-06-20020 June 1999 Discusses Closeout of GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity, for Plant,Units 1 & 2 ML20205L0961999-04-0909 April 1999 Notification of 990426 Meeting with Util to Discuss Licensee Plans to Submit Improved Standard TS for Plant,Units 1 & 2 ML20154R3691998-10-19019 October 1998 Notification of 981029 Meeting with Listed Utils in Rockville,Md to Discuss Proposed Consortium of Utils ML20236N5891998-05-12012 May 1998 Provides Summary of VSC-24 Status.Informs That NRC Weld Team Completed Insp of UT Process That Will Be Used to Insp Both Currently Loaded Casks & Casks That Will Be Loaded in Future ML20216C0551998-05-0808 May 1998 Summarizes 980508 Telcon on 980508 Between T Malanowski & B Sasman of Wepc & L Gundrum & P Patnaik,Nrr Re Status of Evaluation & Resolution of Outliners for GL-87-02 & USI A-46.Forwards Summary of Status for A-46 Outliners ML20217Q7151998-05-0101 May 1998 Notification of 980604 Meeting W/Util in Rockville,Md to Discuss Util TS Change Request 204 Re Control Room Habitability for Plant,Units 1 & 2 ML20236N5271998-04-23023 April 1998 Advises That a Howe Informed That Time-of-Flight Improvement Over P-scan & That Insp Going Well.Team Still Needs to Come to Closure of Some Issues Re Sizing of Flaws ML20236K9301998-03-26026 March 1998 Forwards Status on VSC-24 Weld Issues for Info Purposes. Future Events & Dates Subject to Change.Provides Outline of Internal Plan to Complete CAL Items.Requests Maintaining Guide as Internal Planning Guide ML20236M1921998-02-23023 February 1998 Informs That VSC-24 Owners Group Wants to Postpone Insp of UT Exam Procedure for VSC-24 Closure Welds by 2 Weeks to Week of 980316 Due to Unsuccessful Paint Job on mock-up ML20211D6721997-09-15015 September 1997 Provides NRR Concurrence to Remove Big Rock Point from SALP Program,To Extend Current Point Beach SALP Cycle from 15 to 19 Months & to Extend Current LaSalle County Station SALP Cycle to Approx Six Months Following Restart of Either Unit ML20211D7411997-08-26026 August 1997 Informs of Intent to Extend Current Point Beach SALP Cycle from 15 Months to 19 Months ML20149L1801997-07-25025 July 1997 Notification of 970805 Meeting W/Wisconsin Electric Power Co & Westinghouse Electric Corp in Rockville,Md to Discuss Design of New Reactor Fuel ML20137Y8721997-04-18018 April 1997 Forwards List of Discussion Items for Plant to Review in Preparation for 970428 Meeting ML20137X1511997-04-17017 April 1997 Notification of 970428 Meeting W/Wepco in Rockville,Md to Discuss Dose Assessment Analysis Performed in Support of Current License Amend Requests for Pbnp ML20147F5461997-03-24024 March 1997 Submits Steam Generator Tube Insp Results for Facility ML20138Q5391997-03-0404 March 1997 Forwards Documents from 970131,mgt Meeting Between Plant & NRC to Be Sent to PDR ML20134K7501997-02-12012 February 1997 Notification of 970224 Meeting W/Util in Rockville,Md to Discuss Equipment Qualification Based on Recently Revised Containment Analysis ML20138J7671997-02-0505 February 1997 Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licenseing Exam on 970409. Ltr W/Copy to Chief,Operator Licensing Branch Must Be Submitted to Listed Address in Order to Register Personnel ML20147C4881997-01-30030 January 1997 Forwards Four Documents Given to Region III Staff at Meeting on 970124 W/Plant Mgt to Be Placed in PDR ML20129B3411996-08-0505 August 1996 Discusses Review to Estimate Production of Hydrogen by Radiolysis in Sf Storage Cask,Concluding That Radiolysis Not Significant Contributor to Hydrogen Gas Production at Point Beach & Not Expected to Be Source for Other Sf Storage Sys ML20059G7481994-01-11011 January 1994 Notification of 940131 Meeting W/Util in Rockville,Md to Discuss Wepco Upcoming Insp of Control Rod Drive Vessel Penetrations ML20059B1831993-10-25025 October 1993 Notification of 931103 Meeting W/Util in Rockville,Md to Discuss Diesel Generator Installation Project ML20057F1691993-10-0808 October 1993 Notification of 931008 Meeting W/Util in Rockville,Md to Discuss TS Amend Request Re Reactor Coolant Sys Flow ML20059B3261993-09-14014 September 1993 Forwards Llnl 1993 Probabilistic Seismic Hazard Estimates for Plant,Per Util 930908 Request ML20056F3431993-08-10010 August 1993 Provides Summary of Plant IPE Submitted on 930630,per GL 88-20, Individual Plant Exam for Severe Accident Vulnerabilities ML20056E9361993-08-0909 August 1993 Discusses Safety Significance of Corrective Actions Taken by Licensee in Response to IE Bulletin 86-003 ML20125B6091992-12-0303 December 1992 Requests Review of Due Date.Request for Revised Due Date Must Have Prior Approval from Appropriate Associate Director or NRR Deputy Director & Must Include Valid Justification ML20128A1971992-12-0101 December 1992 Advises of Closeout of TACs M71758 & M71759, Point Beach 1 & 2 - Reactor Vessel Upper Shelf Energy, Per GL 88-11 & Rev 2 to Reg Guide 1.99, Radiation of Reactor Vessel Matls ML20059A5511990-08-17017 August 1990 Notification of 900905 Meeting W/Util in Rockville,Md to Discuss Util Plans for Installation of Addl Emergency Diesel Generators & Extra Station Batteries ML20059B3281990-07-19019 July 1990 Discusses Author Observation of INPO Evaluation Process at Clinton Nuclear Power Plant on 900514-25.Recommends That NRC Observe Addl INPO Evaluations.Description of INPO Process & List of Qualifications & Experience of INPO Members Encl ML20248C7551989-08-0303 August 1989 Notification of 890810 Meeting W/Util in Rockville,Md to Discuss Plant Reactor Vessel Integrity ML20206J4561988-11-22022 November 1988 Notification of 881201 Meeting W/Util in Rockville,Md to Discuss Containment Liner Leak Chase Channel Venting ML20151H8881988-04-12012 April 1988 Requests That Div of Reactor Safety Take Lead in Regional Followup Re Problem at Plant & Potential Generic Implications ML20151A2271988-03-28028 March 1988 Forwards Info Package Re Backround Info for Commissioner Carr 880404 & 05 Visits to Kewaunee & Point Beach Sites, Respectively ML20155K2001988-03-0909 March 1988 Discusses Topics for Senior Mgt Meeting & Submits Partial Listing of Facilities Where Vendor Support Has Been Problem,Vendor Involved & Component/Issue of Interest. W/Copyrighted Matl IA-88-165, Discusses Topics for Senior Mgt Meeting & Submits Partial Listing of Facilities Where Vendor Support Has Been Problem,Vendor Involved & Component/Issue of Interest. W/Copyrighted Matl1988-03-0909 March 1988 Discusses Topics for Senior Mgt Meeting & Submits Partial Listing of Facilities Where Vendor Support Has Been Problem,Vendor Involved & Component/Issue of Interest. W/Copyrighted Matl ML20154H0451988-03-0202 March 1988 Notification of 880331 Meeting W/Numarc in Rockville,Md to Discuss Differences Between Sandia & NUMARC Analyses of DHR at Plant ML20147C7031988-03-0101 March 1988 Forwards Corrected Summary Rept on Multi-Plant Action D-05 Re Upper Plenium Injection,Recommendation Concerning Generic Priority & Items for Senior Mgt Attention ML20149G7871988-02-11011 February 1988 Forwards Proprietary WCAP-11666 Re Evaluation for Vibration Induced Fatigue of Steam Generator Tubes.Licensee Committed to Enhanced Primary to Secondary Leakage Reduction Program, Per Util & NRC 871125 Approval.Rept Withheld ML20237D8041987-12-17017 December 1987 Discusses Steam Generator Temp/Pressure Limitations Based on Info from Plant Resident Inspectors.Plant Tech Specs Do Not Adequately Address Max Permissable Pressure for Corresponding Temp ML20237B2681987-12-11011 December 1987 Requests That Encl 10CFR50.App I Evaluations,For Listed Facilities Not Already Covered by Repts in Dcs,Be Entered Into DCS Sys on Microfiche ML20236S3591987-11-16016 November 1987 Forwards Licensee Responses to 10CFR21 Notification Re Potential Violation of Component Cooling Water Containment Isolation Function,Per 871106 Request ML20236P7451987-11-13013 November 1987 Reviews Latest Performance Indicators to Determine Whether Indicators Can Be Used to Ascertain Quality Performance.Five of Six Plants Achieving Very Good Quality Performance While One Plant Achieving Good Quality Performance ML20236F0781987-10-28028 October 1987 Forwards NRR Input for SALP Board Meeting Scheduled for 871123 Re Plant ML20236A5401987-10-15015 October 1987 Forwards Draft NRR SALP Input Covering Licensing Activities for Apr 1986 - Sept 1987.Performance Rating of Category 2 Assigned.Comments Received by 871023 Will Be Considered for Incoporation in Final Repts 1999-09-23 Category:NRC TO ASLP MONTHYEARML20062F2821982-08-10010 August 1982
[Table view]Forwards Pg Easley Affidavit of Preparation of Response to Wi Environ Decade Interrogatory 2.Affiant Not Available to Sign Affidavit in Time to Meet 820806 Filing Deadline ML20055C0041982-08-0606 August 1982 Advises That NRC Will Not Respond to Licensee 820722 Motion to Conduct Discovery of Wi Environ Decade Re Decade Contacts W/Sleeving Demonstration Program Workers ML20058F5811982-06-30030 June 1982 Forwards Eia Supporting Steam Generator Tube Sleeving Repair Program.Safety Evaluation Will Be Issued in About 10 Days 1982-08-06 |
Text
. _ _. _ _ -._ _. _ . - _ _ _ _ _ _ . __ ._. . .
, ! DESIGNATED ORIGINAL
) ,
A@rtified By_ _ _
l .
p August 10, 1982 i
l Peter R. Bloch, Chairman Dr. Jerry R. Kline Administrative Judge Administrative Judge Atomic Safety and Licensing Board Atomic Safety and Licensing Board U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission Washington, DC 20555 Washington, DC 20555 Dr. Hugh C. Paxton 3
Administrative Judge
~
1229 41st Street Los Alamos, NM 87544 i
1 In the Matter of J
Wisconsin Electric Power Company (Point Beach Nuclear Plant, Units 1 and 2)
- Docket No. 50-266 and 50-301 i (Repair to Steam Generator Tubes)
Dear Administrative Judges:
l
! Enclosed is the signed and notarized Affidavit of Preparation for ,
i Patrick G. Easley. Mr. Easley was not available to sign his affidavit in time to effect express mail service of the Staff's response to Decade's
- interrogatories on the filing date, August 6, 1982.
Sincerely, Richard G. Bachmann i Counsel for NRC Staff
Enclosure:
as stated cc w/ enclosure: Service List 0FC :0E :0 ELD j : : : : :
__.__: g3 - __:___ ______:_________,.__:____________:____________:____________.___________
NAME : '
)y : : : : : :
__ ___ : --__'chma nn/j h _______:____________:____________:
________:___y S AT ___________:____________.___________
DATE :08/09/82 :08F /82 : : : : :
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820812 COO 9 820810 '
PDR ADOCK 05000266 G pop
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. . v l AFFIDAVIT OF PREPARATION ao I, Patrick G. Easley, being duly sworn, state that I was responsible for preparing the foregoing response to Interrogatory No. 2. That response is true and correct to the best of my knowledge.
tr M . h. Y Patrick G. Easley LL 47 Sworn to and signed before me this (,r6dayofAugust,1982.
'N
, 'Ios,,:- /dn.W N Public My Comission expires: 7 ff .
'/
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