|
---|
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:OUTGOING CORRESPONDENCE
MONTHYEARML20217A5911999-09-30030 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 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 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 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 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 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 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 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 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 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 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 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 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 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 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 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 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 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 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 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 IR 05000266/19990041999-04-28028 April 1999 Discusses Insp Rept 50-266/99-04 on 990105-0222 & Forwards NOV Re Failure to Ack Validity of Temp Alarm & Appreciate Significance of Low Temp Readings for Unit 1 SI Pumps Min Flow Line ML20206B8121999-04-23023 April 1999 Forwards FEMA Evaluation Rept for 981103 Emergency Preparedness Exercise at Point Beach Nuclear Power Plant. Deficiency Identified for Manitowoc County as Result of Exercise.County Corrected Deficiency Immediately ML20205S7041999-04-20020 April 1999 Forwards Insp Repts 50-266/99-05 & 50-301/99-05 on 990222-0312.One Violation Noted & Being Treated as Non-Cited Violation.Expresses Concern Re Timeliness of C/As ML20205R4651999-04-19019 April 1999 Forwards Insp Repts 50-266/99-10 & 50-301/99-10 on 990329- 0401.No Violations Noted.During Insp NRC Observation of Licensee Activities Showed Emergency Preparedness Program to Be Adequately Implemented ML20205R6081999-04-19019 April 1999 Confirms of NRC Routine Mgt 990504 Meeting in Lisle,Il to Discuss Progress in Implementation of Improvement Initiatives in Engineering Area,As Well as to Discuss Challenges Faced by Operators ML20205P0311999-04-13013 April 1999 Refers to Various Changes Received by Region III in Jan 1999 to Portions of Point Beach NPP Emergency Plan.Informs That NRC Approval Not Required Based on Determinations That Changes Do Not Decrease Effectiveness of Emergency Plan ML20205N4221999-04-12012 April 1999 Discusses 990326 Predecisional Enforcement Conference with Util Re Apparent Violation Concerning Operator Response to Low Temp Alarm for Minimum Flow Recirculation Line for Unit 1 Safety Injection Sys.Handouts Provided by Util Encl ML20205C4701999-03-26026 March 1999 Discusses Review of Various Changes to Portions of Plant Emergency Plan.Informs That Revision Was Submitted Under Provisions of 10CFR50.54(q) ML20196K8731999-03-26026 March 1999 Advises of Licensee Planned Insp Effort Resulting from Plant Ppr.Plant Issues Matrix & Insp Plan for Next 6 Months Encl ML20204E5561999-03-16016 March 1999 Forwards Insp Repts 50-266/99-07 & 50-301/99-07 on 990216-19.No Violations Noted.Three Weaknesses Re Chemistry Program Were Identified ML20204D8161999-03-12012 March 1999 Forwards Insp Rept 50-266/99-04 on 990105-0222.One Violation of NRC Requirements Occurred & Being Treated as non-cited Violation,Consistent with App C of Enforcement Policy ML20207L9191999-03-11011 March 1999 Discusses from Util Informing NRC That Bases References for TS 15.4.4 Revised to Correct References to Point Beach Nuclear Plant FSAR Related to Reactor Containment Design.Revised Bases Page 15.4.4-7 Encl ML20207L1161999-03-10010 March 1999 Forwards Insp Repts 50-266/99-02 & 50-301/99-02 on 990105- 0222 & Nov.One Violation Associated with Program for Implementing Abnormal & Eops.Other Two Violations non-cited Violations ML20207H8661999-03-0808 March 1999 Ack Receipt of ,Which Transmitted Changes to Pbnp Security Sections 1.2,1.3,2.1,2.4,6.1,B-2.0,B-3.0 & Figure T,Per 10CFR50.54(p).No NRC Approval Is Required,Since Util Determined That Changes Do Not Decrease Effectiveness ML20207D6661999-02-22022 February 1999 Forwards Assessment of Design of Restraints on Main Steam Piping & Primary Loop Auxiliary Piping Systems at Point Beach Nuclear Plant.Staff Concludes That WE Unable to Retrieve Original Analyses That May Have Been Performed ML20203F2541999-02-10010 February 1999 Informs That Beginning 990216,DE Hills Will Be Chief of Operations Branch Which Includes Operator Licensing Function ML20202H6601999-02-0101 February 1999 Discusses Evaluation of Wisconsin Electric Power Co Response to NRC GL 97-05, Steam Generator Tube Insp Techniques ML20206U2981999-02-0101 February 1999 Informs That by 980811 & 1223 Ltrs,Nrc Responded to WOG Positions Re Corrective Actions to Address Generic Aspects of part-length Control Rod Drive Mechanism Housing Issue Resulting from Leak at Prairie Island,Unit 2 on 980123 ML20202G5321999-02-0101 February 1999 Forwards Insp Repts 50-266/99-03 & 50-301/99-03 on 990111-15.No Violations Noted.Cooperation,Communication & Effectiveness of Security & Maint Staff to Ensure Equipment Effectiveness Has Been Successful ML20199H5491999-01-15015 January 1999 Forwards Insp Repts 50-266/98-21 & 50-301/98-21 on 981121- 990104 & Notice of Violation.Violation Being Cited Because of Repetitive Nature & That Violation Could Reasonably Have Been Prevented by C/A for Previous Finding ML20206R8891999-01-13013 January 1999 Forwards SER Accepting Util 981116 & 30 Proposed Revs to Nuclear Quality Assurance Program Implemented at Point Beach Nuclear Plant Units 1 & 2 ML20199D7751999-01-0808 January 1999 Documents 990105 Telcon Issuing Notice of Enforcement Discrection for Wisconsin Electric Re Point Beach,Unit 1 ML20198K6911998-12-24024 December 1998 Forwards Insp Repts 50-266/98-22 & 50-301/98-22 on 981208-10.No Violations Noted.Concludes That Licensee Carried Out Properly Addressed Findings of Maint Rule Baseline Insp ML20198J6061998-12-22022 December 1998 Discusses Plant,Units 1 & 2 Licensed Operator Staffing Requirements 1999-09-08
[Table view] |
Text
o .
l June 2, 1998 Mr. S. A. Patulski Site Vice President
' Point Beach Nuclear Plant 6610 Nuclear Road Two Rivers, WI 54241
SUBJECT:
MANAGEMENT MEETING
Dear Mr. Patuiski:
l The NRC met with you and other members of the Wisconsin Electric Power Company on
. Thursday, May 21,1998, in the NRC Region Ill Office to discuss engineering issues, the employee concems program, and security system upgrades at the Point Beach Nuclear Plant.
The enclosure to this letter contains the handout provided to the NRC by Wisconsin Electric during the meeting.
In accordance with 10 CFR 2.790 of the NRC's " Rules of Practice," a copy of this letter and its enclosure will be placed in NRC's Public Document Room.
. Sincerely,
/s/J. W. McCormick-Barger J. W. McCormick-Barger, Chief Reactor Projects Branch 7 Docket Nos.: 50-266; 50-301 Licenses Nos.: DPR-24; DPR-27
Enclosure:
Meeting Handout See Attached Distribution l
/
t80059 DOCUMENT NAME: G:\poin\poiO5218. sum To esceive a copy of this document. Ind6cete in the hos "C" = Copy without attachment / enclosure 'E" m Copy with attachment / enclosure
- N" = No copy OFFICE Rlil 6 Rlli . (A Rlll Rlli NAME Kunowski:dppAK JMcB %h DATE 06/2/98 06/J98 OFFICIAL RECORD COPY f" .d
.9906090158 990602 s t /
POR- ADOCK 05000266 9 //
i L
l.-
j*
S. Patuiski . 1 l
cc w/ encl:. R. R. Grigg, President and Chief Operating Officer, WEPCO M. B. Sellman, Chief Nuclear Officer M. Reddeman, Plant Manager J. H. O'Neill, Jr.
Shaw, Pittman Potts & Trowbridge K. Duveneck, Town Chairman
- Town of Two Creeks B. D. Burks, P.E., Director l Bureau of Field Operations l Cheryl L. Parrino, Chairman Wisconsin Public Service Commission S. Jenkins, Electric Division Wisconsin Public Service Commission State Liaison Officer Distribution:
Project Mgr., NRR w/enci C. Paperiello, Rlli w/ enc!
J. Caldwell, Rlil w/ encl B. Clayton, Rlll w/ encl SRI Point Beach w/ encl DRP, Rill w/enci TSS, Rill w/enct DRS (2), Rlli w/ encl Rill PRR w/enci PUBLIC IE-01 w/enci Docket File, Rill w/enci GREENS
WISCONSIN ELECTRIC /NRC REGION lll lHANAGEl/IENT I/IEETING MAY 21,1998 LISLE, IL AGENDA l
Introduction Mike Seliman Plant Status Update Mark Reddemann Engineering Issues Carol Peterson Jim Schweitzer Service Water System Issues l
& Model Marlin Conry i Employee Concerns Program Al Capristo Commitment Management Scott Patuiski Security System Upgrades Mark Findlay Closing Remarks Mike Sellman l' o l u t In c a c h N u c l e a r I' l a n t I
PLANT STATUS UPDATE MARK REDDEI/IANN 1
Unit 2 e Removed from Service on March 5,1998 following discovery of CCWsystem design /iicensing basis concern.
. Returned to service on March 29,1998.
Unit 4_
e Removed from service on February 13,1998 for refueling and maintenance outage.
- Scheduled to return to service in mid-June.
2
e 4
- PLANT STATUS UPDATE L MARK REDDEMANN
- Unit 1 Outage Scope (continued) 75 modifications installed
. Support modifications i
. GL 96-06 modifications
- Modifications to return operable but degraded /non-conforming equipment to full operability Electrical system enhancements I
Appendix R modifications NRC commitments Reliability improvement modifications 1
3
g 4 ENGINEERING ISSUES CAROL PETERSON
- Challenges in Engineering Move NES from Milwaukee to Site Address engineering process and implementation weaknesses identified through self-assessments
- Continue efforts to upgrade material condition of plant Establish capable and qualified engineering organization
- New Engineering Director effective June 1,1998 1
- New alliance relationship with Duke Engineering & Services 4-
ENGINEERING ISSUES CAROL PETERSON
- Martin /Sigmon Assisted Self-Assessment Performed in 1Q98 l
Purpose was to gain clear understanding of readiness for the transition Assessment concluded that successful transition was challenged by four factors Lack of clear, integrated transition plan
. Heavy reliance on staff experience / expertise (many are leaving) without weII-defined processes, weII documented program content
. Large backlog of engineering work, program upgrades, modifications, NRC commitments
. No integrated, resource-loaded engineering work management system 5
I ENGINEERING ISSUES CAROL PETERSON
- Martin /Sigmon Recommendations
- Develop / implement detailed transition plan
- Shift stGYn problem-solving / production to prioritization/ planning orientation Develop and enforce standards and expectations for documentation, process and procedure adherence
- Inventory work backlogs, assign priorities, resource-load - tie to commitment management
- Develop / implement integrated work management process Strengthen procedureshvork processes 1 (particularly design change process) - move to the site provides advantages in this area Improve documentation and document retrieval sysiems 6
_______-____=_-____
ENGINEERING ISSUES CAROL PETERSON
- Site design engineering team formation began March 1 Transition Plan issued April 2,1998
. Living Plan
. Top level and detailed subplans
- Alliance with Duke Engineering to address challenges identified in the self-assessment New site-based organization defined with 1 clear roles and responsibilities
. Management level by June 12,1998
. Organization by June 30,1998
. Mobilized on site by July 13,1998 7
ENGINEERING ISSUES CAROL PETERSON
- NES Transition Status (continued)
Currently completing prioritizing and resource loading NES work backlogs NES continues to provide high quality support to plant, both day-to-day and project support
- Instituting process for periodic review of NES backlog (issues requiring CRs, issues requiring expedited actions by GL 91-18)
Establishing Engineering Assurance Group
- objectives and process under development Process improvement initiatives -
modification, drawing, calculation control
- due to complete in December 1998 8
REACTOR ENGINEERING PERFORMANCE IMPROVEMENT JIM SCHWEITZER
- The need was identified by
- Condition Report trend QA audit
- Routine residentinspector report 9
)
REACTOR ENGINEERING PERFORMANCE IMPRO'/EMENT \
JIM SCHWEITZER e Actions Com$eted Shifted work and focus
- Reviewed and reprioritized individual workload
- Developed improvement plan )
- Reviewed Condition Reports, audits, inspection reports, and the improvement plan with the group i
Discussed concerns with the Resident Inspector (
Performed a self-assessment of Reactor Engineering i
10 r . ..._ . _ , . _ _ _ _ . . . . . . _
REACTOR ENGINEERING PERFORMANCE IMPROVEMENT JIM SCHWEITZER i
e Self-Assessment Results - Findings
- Weakness identified in the area of fully communicating with Operations and plant management issues associated with reactivity management and providing leadership to Operations.
- Important parameters affecting core performance, core power monitoring and reactivity control are routinely reviewed but are not being graphically trended to detect deviations from normal
- Roles, responsibilities and work assignments for RE emphasize systems rather than reactor core performance and reactivity management Weaknesses in the interface between RE and corporate fuels group has the potential to adversely impact the core design and reload analysis process 11
r . ". '.
REACTOR ENGINEERING PERFORMANCE IMPRO'/EMENT JIM SCHWEITZER
- Self-Assessment Results -
Observations
- Corrective action addressing REI .0, " Power Level Determinations, " are adequate but were not timely
- Failed Fuel Action Plan action level entry criteria is adequate but is not consistent with the industry
. Self-Assessment Results -
Strengths
- Reactor Engineering personnel participate in external training programs with the support of group managers and supervisors
- A Reactor Engineering point of contact is continuously available through the duty & caII RE program i
12
l
~ '
REACTOR ENGINEERING PERFORMANCE IMPRO'/EMENT JIM SCHWEITZER ,
Complete a human performance Root Cause i Evaluation of the problems with the estimated critical position calculation associated with non-refueling outage startups. Technical aspects are understood and are being addressed
- Revise administrative procedures to clarify the relationship / responsibilities between RE and Operations Review-and plan an upgrade to RE procedures
- Convert applicable REls (Reactor Engineering Instructions) to Operations procedures and Vice Versa Design and implement an expanded fuel cycles group l
I 13 i
(
SERVICE \//ATER SYSTEM ISSUES & MODEL MARLIN CONRY
- SW System Analysis - Background SW System Model
. Documented in Calc 96-0059
. Updated periodically to reflect changes / updates
- Base Calculations (Steady-State Analyses)
. 96-0117, Post-LOCA SIInjection Phase '
. 95-0119, Post-LOCA SI Sump Recirculation Phase
. 97-0054, Initially in SW LCO, Post LOCA Injection
. 97-0126, Initially in SW LCO, Post-LOCA Recirculation 14
i
~
- SERACE WATER SYSTEM ISSUES & I/10 DEL MARUN CONRY t
- GL 96-06 Analysis (Transient, Water Hammer {
Analyses) \
J FAI did transient water hammer analyses -
results to S&L t S&L used results to perform pipe stress analyses to determine need for support modifications 1
i 15
~
__..._-__._..._-_._--_________________-_-_--____-----_-O
~
~' '
SERVICE WATER SYSTEM
/SSUES & MODEL MARLIN CONRY e Recent SW System Issues
- Summary of Condition Reports written since January 1,1997 Categorization
. SW System Design Deficiencies [6]
. SW Calculation Deficiencies [201
- 1) analysis error - 11 (4 of these by Westinghouse)
- 2) Operations / Engineering interface - 3
- 3) error in original model- 3
- 4) Incomplete analysis or documentation - 2
- 5) procedure error- 1
. Documentation Errors [5]
. Configuration Management Deficiencies (2]
16
SERVICE WATER SYSTEM ISSUES & MODEL MARUN CONRY
- Recent SW System Issues (cont.)
Status l:
Many of these willbe completed via
! revision to the base calculations to incorporate outstanding issues Some ODs have resulted in SW system operational restrictions
- 1) One CCW HXIn service per Unit
- 2) restricted CCW Inlet endbeII and AFW blowdowns
- 3) revised SW pump IST minimum acceptance criteria
- 4) revised band of acceptable CFC fouling factor The cumulative impact of existing ODs is primarily evident in the revised acceptance criteria for the SW Pump performance and CFC fouling factor 17
l*
SERVICE WATER SYSTEM l
ISS/JES & MODEL MARLIN CONRY
- WE Confidence In Sl// System Analyses General SW system analyses is far-reaching and comprehensive Personnel involved with SW from aII work groups demonstrate a questioning attitude AII conditions will continue to be Condition Reported Historical Basis for Confidence
. System configurations used in our analyses are very conservative SW system validation testing documented in calc N-92-087 Program to periodically blow down the SW system to remove slit Program to routinely RT the SWpiping
- 1) slit
- 2) macrofouling (nodules, zebra mussels)
- 3) pipe waII thinning
- GL 89-13 testing of CFCs, EDGs, CCWs 18
E SERVICE WATER SYSTEM
/SS/JES & MODEL MARUN CONRY Historical Basis for Confidence (cont)
- Testing upon Implementation of CFC throttle Valve setting procedure Chlorination program to deter brofouling
- S&L and FAIIndependently confirmed WE's conservative modeIIng methodology for potential two-phase flow conditions usIng a single phase flow modeling program
- Meetings with Operations to confirm analyses
- Current Plans To Support SW Functionality Improve the ability of Operations to use the system as needed Provide operational flexibility with regard to CCW HX cooling Restore varl0US system blowdowns DeVeiop a new conservative analysis methodology with FAI's help, using our existing single phase fluid flow tools but removing some of the conservatism from our current methodology 1
- Integrate FAI's two-phase flow analysis tools
[
-with our existing WATER program to provide a U true picture of SW system performance 19 1
4 j
L --
~
~ '
SERVICE WATER SYSTEM ISSUES & MODEL MARLIN CONRY
- Future Plans To Enhance Our Process
- Develop a new SW hydraulic model using ProtoFlo Software developer has an approved 10CFR50 Appendix B QA program Single-phase thermal-hydraulic analysis tool c .
Model can be extended to support SW upgrade project
- Baseline the new ProtoFlo model against test data Discreet component testing Integrated system testing 20
l l
SERVICE WATER SYSTEM ISSfJES & MODEL MARLIN CONRY 1
- Service Water System Upgrade Project Nineteen system modifications that will:
- 1) increase the overall SW system capacity
- 2) Increase flow rates to critical components
- 3) Improve Isolation of non-essential loads during DBAs
- 4) Improve Isolation capabilities for maintenance
- 5) Increase the margin on critical system parameters
- 6) raise the SWsystem design temperature
- 7) resolve maintenance issues associated with existing pumps
- 8) allow one SW pump to be 005 without LCO entry
- 9) provide redundant SW supply to SFP HXS
- 10) provide capacity to allow DBA concurrent w/cooldown
- 11) Improve corrosion controlmeasures
- 12) Increase accuracy of SW pump ISTinstrumentation 21
- - - - - - - . - _ - - - . - - - _ )
E l i.
. '. '. 1 EMPLOYEE CONCERNS PROGRAM AL CAPRISTO e ECP Beginnings & Goals Early 1997 - Began ECP to meet industry standards and respond to regulatory expectations
- Late 1997- Recognized need to expand ECP program as a result ofinternal indicators and allegation trends Encourage self-identification and effective correction of ourissues ECP fosters safety conscious work environment (SCWE) improvements:
. Skills training, coaching with
" receivers"
. Assistance and encouragement for problem identification and effective correction
. Share observations with managers 22
\
EMPLOYEE CONCERNS PROGRAM AL CAPRISTO
. Actions Taken
- Removed Condition Reporting process barriers l
1 Reiterated expectations for SCWE
- Consultant conducting training for receivers
- Cultural Assessment - all hands survey Establishing performance indicators Full-time ECP Manager as of April 20,1998 Prompt response to issues and indicators
-- Timely, Effective, Confidential
)
23 j
l
~
EMPLOYEE CONCERNS PROGRAM AL CAPRISTO
- Current Status of SCWE/ECP
- Cultural Assessment Report due June 15 Vendor contract revisions
- Establishing personal credibility with frequent contact and presence All hands and department meetings Walk arounds, meeting attendance
- Working on open ECP files Reducing reliance on consultants ;
24
l .
EMPLOYEE CONCERNS PROGRAM AL CAPRISTO l
- Future Direction of ECP EVaivate staff training needs - Phase II GET Indoctrination / Exit interviews New contact methods Postage paid mailer / toll free hotline QWSelf-assessments of SCWE Periodic Culture Assessments 25
EMPLOYEE CONCERNS PROGRAM AL CAPRISTO e Early Indicators
- ECP Activity - 4 in last month; 12 YTD Expecting more internalissues as ,
program demonstrates effectiveness Good support at alllevels for ECP I Providing requested coaching and counseling before issues arise Management is focused on improving SCWE l
I l
l l
l 26
< - - ____ _ _______-__ ___ ___ _ -___-_-_- _ ___ =
COMMITMENT MANAGEMENT SCOTT PATULSKI
- Wisconsin Electric has completed a number of corrective actions to improve our performance.
Many of these corrective actions were docketed commitments made to the Nuclear Regulatory Commission.
- Since late summer of 1996, Wisconsin Electric docketed approximately 775 corrective action commitments.
t 27
COMMITMENT MANAGEMENT SCOTT PATULSKI
- We have completed approximately 580 corrective action commitments and follow-on actions since late summer 1996, including the 148 September 1996 enforcement conference and Unit 2 restart commitments.
- Completed corrective actions include:
66 Generic Letter actions 140 LER actions 198 inspection report actions \
1
- 29 miscellaneous actions arising from confirmatory action letters, operating license conditions, code issues, and requests for ;
additionalinformation.
28 j i
J
t
\.
COMMITMENT MANAGEMENT SCOTT PATULSKI e Summary of Cominicments Pending l
Point Beach Nuclear Plant is currently reviewing our open commitments. The list of open NRC commitments was Verified by Licensing and we currently have approximately 195 corrective action NRC commitments pending Quality Assurance performed a surveillance of our NRC open items during the week of May 11.
Currently, approximately 160 of these items are committed to be completed in 1998, or by the end of the Unit 2 Refueling 23 outage.
U2R23 is planned for late 1998 or early 1999
1
\
COMMITMENT I/IANAGEMENT SCOTT PATULSKI
- Future Commitment liianagement 1
- PBNP is about to achieve a major milestone by entering an extended dual unit operation period
- PBNP now has a predictable Outage schedule for the next 2-3 years
(
- With the expected achievement of dual unit operation and planned future outage schedules, now is the appropriate time for 1 PBNP to reassess and reprioritize our ongoing improvement initiatives and work efforts
- in addition to validating our pending NRC commitments, we are in the process of reviewing and prioritizing all open action items in our NUTRK database
- Prioritizing NES transition, engineering work and planned process upgrades
- Anticipated completion of commitment reprioritization by September 1,1998. We will hold a management meeting with Region III at that time.
30
.. . ~
SECURITY UPGRADE PROJECT MARKFINDLAY
- Reason for Replacement Replace aging equipment and resolve Y2K concerns
- Reduce CAS operator distractions by installing current industry standard alarm intrusion equipment Reduction of workarounds and compensatory measures j
- Enhance response force capabilities
- Reduce equipment-generated loggable events 31 j
SECURITY UPGRADE PROJECT MARK FINDLAY l
- Security Access Control Project Scope
- Replacement of security computers
- Replacement of alarm station consoles Modification of card readers
- Installation of hand geometry in gatehouses
- Installation of maintenance and training console 32
SECURITY UPGRADE PROJECT MARK FINDLAY e Security Perimeter Replacement Project Scope l
1 -
Addition of nuisance fence
- Relocation and replacement ofintrusion equipment Redeployment and potential additions to >
CCTV Increase PA illumination levels Replacement of original equipment cables 33
. c. ..
l SECURITY UPGRADE PROJECT MARK RNDLAY e Project Schedule
- October 1997- Conceptual design approved March 1999 System development and installation preparation complete
- November 1999 -Installation and testing complete
- April 2000 - Close-out of modifications complete l
34 l
L -- _ __ . _ - - .
._