ML20147F546
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| ML20147F546 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 03/24/1997 |
| From: | Gundrum L NRC |
| To: | Malanowski T NRC |
| References | |
| NUDOCS 9703260178 | |
| Download: ML20147F546 (1) | |
Similar Documents at Point Beach | |
|---|---|
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 |
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i Ste6.m Generator Tube inspection Results Licensees' steam generator (SG) tube eddy current (EC) inspections play a vital role in the management of SG tube degradation. The results are used to demonstrate adequate structural and
, leakage integrity of the SG tubes.
1 NRC staff is interested in discussing the licensee's steam generator inspection plans and results, although the licensee is not required to participate in this discussion. The following list of topics i describes areas the NRC staff typically is interested in talking about, i
f Primary to secondary leakage prior to shutdown Results of secondary side hydro i For each steam generator, provide a general description of areas examined; include expansion i criteria and specify type of probe used in each area For analyzed EC results, describe bobbin indications (those not examined with RPC) and RPC/Plus Point /Cecco indications. Include the following information: location, number, degradation mode, disposition, and voltages / depths / lengths of most significant indications.
I Describe repair / plugging plans Discuss previous history: "look backs" performed Discuss new inspection findings
} Describe in-situ pressure test plans and results, if available; include tube selection criteria Describe tube pull plans and preliminary results, if available; include tube selection criteria 4
Assessment of tube integrity for previous operating cycle
. Assessment of tube integrity for next operating cycle Provide schedule for steam generator-related activities during remainder of current outage Note: You are encouraged to provide details on the topics listed above prior to the conference call (e.g., simple tables and figures) if you think it will facilitate the discussion.
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