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Category:CORRESPONDENCE-LETTERS
MONTHYEARNPL-99-0564, Forwards Response to NRC Request During 990720 Meeting,To Provide Addl Details to Several Questions Re Amend Currently Under Review by Staff Pertaining to CR Habitability1999-10-19019 October 1999 Forwards Response to NRC Request During 990720 Meeting,To Provide Addl Details to Several Questions Re Amend Currently Under Review by Staff Pertaining to CR Habitability ML20217A5911999-09-30030 September 1999 Advises of NRC Plans for Future Insp Activities at Facility for Licensee to Have Opportunity to Prepare for Insps & to Provide NRC with Feedback on Any Planned Insps Which May Conflict with Plant Activities.Plant Issues Matrix Encl 05000266/LER-1999-007, Forwards LER 99-007-00 for Point Beach Nuclear Plant,Unit 1. Condition Would Be Outside App R Design Basis for Plant.New Commitments within Rept Indicated in Italics1999-09-30030 September 1999 Forwards LER 99-007-00 for Point Beach Nuclear Plant,Unit 1. Condition Would Be Outside App R Design Basis for Plant.New Commitments within Rept Indicated in Italics ML20212J7431999-09-30030 September 1999 Forwards Insp Repts 50-266/99-15 & 50-301/99-15 on 990830- 0903.No Violations Noted.Inspectors Concluded That Util Licensed Operator Requalification Training Program Satisfactorily Implemented NPL-99-0555, Discusses Rev 1,suppl 1 to GL 92-01, Reactor Vessel Structural Integrity. Calculation That Provides Evaluation of New Surveillance Data for Assessing Integrity of Unit 1 Reactor Vessel1999-09-29029 September 1999 Discusses Rev 1,suppl 1 to GL 92-01, Reactor Vessel Structural Integrity. Calculation That Provides Evaluation of New Surveillance Data for Assessing Integrity of Unit 1 Reactor Vessel ML20212K7651999-09-29029 September 1999 Forwards Insp Repts 50-266/99-13 & 50-301/99-13 on 990714-0830.No Violations Noted.Operators Responded Well to Problems with Unit 1 Instrument Air Leak & Unit 2 Turbine Governor Valve Position Fluctuation ML20212D5771999-09-15015 September 1999 Discusses Review of Response to GL 88-20,suppl 4,requesting All Licensees to Perform Ipeee.Ser,Ter & Supplemental TER Encl ML20211Q6451999-09-0808 September 1999 Forwards Operator Licensing Exam Repts 50-266/99-301OL & 50-301/99-301OL for Exams Conducted on 990726-0802 at Point Beach Npp.All Nine Applicants Passed All Sections of Exam ML20211Q4171999-09-0606 September 1999 Responds to VA Kaminskas by Informing That NRC Tentatively Scheduled Initial Licensing Exam for Operator License Applicants During Weeks of 001016 & 23.Validation of Exam Will Occur at Station During Wk of 000925 05000266/LER-1999-004, Forwards LER 99-004-01,re Fuel Oil Transfer Pump Cable in AFW Pump Room Being Outside App R Design Basis.Suppl to LER Provides Corrective Actions to Address Concerns Re Fire Disrupting Electrical Power to Fuel Oil Transfer Pump1999-09-0202 September 1999 Forwards LER 99-004-01,re Fuel Oil Transfer Pump Cable in AFW Pump Room Being Outside App R Design Basis.Suppl to LER Provides Corrective Actions to Address Concerns Re Fire Disrupting Electrical Power to Fuel Oil Transfer Pump ML20211K5261999-08-31031 August 1999 Forwards Insp Repts 50-266/99-14 & 50-301/99-14 on 990726- 30.Areas Examined within Secutity Program Identified in Rept.No Violations Noted ML20211F6941999-08-27027 August 1999 Provides Individual Exam Results for Applicants That Took Initial License Exam in July & August of 1999.Completed ES-501-2,copy of Each Individual License,Ol Exam Rept, ES-303-1,ES-303-2 & ES-401-8 Encl.Without Encl NPL-99-0473, Informs of Change Being Made to Plan Third 10-year Interval ISI Long Term Plan.Change Extends Interval from Current End Date of 001130 to 020831,due to Operating Cycle Being Increased from 12 to 18 Months1999-08-27027 August 1999 Informs of Change Being Made to Plan Third 10-year Interval ISI Long Term Plan.Change Extends Interval from Current End Date of 001130 to 020831,due to Operating Cycle Being Increased from 12 to 18 Months ML20211E8791999-08-24024 August 1999 Discusses Completion of Licensing Action for GL 96-01, Testing of Safety-Related Logic Circuits, for Point Beach Nuclear Power Plant,Units 1 & 2.Licensees Provided Requested Info & Responses Required by GL 96-01 ML20211F1501999-08-24024 August 1999 Submits Summary of Meeting Held on 990729,in Region III Office with Util Re Proposed Revs to Plant Emergency Action Level Criteria Used in Classifying Emergencies & Results of Recent Improvement Initiatives in Emergency Preparedness 05000266/LER-1999-006, Forwards LER 99-006-00 Which Describes Discovery That Postulated Fire in Central Zone of Primary Auxiliary Bldg Could Result in Spurious Operation of Pressurizer Porv. New Commitments within Rept Are Indicated in Italics1999-08-19019 August 1999 Forwards LER 99-006-00 Which Describes Discovery That Postulated Fire in Central Zone of Primary Auxiliary Bldg Could Result in Spurious Operation of Pressurizer Porv. New Commitments within Rept Are Indicated in Italics NPL-99-0477, Forwards Revised Procedures to Point Beach Nuclear Plant Epips.Revised Procedures Dtd 990723,should Be Filed in NRC Copies of Manual IAW Attached Instructions1999-08-18018 August 1999 Forwards Revised Procedures to Point Beach Nuclear Plant Epips.Revised Procedures Dtd 990723,should Be Filed in NRC Copies of Manual IAW Attached Instructions NPL-99-0426, Requests Relief from Section II of ASME B&PV Code, Nuclear Vessels, 1965 Edition,No Addenda.Detailed Info Attached1999-08-16016 August 1999 Requests Relief from Section II of ASME B&PV Code, Nuclear Vessels, 1965 Edition,No Addenda.Detailed Info Attached ML20210L9141999-08-0404 August 1999 Informs That Versions of Info Re WCAP-14787,submitted in 990622 Application for Amend,Marked Proprietary,Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954,as Amended ML20210K5221999-08-0404 August 1999 Discusses Point Beach Nuclear Plant,Units 1 & 2 Response to Request for Info in GL 92-01,Rev 1,Suppl 1, Rv Structural Integrity NPL-99-0436, Forwards fitness-for-duty Performance Data for six-month Period Ending 9906301999-08-0202 August 1999 Forwards fitness-for-duty Performance Data for six-month Period Ending 990630 ML20210G6011999-07-30030 July 1999 Discusses 990415 Complaint OSHA Received from Employee of Wisconsin Electric Power Co Alleging That Employee Received Lower Performance Appraisal for 1998 Because Employee Raised Safety Concerns While Performing Duties at Point Beach NPL-99-0406, Provides Response to NRC GL 99-02, Lab Testing of Nuclear- Grade Activated Charcoal1999-07-29029 July 1999 Provides Response to NRC GL 99-02, Lab Testing of Nuclear- Grade Activated Charcoal ML20210H0211999-07-28028 July 1999 Forwards Insp Repts 50-266/99-09 & 50-301/99-09 on 990528-0713.Two Violations of NRC Requirements Occurred & Being Treated as non-cited Violations,Consistent with App C of Enforcement Policy ML20210G2441999-07-26026 July 1999 Discusses 990714 Meeting with PRA Staff to Discuss Initiatives in Risk Area & to Establish Dialog Between SRAs & PRA Staff NPL-99-0408, Forwards Pbnps,Units 1 & 2 Plant Simulation Four-Yr Rept, IAW 10CFR55.45(b)(5)(ii).Rept Describes Certification Program Tests Conducted from 1996-1999,identifies Test Discrepancies Still Outstanding & Schedules for 2000-20031999-07-15015 July 1999 Forwards Pbnps,Units 1 & 2 Plant Simulation Four-Yr Rept, IAW 10CFR55.45(b)(5)(ii).Rept Describes Certification Program Tests Conducted from 1996-1999,identifies Test Discrepancies Still Outstanding & Schedules for 2000-2003 ML20209H5471999-07-14014 July 1999 Forwards Insp Repts 50-266/99-12 & 50-301/99-12 on 990614-18.One Violation Noted,But Being Treated as non-cited violation.Long-term MOV Program Not Sufficiently Established to close-out NRC Review of Program,Per GL 89-10 NPL-99-0395, Forwards Partial Response to NRC 990512 RAI Re TS Change 204 Re Control Room Habitability.Meeting Is Planned with NRC to Discuss Issues Related to Control Room & Primary Auxiliary Bldg Ventilation Sys Modifications1999-07-12012 July 1999 Forwards Partial Response to NRC 990512 RAI Re TS Change 204 Re Control Room Habitability.Meeting Is Planned with NRC to Discuss Issues Related to Control Room & Primary Auxiliary Bldg Ventilation Sys Modifications NPL-99-0390, Projects Listed Major near-term License Amend Requests That Could Be Expected to Impact Staff Resources Into Fiscal Years 2000 & 2001,in Response to Administrative Ltr 99-021999-07-0808 July 1999 Projects Listed Major near-term License Amend Requests That Could Be Expected to Impact Staff Resources Into Fiscal Years 2000 & 2001,in Response to Administrative Ltr 99-02 NPL-99-0388, Forwards MORs for June 1999 & Revised MORs for May 1999 for Pbnps,Units 1 & 21999-07-0707 July 1999 Forwards MORs for June 1999 & Revised MORs for May 1999 for Pbnps,Units 1 & 2 NPL-99-0381, Submits Response to NRC GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. GL 98-01 Requested Response on Status of Facility Y2K Readiness by 990701.Disclosure Encl1999-06-30030 June 1999 Submits Response to NRC GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. GL 98-01 Requested Response on Status of Facility Y2K Readiness by 990701.Disclosure Encl ML20196J4161999-06-30030 June 1999 Discusses Relief Requests Submitted by Wisconsin Electric on 980930 for Pump & Valve Inservice Testing Program,Rev 5. Safety Evaluation Authorizing Relief Requests VRR-01,VRR-02, PRR-01 & ROJ-16 Encl NPL-99-0379, Documents Telcon with Hg Ashar of NRC Re Licensee Intentions & Basis for Reselection of Control Tendons in Pbnps Containment Structures.Plants Are Currently Completing 28th Year Tendon Surveillance During Summer of 19991999-06-29029 June 1999 Documents Telcon with Hg Ashar of NRC Re Licensee Intentions & Basis for Reselection of Control Tendons in Pbnps Containment Structures.Plants Are Currently Completing 28th Year Tendon Surveillance During Summer of 1999 NPL-99-0376, Forwards Errata to Pbnp 1998 Annual Monitoring Rept, Originally Submitted by Ltr Dtd 990427.List of Corrections, Provided1999-06-28028 June 1999 Forwards Errata to Pbnp 1998 Annual Monitoring Rept, Originally Submitted by Ltr Dtd 990427.List of Corrections, Provided NPL-99-0353, Forwards June 1999 Rev to FSAR for Point Beach Nuclear Plant,Units 1 & 2, IAW Requirements of 10CFR50.71(e).Each Package Contains Revised FSAR Pages That Are to Be Inserted IAW Instructions1999-06-23023 June 1999 Forwards June 1999 Rev to FSAR for Point Beach Nuclear Plant,Units 1 & 2, IAW Requirements of 10CFR50.71(e).Each Package Contains Revised FSAR Pages That Are to Be Inserted IAW Instructions ML20196D4931999-06-18018 June 1999 Forwards Insp Repts 50-266/99-08 & 50-301/99-08 on 990411- 0527.No Violations Noted.Operator Crew Response to Equipment Induced Challenges Generally Good.Handling of Steam Plume in Unit 1 Turbine Bldg Particularly Good ML20195J9471999-06-16016 June 1999 Discusses Ltr from NRC ,re Arrangements Made to Finalized Initial Licensed Operator Exam to Be Administered at Point Beach Nuclear Plant During Week of 990726 ML20196A2931999-06-16016 June 1999 Ack Receipt of Transmitting Changes to Listed Sections of Point Beach Nuclear Plant Security Plan & ISFSI Security Plan,Submitted IAW 10CFR50.54(p).No NRC Approval Is Required Since Changes Do Not Decrease Effectiveness ML20195J9251999-06-14014 June 1999 Discusses 990610 Telcon Between Wp Walker & D Mcneil Re Arrangements for NRC to Inspect Licensed Operator Requalification Program at Point Beach Nuclear Power Plant for Week of 990816 05000266/LER-1999-005, Forwards LER 99-005-00,re Failure of Shell of 4B FW Heater Which Resulted in Significant Steam Leak & Manual Trip. New Commitments within Rept Are Indicated in Italics1999-06-11011 June 1999 Forwards LER 99-005-00,re Failure of Shell of 4B FW Heater Which Resulted in Significant Steam Leak & Manual Trip. New Commitments within Rept Are Indicated in Italics NPL-99-0336, Forwards Unit 2 Refueling 23 Inservice Insp Summary Rept for Form NIS-1, IAW ASME Section Xi,Subsection IWA-62301999-06-10010 June 1999 Forwards Unit 2 Refueling 23 Inservice Insp Summary Rept for Form NIS-1, IAW ASME Section Xi,Subsection IWA-6230 NPL-99-0330, Forwards Revs to Pbnp Security Plan Sections 2.1,2.4,3.1, Figures A,D & T & Pbnp ISFSI Security Plan Section 2.0, Dtd 990604.Plans Withheld1999-06-0404 June 1999 Forwards Revs to Pbnp Security Plan Sections 2.1,2.4,3.1, Figures A,D & T & Pbnp ISFSI Security Plan Section 2.0, Dtd 990604.Plans Withheld 05000301/LER-1999-003, Forwards LER 99-003-00 for Point Beach Nuclear Plant,Unit 2. Rept Is Provided in Accordance with 10CFR50.73(a)(2)(i)(B), as Any Operation or Condition Prohibited by Plant Tech Specs1999-05-28028 May 1999 Forwards LER 99-003-00 for Point Beach Nuclear Plant,Unit 2. Rept Is Provided in Accordance with 10CFR50.73(a)(2)(i)(B), as Any Operation or Condition Prohibited by Plant Tech Specs NPL-99-0319, Provides Main Control Board Wiring Separation Project Status Update Rept for Pbnps,Units 1 & 21999-05-28028 May 1999 Provides Main Control Board Wiring Separation Project Status Update Rept for Pbnps,Units 1 & 2 ML20206T3691999-05-17017 May 1999 Ltr Contract,Task Order 242 Entitled, Review Point Beach 1 & 2 Conversion of Current TS for Electrical Power Systems to Improved TS Based on Standard TS, Under Contract NRC-03-95-026 ML20206N5561999-05-13013 May 1999 Informs That NRC Office of Nuclear Reactor Regulation Reorganized Effective 990328.As Part of Reorganization,Div of Licensing Project Mgt Created.Cm Craig Will Be Section Chief for Point Beach Npp.Organization Chart Encl ML20206P2551999-05-12012 May 1999 Forwards Handout Provided to NRC by Wisconsin Electric at 990504 Meeting Which Discussed Several Recent Operational Issues & Results of Recent Improvement Initiatives in Engineering ML20206N5331999-05-12012 May 1999 Forwards RAI Re & Suppl by Oral Presentation During 980604 Meeting,Requesting Amend for Plant,Units 1 & 2 to Revise TSs 15.3.12 & 15.4.11 ML20196F3211999-05-11011 May 1999 Requests Proprietary WCAP-14787, W Revised Thermal Design Procedure Instrument Uncertainty Methodology for Wepc Point Beach Units 1 & 2 (Fuel Upgrade & Uprate to 1656 Mwt-NSSS Power), Be Withheld from Public Disclosure ML20206K0391999-05-0707 May 1999 Forwards Insp Repts 50-266/99-06 & 50-301/99-06 on 990223- 0410.Ten Violations of NRC Requirements Occurred & Being Treated as non-cited Violations,Consistent with App C of Enforcement Policy 1999-09-08
[Table view] Category: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] |
See also: IR 05000301/1992018
Text
_ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ . _ . _ _ _ _ .
.
, ,', DC 0/Oc.6
5I Decembei 8, 1992
Docket No. 50-301
License No. DPR-i~.
EA 92-205
Wisconsin Electric Power Company
ATTH: Mr. R. E. Link, Vice President
fluclear Power
231 West Michigan Street - P379
Milwaukee, Wisconsin 53201
Dear Mr. Link:
, _
SUBJECT: NOTICE OF VIOLATION AllD PROPOSED IMPOSITION OF CIVIL
PENALTY - $75,000
(NRC INSFECTION REPORT 50-301/92018)
This refors to the safety incpection conducted during the period
from August 24, 1992, through October 12, 1992, at the Point
Beach Nuclear Plant Unit 2. During this inspection, significant
violations of NRC requirements were identified, and on ~
November 6, 1992, an enforcement conference was conducted in the
Region III office. Attending the enforcement conference were -
you, Dr. Carl Paperiello, Deputy Regional Administrator, and
other members of our respective staffs. The report documenting
the inspection was sent to you by letter dated October 30, 1992.
The report summarizing the enforcement conference was sent to you
by letter dated November 18, 1992.
During performance of an annual containment spray leakage
reduction test on the "A" train for Unit 2 on September 17, 1992,
the discharge pressure of containment spray pump P-14A was -
observed by operators to be lower than that for containment spray
pump P-14B. During the quarterly containment spray pump test on
the "A" train for Unit 2 on September 18, 1992, operators
observed abnormally low discharge pressure and noises on
containment spray pump P-14A. Subsequent disassembly of the pump
revealed a foam disk wrapped in duct tape blocking the impeller
of the pump.
! ')'
Plant personnel believe that the disk was inserted into an
l ; existing section of piping when it was cut to install a "T"
! k . connection for modification IWP 88-098 which was performed during
0 the fall 1991 refueling outage. This modification allows full
l 7
flow testing of containment spray (CS), safety injection (SI),
- and residual heat removal (RHR) systems as recommended by NUREG-
/dhb
g
0578. The modification consisted of 6-inch diameter (15 cm)
_
CESTJJlRD_MML
RECEIPT REQUESTED
11001a g=gg'
,
- m ,
- - _ _ _ _ _ -- ____-___ _ __--_ . . _ _ _ _
-
-
' ' '
'
,
, l
.
I
Wisconsin Electric -2 -
Deumber 8, 1992 !
Power Company J
piping connecting the various pump discharges to the refueling l
water storage tank (RWST). Post-modification testing had i
'
verified that all newly installed pipe was free of blockage.
However, the existing piping that was not modified as part of the
.
,
full flow test line modification was not tested.
t
In addition to being used to perform the annual containment spray
leakage test, this line is used during the recirculation mode of
safety injection. Therefore, the disk remaining in the system I
following the modification rendered the "A" train safety
,
injection system piping inoperable.
i
The violations are described in the enclosed Hotice of Violation -
and Proposed Imposition of Civil Penalty (Notice) and involve the
'
failure to ensure that foreign material exclusion requirements
were adequately implemented during modification activities
associated with the fall 1991 refueling outage. The Notice also
pertains to restarting the-plant and operating it for nearly a ~
year with one train of the safety injection system piping being
inoperable in violation of technical specifications (TS). The- t
violations in the aggregate represent a significant safety
concern and are ca+egorized as a Severity Level III problem in
accordance with the General Statement of Policy and Procedure
for NRC Enforcement Actions," (EnDircement Policy) 10 CFR Part 2, >
Appendix C.
The root cause of leaving the foam di k in the system was
inadequate procedures for material exclusion control. You
indicated at the enforcement confere:.cc that inserting such
foreign material exclusion disks in piping systems during
modification work is not prohibited'by plant procedures, and that
the decision to use these was left up to the craft personnel
doing the work. In this case, the contract craft personnel
performing the worP chose to use a disk, but neither their
procedures nor QC inspection personnel identified that the disk
remained in the system upon completion of the modification.
Additionally, your personnel had not reviewed the contractor's-
procedure prior to its use to verify if it contained adequate:
controls. Therefore, the plant was in violation of the TS that-
prohibits plant startup unless all valves and~ piping associated ,
with the safety injection system that are required to function'
during accident conditions are operable. The plant was made
critical in November 1991 and operated until the problem was
- discovered in September 1992.-
The staff recognizes that immediate corrective actions were taken
when the problem was identified. You formed an incident
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investigation team to thoroughly review the event and performed
- extensive radiographic and boroscopic examinations of as much of -
the CS, RHR, and SI systems for both Units-1 and 2 as were
c er-yr+ - -r- :y -- e-e q- mv gyr e- + ,ew-
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Wisconsin Electric -3 - December 8, 1992
Power company '
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accessible. In the longer term, you are revising your procedures
to better control such work (using INPO good practices ,
guidelines) and are creating and implementing an enhanced foreign i
material exclusion program. Also, the maintenance group's job
observation checklist will be revised to include observation of ;
foreign material exclusion practices on the job. !
Nevertheless, due to the safety significance of this violation,
and to emphasize the importance of ensuring that modification
activities performed on safety systems are properly implemented ;
and erecuted under strict compliance with foreign material
exclusicn requirements, and that adequate contractor oversight is
provided, I have been authorized, after consultation with the
Director, Office of Enforcement, and the Deputy Executive
Director for Nuclear Reactor Regulation, Regional Operations and
Research, to issue the enclosed Hotice of Violation and Proposed
Imposition of Civil Penalty in the amount of $75,000 for the
Severity Level III problem.
,
The base civil penalty for a Severity Level III problem is
$50,000. The escalation and mitigation factors in tbc
Enforcement Policy were considered. Mitigation of 25 percent was
appropriate for your initiative in identifying the root cause of-
this self-disclosing event. Mitigation of 2S percent was also
appropriate for your corrective actions that involved procedural,
job observation checklist, and work control _ improvements and a
significant effort to verify the scope of the potential problem
through testing and inspection. The Enforcement Policy permits
50 percent mitigation for corrective actions but the full
allowance for this factor was not appropriate because you did not
broadly address the issue of contractor oversight (i.e., training
and supervision). Specifically, you have taken corrective
actions for future contractor work involving foreign material
exclusion which will prevent problems similar to those in this
-
event. However, you have not addressed whether there'is a
broader problem in maintaining overcight of contractors.- Thel
civil penalty was escalated 100 percent because of the-duration
of this avoidable and safety significant problem that resulted in
operating the plant for nearly a year with one train of the SI
system piping inoperable. The other factors in the Enforcement
Policy were considered and no further adjustment was appropriate.
Based on the assessment of the civil pensity adjustment factors,
the base civil penalty was escalated 50 percent.
You are required to respond to this letter and should follow the _
instruction.specified in the enclosed Notice when preparing your
response. In your response, you.should document the specific
actions _taken and any additional actions you plan to. prevent
recurrence. After reviewing your response to this. Notice,
including your proposed corrective actions and the results of
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Wisconsin Electric -4 - December 8, 1992
Power Company
including your proposed corrective actions and the results of
future inspections, the NRC will determine whether further NRC
enforcement action is necessary to ensure compliance with NRC
regulatory requirements.
In accordance with 10 CFR 2.790 of the NRC's " Rules of Practico,"
a copy of this letter and its enclosure will be placed in the NRC
Public Document Room.
The response directed by this letter and the enclosed Notice are
not subject to the clearance procedures of the office of
Management and Budget as required by the Paperwork Reduction Act
of 1980, PL 96-511.
Should you have any questions concerning this letter, please
contact us.
Sincerely,
d zSv6b2 i
A. Bert Davis
Regional Administrator
Enclosure: Notice of Violation and
Proposed Imposition of Civil Penalty
cc w/ enclosure:
DCD/DCB (RIDS)
G. J. Maxfield, Plant Manager
OC/LFDCB
Resident Inspector, Point Beach
Virgil Kanable, Chief
Boiler Section
Charles _ Thompson, Chairman
Wisconsin Public Service
Commission
Robert M. Thompson, Administrator
WI Div. of Emergency Govt.
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December 8, 1992
Wisconsin Electric-
Power Company
DISTRIBUTION:
SECY
CA
JSniezek, DEDR
ADDavis, RIII
JLieberman, OE
LChandler, OGC
JGoldberg, OGC
TMurley, NRR
JPartlow, NRR
Enforcement Coordinators
RI, RII, RIV, RV
FIngram, GPA/PA
DWilliams, OIG
BHayes, OI
EJordan, AEOD
JLuchman, OE
LTran, OE
Day File
EA File
-DCS
RAO:RIII
SLO:RIII
PAO;RIII
IMS;RIII
'kg
R:pL IL. DtOE* RII
'e
De I a e/pb G man an Davis
12/ /92 12/q/92 12//:/92 12///92
- Concurrence received via fax. N , p[3 g1
N.
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NOTICE OF VIOLATION
AND
PROPOSED ,T(POSITION OF CIVIL PENALTY
Wisconsin Electric Power Co. Docket No. 50-301
Point Beach Nuclear Plarit License No. DPR-30
Unit 2 EA 92-205
During an inspection conducted from August 24 through October 12,
1992, violations of NRC requirements were identified. In
accordance with the " Statement of Policy and Procedure for NRC
Enforcement Actions," 10 CFR Part 2, Appendix C, the Nuclear
Ragulatory Commission proposes to impose a civil penalty pursuant
to Section 234 of the Atomic Energy Act of 1954, as amended
(Act), 42 U.S.C. 2282, and 10 CFR 2.205. The particular -
violations and associated civil penalty are set forth below:
A. Technical Specification 15.3.3.A.1.g requires, in part, that
a reactor shall not be made critical, except for low
temperature physics tests, unless al) valves and piping
_
associated with the safety injection system components that
are required to function during accident conditions are
operable.
Contrary to the above, on or about November 13, 1991, the
Unit 2 reactor was made critical, not in connection with low
temperature physics tests, while the piping associated with
train A of the containment recirculation mode of safety
injection, which is required to function during accident
conditions, was inoperable. Specifically, a foreign
material exclusion disk had been left in a section of the
system piping leading to the suction of the train A safety
injection pump.
-
B. 10 CFR Part 50, Appendix B, Criterion V, " Instructions,
Procedures, and Drawings", requires, in part, that
activities affecting quality be prescribed by procedures of
a type appropriate to the circumstances and shall include
appropriate quantitative or qualitative acceptance criteria
for determining that important activities have been
satisfactorily accomplished.
Contrary to the above, on or about October 17, 1991,
Procedure QAP-105-PB, " Cleanliness Inspection of Fluid
Systems and Components," Revision 1, a procedure affecting
quality, did not include appropriate guidance or acceptance
criteria to ensure that debris was not left inside the
safety injection and containment spray pump suction during
performance of modification IWP 88-098.
'this is a Severity Level III problem (Supplement I).
Civil Penalty - $75,000
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Notice of Violation -2 -
Pursuant to the provisions of 10 CFR 2.201, Wisconsin Electric
Power Company (Licensee) is hereby required to submit a written
statement of explanation to the Director, Office of Enforcement,
U.S. Nuclear Regulatory Commission, within 30 days of the date of
this Notice of Violation and Proposed Imposition of Civil Penalty
(Notice). This reply should be clearly marked as a " Reply to a
Notice of Violation" and should include for each alleged
violations (1) admission or denial of the alleged violation, (2)
the reasons for the violation if admitted, and if denied, the
reasons why, (3) the corrective steps that have been taken and
the results achieved, (4) the corrective steps that will be taken
to avoid further violations, and (5) the date when full
compliance will be achieved. If an adequate reply is not
received within the time specified in this Notice, an order or a
demand for information may be issued as to why the license should
not be modified, suspended, or revoked or why such other actions
! as may be proper should not be taken. Consideration may be given
'
to extending the response time for good cause shown. Under the
authority of Section 182 of the Act, 42 U.S.C. 2232, this
response shall be submitted under oath or affirmation.
Within the same time as provided for the response required under
10 CFR 2.201, the Licenseo may pay the civil penalty by letter
addressed to the Director, Office of Enforcement, U.S. Nuclear
, Regulatory Commission, with a check, draft, money order, or
electronic transfer payable to the Treasurer of the United States
in the amount of the civil penalty proposed above, or may protest
imposition of the civil penalty in whole or in part, by a written
answer addressed to the Director, Office of Enforcement, U. S.
Nuclear Regulatory Commission. Should the Licensee fail to
answer within the time specified, an order imposing the civil
penalty will be issued. Should the Licensee elect to file an
answer in accordance with 10 CFR 2.205 protesting the civil
i penalty, in whole or in part, such answer should be clearly
marked as an " Answer to a Notice of Violation" and may: (1) deny
the violations listed in this Notice in whole or in part, (2)
demonstrate extenuating _ circumstances, (3) show error in this
Notice, or (4) show other reasons why the penalty should not be
I imposed. In addition to protesting the civil penalty in whole or
in part, such answer may request remission or mitigation of the
penalty.
1
In requesting mitigation of the proposed penalty, the factors
addressed in Section V.B of 10 CFR Part 2, Appendix C, should be
addressed. Any written answer in accordance with 10 CFR 2.205
should be set forth separately from the statement or explanation
in reply pursuant to 10 CFR 2.201, but may incorporate parts of
the 10 CFR 2.201 reply by specific reference (e.g., citing page
and paragraph numbers) to avoid repetition. The attention of the
Licensee is directed to the other provisions of 10 CFR 2.205,
regarding the procedure for imposing a civil penalty.
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Notice of Violation -3- ,
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Upon failure to pay any civil penalty due which subsequently has
been determined in accordance with the applicable provisions of *
10 CFR 2.205, this matter may be referred to the Attorney -
General, and the penalty, unless compromised, remitted, or ;
mitigated, may be collected by civil action pursuant to Section .
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234c of the Act,-42 U.S.C. 2282c. ;
The responses noted above (Reply to Notice of Violation, letter *
with payn.ont of civil penalty, and Answer to a Hotice of
Violation) should be addressed to: Director, Office of ;
'
Enforcement, U.S. Nuclear Regulatory Commission, ATTN: Document
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control Desk, Washington, D.C. 20555 with a copy to the Regional
Administrator, U.S. Nuclear Regulatory Commission. Region III,
799 Roosevelt Road, Glen Ellyn, Illinois 60137, and a copy to the +
NRC Recident Inspector at the Point Beach Nuclear Plant.
FOR THE NUCLEAR REGULATORY COMMISSION ,
,
, a) "
A. Bert Davis _
,
T<egional Administrator
Dated at Glen Ellyn, Illincip
this 8th day of December l'392
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