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Category:CORRESPONDENCE-LETTERS
MONTHYEARNPL-99-0564, Forwards Response to NRC Request During 990720 Meeting,To Provide Addl Details to Several Questions Re Amend Currently Under Review by Staff Pertaining to CR Habitability1999-10-19019 October 1999 Forwards Response to NRC Request During 990720 Meeting,To Provide Addl Details to Several Questions Re Amend Currently Under Review by Staff Pertaining to CR Habitability ML20217A5911999-09-30030 September 1999 Advises of NRC Plans for Future Insp Activities at Facility for Licensee to Have Opportunity to Prepare for Insps & to Provide NRC with Feedback on Any Planned Insps Which May Conflict with Plant Activities.Plant Issues Matrix Encl 05000266/LER-1999-007, Forwards LER 99-007-00 for Point Beach Nuclear Plant,Unit 1. Condition Would Be Outside App R Design Basis for Plant.New Commitments within Rept Indicated in Italics1999-09-30030 September 1999 Forwards LER 99-007-00 for Point Beach Nuclear Plant,Unit 1. Condition Would Be Outside App R Design Basis for Plant.New Commitments within Rept Indicated in Italics ML20212J7431999-09-30030 September 1999 Forwards Insp Repts 50-266/99-15 & 50-301/99-15 on 990830- 0903.No Violations Noted.Inspectors Concluded That Util Licensed Operator Requalification Training Program Satisfactorily Implemented NPL-99-0555, Discusses Rev 1,suppl 1 to GL 92-01, Reactor Vessel Structural Integrity. Calculation That Provides Evaluation of New Surveillance Data for Assessing Integrity of Unit 1 Reactor Vessel1999-09-29029 September 1999 Discusses Rev 1,suppl 1 to GL 92-01, Reactor Vessel Structural Integrity. Calculation That Provides Evaluation of New Surveillance Data for Assessing Integrity of Unit 1 Reactor Vessel ML20212K7651999-09-29029 September 1999 Forwards Insp Repts 50-266/99-13 & 50-301/99-13 on 990714-0830.No Violations Noted.Operators Responded Well to Problems with Unit 1 Instrument Air Leak & Unit 2 Turbine Governor Valve Position Fluctuation ML20212D5771999-09-15015 September 1999 Discusses Review of Response to GL 88-20,suppl 4,requesting All Licensees to Perform Ipeee.Ser,Ter & Supplemental TER Encl ML20211Q6451999-09-0808 September 1999 Forwards Operator Licensing Exam Repts 50-266/99-301OL & 50-301/99-301OL for Exams Conducted on 990726-0802 at Point Beach Npp.All Nine Applicants Passed All Sections of Exam ML20211Q4171999-09-0606 September 1999 Responds to VA Kaminskas by Informing That NRC Tentatively Scheduled Initial Licensing Exam for Operator License Applicants During Weeks of 001016 & 23.Validation of Exam Will Occur at Station During Wk of 000925 05000266/LER-1999-004, Forwards LER 99-004-01,re Fuel Oil Transfer Pump Cable in AFW Pump Room Being Outside App R Design Basis.Suppl to LER Provides Corrective Actions to Address Concerns Re Fire Disrupting Electrical Power to Fuel Oil Transfer Pump1999-09-0202 September 1999 Forwards LER 99-004-01,re Fuel Oil Transfer Pump Cable in AFW Pump Room Being Outside App R Design Basis.Suppl to LER Provides Corrective Actions to Address Concerns Re Fire Disrupting Electrical Power to Fuel Oil Transfer Pump ML20211K5261999-08-31031 August 1999 Forwards Insp Repts 50-266/99-14 & 50-301/99-14 on 990726- 30.Areas Examined within Secutity Program Identified in Rept.No Violations Noted ML20211F6941999-08-27027 August 1999 Provides Individual Exam Results for Applicants That Took Initial License Exam in July & August of 1999.Completed ES-501-2,copy of Each Individual License,Ol Exam Rept, ES-303-1,ES-303-2 & ES-401-8 Encl.Without Encl NPL-99-0473, Informs of Change Being Made to Plan Third 10-year Interval ISI Long Term Plan.Change Extends Interval from Current End Date of 001130 to 020831,due to Operating Cycle Being Increased from 12 to 18 Months1999-08-27027 August 1999 Informs of Change Being Made to Plan Third 10-year Interval ISI Long Term Plan.Change Extends Interval from Current End Date of 001130 to 020831,due to Operating Cycle Being Increased from 12 to 18 Months ML20211E8791999-08-24024 August 1999 Discusses Completion of Licensing Action for GL 96-01, Testing of Safety-Related Logic Circuits, for Point Beach Nuclear Power Plant,Units 1 & 2.Licensees Provided Requested Info & Responses Required by GL 96-01 ML20211F1501999-08-24024 August 1999 Submits Summary of Meeting Held on 990729,in Region III Office with Util Re Proposed Revs to Plant Emergency Action Level Criteria Used in Classifying Emergencies & Results of Recent Improvement Initiatives in Emergency Preparedness 05000266/LER-1999-006, Forwards LER 99-006-00 Which Describes Discovery That Postulated Fire in Central Zone of Primary Auxiliary Bldg Could Result in Spurious Operation of Pressurizer Porv. New Commitments within Rept Are Indicated in Italics1999-08-19019 August 1999 Forwards LER 99-006-00 Which Describes Discovery That Postulated Fire in Central Zone of Primary Auxiliary Bldg Could Result in Spurious Operation of Pressurizer Porv. New Commitments within Rept Are Indicated in Italics NPL-99-0477, Forwards Revised Procedures to Point Beach Nuclear Plant Epips.Revised Procedures Dtd 990723,should Be Filed in NRC Copies of Manual IAW Attached Instructions1999-08-18018 August 1999 Forwards Revised Procedures to Point Beach Nuclear Plant Epips.Revised Procedures Dtd 990723,should Be Filed in NRC Copies of Manual IAW Attached Instructions NPL-99-0426, Requests Relief from Section II of ASME B&PV Code, Nuclear Vessels, 1965 Edition,No Addenda.Detailed Info Attached1999-08-16016 August 1999 Requests Relief from Section II of ASME B&PV Code, Nuclear Vessels, 1965 Edition,No Addenda.Detailed Info Attached ML20210L9141999-08-0404 August 1999 Informs That Versions of Info Re WCAP-14787,submitted in 990622 Application for Amend,Marked Proprietary,Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954,as Amended ML20210K5221999-08-0404 August 1999 Discusses Point Beach Nuclear Plant,Units 1 & 2 Response to Request for Info in GL 92-01,Rev 1,Suppl 1, Rv Structural Integrity NPL-99-0436, Forwards fitness-for-duty Performance Data for six-month Period Ending 9906301999-08-0202 August 1999 Forwards fitness-for-duty Performance Data for six-month Period Ending 990630 ML20210G6011999-07-30030 July 1999 Discusses 990415 Complaint OSHA Received from Employee of Wisconsin Electric Power Co Alleging That Employee Received Lower Performance Appraisal for 1998 Because Employee Raised Safety Concerns While Performing Duties at Point Beach NPL-99-0406, Provides Response to NRC GL 99-02, Lab Testing of Nuclear- Grade Activated Charcoal1999-07-29029 July 1999 Provides Response to NRC GL 99-02, Lab Testing of Nuclear- Grade Activated Charcoal ML20210H0211999-07-28028 July 1999 Forwards Insp Repts 50-266/99-09 & 50-301/99-09 on 990528-0713.Two Violations of NRC Requirements Occurred & Being Treated as non-cited Violations,Consistent with App C of Enforcement Policy ML20210G2441999-07-26026 July 1999 Discusses 990714 Meeting with PRA Staff to Discuss Initiatives in Risk Area & to Establish Dialog Between SRAs & PRA Staff NPL-99-0408, Forwards Pbnps,Units 1 & 2 Plant Simulation Four-Yr Rept, IAW 10CFR55.45(b)(5)(ii).Rept Describes Certification Program Tests Conducted from 1996-1999,identifies Test Discrepancies Still Outstanding & Schedules for 2000-20031999-07-15015 July 1999 Forwards Pbnps,Units 1 & 2 Plant Simulation Four-Yr Rept, IAW 10CFR55.45(b)(5)(ii).Rept Describes Certification Program Tests Conducted from 1996-1999,identifies Test Discrepancies Still Outstanding & Schedules for 2000-2003 ML20209H5471999-07-14014 July 1999 Forwards Insp Repts 50-266/99-12 & 50-301/99-12 on 990614-18.One Violation Noted,But Being Treated as non-cited violation.Long-term MOV Program Not Sufficiently Established to close-out NRC Review of Program,Per GL 89-10 NPL-99-0395, Forwards Partial Response to NRC 990512 RAI Re TS Change 204 Re Control Room Habitability.Meeting Is Planned with NRC to Discuss Issues Related to Control Room & Primary Auxiliary Bldg Ventilation Sys Modifications1999-07-12012 July 1999 Forwards Partial Response to NRC 990512 RAI Re TS Change 204 Re Control Room Habitability.Meeting Is Planned with NRC to Discuss Issues Related to Control Room & Primary Auxiliary Bldg Ventilation Sys Modifications NPL-99-0390, Projects Listed Major near-term License Amend Requests That Could Be Expected to Impact Staff Resources Into Fiscal Years 2000 & 2001,in Response to Administrative Ltr 99-021999-07-0808 July 1999 Projects Listed Major near-term License Amend Requests That Could Be Expected to Impact Staff Resources Into Fiscal Years 2000 & 2001,in Response to Administrative Ltr 99-02 NPL-99-0388, Forwards MORs for June 1999 & Revised MORs for May 1999 for Pbnps,Units 1 & 21999-07-0707 July 1999 Forwards MORs for June 1999 & Revised MORs for May 1999 for Pbnps,Units 1 & 2 NPL-99-0381, Submits Response to NRC GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. GL 98-01 Requested Response on Status of Facility Y2K Readiness by 990701.Disclosure Encl1999-06-30030 June 1999 Submits Response to NRC GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. GL 98-01 Requested Response on Status of Facility Y2K Readiness by 990701.Disclosure Encl ML20196J4161999-06-30030 June 1999 Discusses Relief Requests Submitted by Wisconsin Electric on 980930 for Pump & Valve Inservice Testing Program,Rev 5. Safety Evaluation Authorizing Relief Requests VRR-01,VRR-02, PRR-01 & ROJ-16 Encl NPL-99-0379, Documents Telcon with Hg Ashar of NRC Re Licensee Intentions & Basis for Reselection of Control Tendons in Pbnps Containment Structures.Plants Are Currently Completing 28th Year Tendon Surveillance During Summer of 19991999-06-29029 June 1999 Documents Telcon with Hg Ashar of NRC Re Licensee Intentions & Basis for Reselection of Control Tendons in Pbnps Containment Structures.Plants Are Currently Completing 28th Year Tendon Surveillance During Summer of 1999 NPL-99-0376, Forwards Errata to Pbnp 1998 Annual Monitoring Rept, Originally Submitted by Ltr Dtd 990427.List of Corrections, Provided1999-06-28028 June 1999 Forwards Errata to Pbnp 1998 Annual Monitoring Rept, Originally Submitted by Ltr Dtd 990427.List of Corrections, Provided NPL-99-0353, Forwards June 1999 Rev to FSAR for Point Beach Nuclear Plant,Units 1 & 2, IAW Requirements of 10CFR50.71(e).Each Package Contains Revised FSAR Pages That Are to Be Inserted IAW Instructions1999-06-23023 June 1999 Forwards June 1999 Rev to FSAR for Point Beach Nuclear Plant,Units 1 & 2, IAW Requirements of 10CFR50.71(e).Each Package Contains Revised FSAR Pages That Are to Be Inserted IAW Instructions ML20196D4931999-06-18018 June 1999 Forwards Insp Repts 50-266/99-08 & 50-301/99-08 on 990411- 0527.No Violations Noted.Operator Crew Response to Equipment Induced Challenges Generally Good.Handling of Steam Plume in Unit 1 Turbine Bldg Particularly Good ML20195J9471999-06-16016 June 1999 Discusses Ltr from NRC ,re Arrangements Made to Finalized Initial Licensed Operator Exam to Be Administered at Point Beach Nuclear Plant During Week of 990726 ML20196A2931999-06-16016 June 1999 Ack Receipt of Transmitting Changes to Listed Sections of Point Beach Nuclear Plant Security Plan & ISFSI Security Plan,Submitted IAW 10CFR50.54(p).No NRC Approval Is Required Since Changes Do Not Decrease Effectiveness ML20195J9251999-06-14014 June 1999 Discusses 990610 Telcon Between Wp Walker & D Mcneil Re Arrangements for NRC to Inspect Licensed Operator Requalification Program at Point Beach Nuclear Power Plant for Week of 990816 05000266/LER-1999-005, Forwards LER 99-005-00,re Failure of Shell of 4B FW Heater Which Resulted in Significant Steam Leak & Manual Trip. New Commitments within Rept Are Indicated in Italics1999-06-11011 June 1999 Forwards LER 99-005-00,re Failure of Shell of 4B FW Heater Which Resulted in Significant Steam Leak & Manual Trip. New Commitments within Rept Are Indicated in Italics NPL-99-0336, Forwards Unit 2 Refueling 23 Inservice Insp Summary Rept for Form NIS-1, IAW ASME Section Xi,Subsection IWA-62301999-06-10010 June 1999 Forwards Unit 2 Refueling 23 Inservice Insp Summary Rept for Form NIS-1, IAW ASME Section Xi,Subsection IWA-6230 NPL-99-0330, Forwards Revs to Pbnp Security Plan Sections 2.1,2.4,3.1, Figures A,D & T & Pbnp ISFSI Security Plan Section 2.0, Dtd 990604.Plans Withheld1999-06-0404 June 1999 Forwards Revs to Pbnp Security Plan Sections 2.1,2.4,3.1, Figures A,D & T & Pbnp ISFSI Security Plan Section 2.0, Dtd 990604.Plans Withheld 05000301/LER-1999-003, Forwards LER 99-003-00 for Point Beach Nuclear Plant,Unit 2. Rept Is Provided in Accordance with 10CFR50.73(a)(2)(i)(B), as Any Operation or Condition Prohibited by Plant Tech Specs1999-05-28028 May 1999 Forwards LER 99-003-00 for Point Beach Nuclear Plant,Unit 2. Rept Is Provided in Accordance with 10CFR50.73(a)(2)(i)(B), as Any Operation or Condition Prohibited by Plant Tech Specs NPL-99-0319, Provides Main Control Board Wiring Separation Project Status Update Rept for Pbnps,Units 1 & 21999-05-28028 May 1999 Provides Main Control Board Wiring Separation Project Status Update Rept for Pbnps,Units 1 & 2 ML20206T3691999-05-17017 May 1999 Ltr Contract,Task Order 242 Entitled, Review Point Beach 1 & 2 Conversion of Current TS for Electrical Power Systems to Improved TS Based on Standard TS, Under Contract NRC-03-95-026 ML20206N5561999-05-13013 May 1999 Informs That NRC Office of Nuclear Reactor Regulation Reorganized Effective 990328.As Part of Reorganization,Div of Licensing Project Mgt Created.Cm Craig Will Be Section Chief for Point Beach Npp.Organization Chart Encl ML20206P2551999-05-12012 May 1999 Forwards Handout Provided to NRC by Wisconsin Electric at 990504 Meeting Which Discussed Several Recent Operational Issues & Results of Recent Improvement Initiatives in Engineering ML20206N5331999-05-12012 May 1999 Forwards RAI Re & Suppl by Oral Presentation During 980604 Meeting,Requesting Amend for Plant,Units 1 & 2 to Revise TSs 15.3.12 & 15.4.11 ML20196F3211999-05-11011 May 1999 Requests Proprietary WCAP-14787, W Revised Thermal Design Procedure Instrument Uncertainty Methodology for Wepc Point Beach Units 1 & 2 (Fuel Upgrade & Uprate to 1656 Mwt-NSSS Power), Be Withheld from Public Disclosure ML20206K0391999-05-0707 May 1999 Forwards Insp Repts 50-266/99-06 & 50-301/99-06 on 990223- 0410.Ten Violations of NRC Requirements Occurred & Being Treated as non-cited Violations,Consistent with App C of Enforcement Policy 1999-09-08
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARNPL-99-0564, Forwards Response to NRC Request During 990720 Meeting,To Provide Addl Details to Several Questions Re Amend Currently Under Review by Staff Pertaining to CR Habitability1999-10-19019 October 1999 Forwards Response to NRC Request During 990720 Meeting,To Provide Addl Details to Several Questions Re Amend Currently Under Review by Staff Pertaining to CR Habitability 05000266/LER-1999-007, Forwards LER 99-007-00 for Point Beach Nuclear Plant,Unit 1. Condition Would Be Outside App R Design Basis for Plant.New Commitments within Rept Indicated in Italics1999-09-30030 September 1999 Forwards LER 99-007-00 for Point Beach Nuclear Plant,Unit 1. Condition Would Be Outside App R Design Basis for Plant.New Commitments within Rept Indicated in Italics NPL-99-0555, Discusses Rev 1,suppl 1 to GL 92-01, Reactor Vessel Structural Integrity. Calculation That Provides Evaluation of New Surveillance Data for Assessing Integrity of Unit 1 Reactor Vessel1999-09-29029 September 1999 Discusses Rev 1,suppl 1 to GL 92-01, Reactor Vessel Structural Integrity. Calculation That Provides Evaluation of New Surveillance Data for Assessing Integrity of Unit 1 Reactor Vessel 05000266/LER-1999-004, Forwards LER 99-004-01,re Fuel Oil Transfer Pump Cable in AFW Pump Room Being Outside App R Design Basis.Suppl to LER Provides Corrective Actions to Address Concerns Re Fire Disrupting Electrical Power to Fuel Oil Transfer Pump1999-09-0202 September 1999 Forwards LER 99-004-01,re Fuel Oil Transfer Pump Cable in AFW Pump Room Being Outside App R Design Basis.Suppl to LER Provides Corrective Actions to Address Concerns Re Fire Disrupting Electrical Power to Fuel Oil Transfer Pump NPL-99-0473, Informs of Change Being Made to Plan Third 10-year Interval ISI Long Term Plan.Change Extends Interval from Current End Date of 001130 to 020831,due to Operating Cycle Being Increased from 12 to 18 Months1999-08-27027 August 1999 Informs of Change Being Made to Plan Third 10-year Interval ISI Long Term Plan.Change Extends Interval from Current End Date of 001130 to 020831,due to Operating Cycle Being Increased from 12 to 18 Months 05000266/LER-1999-006, Forwards LER 99-006-00 Which Describes Discovery That Postulated Fire in Central Zone of Primary Auxiliary Bldg Could Result in Spurious Operation of Pressurizer Porv. New Commitments within Rept Are Indicated in Italics1999-08-19019 August 1999 Forwards LER 99-006-00 Which Describes Discovery That Postulated Fire in Central Zone of Primary Auxiliary Bldg Could Result in Spurious Operation of Pressurizer Porv. New Commitments within Rept Are Indicated in Italics NPL-99-0477, Forwards Revised Procedures to Point Beach Nuclear Plant Epips.Revised Procedures Dtd 990723,should Be Filed in NRC Copies of Manual IAW Attached Instructions1999-08-18018 August 1999 Forwards Revised Procedures to Point Beach Nuclear Plant Epips.Revised Procedures Dtd 990723,should Be Filed in NRC Copies of Manual IAW Attached Instructions NPL-99-0426, Requests Relief from Section II of ASME B&PV Code, Nuclear Vessels, 1965 Edition,No Addenda.Detailed Info Attached1999-08-16016 August 1999 Requests Relief from Section II of ASME B&PV Code, Nuclear Vessels, 1965 Edition,No Addenda.Detailed Info Attached NPL-99-0436, Forwards fitness-for-duty Performance Data for six-month Period Ending 9906301999-08-0202 August 1999 Forwards fitness-for-duty Performance Data for six-month Period Ending 990630 NPL-99-0406, Provides Response to NRC GL 99-02, Lab Testing of Nuclear- Grade Activated Charcoal1999-07-29029 July 1999 Provides Response to NRC GL 99-02, Lab Testing of Nuclear- Grade Activated Charcoal NPL-99-0408, Forwards Pbnps,Units 1 & 2 Plant Simulation Four-Yr Rept, IAW 10CFR55.45(b)(5)(ii).Rept Describes Certification Program Tests Conducted from 1996-1999,identifies Test Discrepancies Still Outstanding & Schedules for 2000-20031999-07-15015 July 1999 Forwards Pbnps,Units 1 & 2 Plant Simulation Four-Yr Rept, IAW 10CFR55.45(b)(5)(ii).Rept Describes Certification Program Tests Conducted from 1996-1999,identifies Test Discrepancies Still Outstanding & Schedules for 2000-2003 NPL-99-0395, Forwards Partial Response to NRC 990512 RAI Re TS Change 204 Re Control Room Habitability.Meeting Is Planned with NRC to Discuss Issues Related to Control Room & Primary Auxiliary Bldg Ventilation Sys Modifications1999-07-12012 July 1999 Forwards Partial Response to NRC 990512 RAI Re TS Change 204 Re Control Room Habitability.Meeting Is Planned with NRC to Discuss Issues Related to Control Room & Primary Auxiliary Bldg Ventilation Sys Modifications NPL-99-0390, Projects Listed Major near-term License Amend Requests That Could Be Expected to Impact Staff Resources Into Fiscal Years 2000 & 2001,in Response to Administrative Ltr 99-021999-07-0808 July 1999 Projects Listed Major near-term License Amend Requests That Could Be Expected to Impact Staff Resources Into Fiscal Years 2000 & 2001,in Response to Administrative Ltr 99-02 NPL-99-0388, Forwards MORs for June 1999 & Revised MORs for May 1999 for Pbnps,Units 1 & 21999-07-0707 July 1999 Forwards MORs for June 1999 & Revised MORs for May 1999 for Pbnps,Units 1 & 2 NPL-99-0381, Submits Response to NRC GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. GL 98-01 Requested Response on Status of Facility Y2K Readiness by 990701.Disclosure Encl1999-06-30030 June 1999 Submits Response to NRC GL 98-01, Y2K Readiness of Computer Sys at Nuclear Power Plants. GL 98-01 Requested Response on Status of Facility Y2K Readiness by 990701.Disclosure Encl NPL-99-0379, Documents Telcon with Hg Ashar of NRC Re Licensee Intentions & Basis for Reselection of Control Tendons in Pbnps Containment Structures.Plants Are Currently Completing 28th Year Tendon Surveillance During Summer of 19991999-06-29029 June 1999 Documents Telcon with Hg Ashar of NRC Re Licensee Intentions & Basis for Reselection of Control Tendons in Pbnps Containment Structures.Plants Are Currently Completing 28th Year Tendon Surveillance During Summer of 1999 NPL-99-0376, Forwards Errata to Pbnp 1998 Annual Monitoring Rept, Originally Submitted by Ltr Dtd 990427.List of Corrections, Provided1999-06-28028 June 1999 Forwards Errata to Pbnp 1998 Annual Monitoring Rept, Originally Submitted by Ltr Dtd 990427.List of Corrections, Provided NPL-99-0353, Forwards June 1999 Rev to FSAR for Point Beach Nuclear Plant,Units 1 & 2, IAW Requirements of 10CFR50.71(e).Each Package Contains Revised FSAR Pages That Are to Be Inserted IAW Instructions1999-06-23023 June 1999 Forwards June 1999 Rev to FSAR for Point Beach Nuclear Plant,Units 1 & 2, IAW Requirements of 10CFR50.71(e).Each Package Contains Revised FSAR Pages That Are to Be Inserted IAW Instructions 05000266/LER-1999-005, Forwards LER 99-005-00,re Failure of Shell of 4B FW Heater Which Resulted in Significant Steam Leak & Manual Trip. New Commitments within Rept Are Indicated in Italics1999-06-11011 June 1999 Forwards LER 99-005-00,re Failure of Shell of 4B FW Heater Which Resulted in Significant Steam Leak & Manual Trip. New Commitments within Rept Are Indicated in Italics NPL-99-0336, Forwards Unit 2 Refueling 23 Inservice Insp Summary Rept for Form NIS-1, IAW ASME Section Xi,Subsection IWA-62301999-06-10010 June 1999 Forwards Unit 2 Refueling 23 Inservice Insp Summary Rept for Form NIS-1, IAW ASME Section Xi,Subsection IWA-6230 NPL-99-0330, Forwards Revs to Pbnp Security Plan Sections 2.1,2.4,3.1, Figures A,D & T & Pbnp ISFSI Security Plan Section 2.0, Dtd 990604.Plans Withheld1999-06-0404 June 1999 Forwards Revs to Pbnp Security Plan Sections 2.1,2.4,3.1, Figures A,D & T & Pbnp ISFSI Security Plan Section 2.0, Dtd 990604.Plans Withheld NPL-99-0319, Provides Main Control Board Wiring Separation Project Status Update Rept for Pbnps,Units 1 & 21999-05-28028 May 1999 Provides Main Control Board Wiring Separation Project Status Update Rept for Pbnps,Units 1 & 2 05000301/LER-1999-003, Forwards LER 99-003-00 for Point Beach Nuclear Plant,Unit 2. Rept Is Provided in Accordance with 10CFR50.73(a)(2)(i)(B), as Any Operation or Condition Prohibited by Plant Tech Specs1999-05-28028 May 1999 Forwards LER 99-003-00 for Point Beach Nuclear Plant,Unit 2. Rept Is Provided in Accordance with 10CFR50.73(a)(2)(i)(B), as Any Operation or Condition Prohibited by Plant Tech Specs ML20196F3211999-05-11011 May 1999 Requests Proprietary WCAP-14787, W Revised Thermal Design Procedure Instrument Uncertainty Methodology for Wepc Point Beach Units 1 & 2 (Fuel Upgrade & Uprate to 1656 Mwt-NSSS Power), Be Withheld from Public Disclosure NPL-99-0242, Submits Commitment Schedule Update,Per GL 95-07 Re Pressure Locking & Thermal Binding of safety-related power-operated Gate Valves.Unit 1 Block Valve Replacement Will Be Performed During Upcoming 1999 U1R25 Outage1999-04-27027 April 1999 Submits Commitment Schedule Update,Per GL 95-07 Re Pressure Locking & Thermal Binding of safety-related power-operated Gate Valves.Unit 1 Block Valve Replacement Will Be Performed During Upcoming 1999 U1R25 Outage NPL-99-0246, Forwards 1998 Annual Monitoring Rept, for Pbnps Units 1 & 2.Revised ODCM & Environ Manual Are Encl1999-04-27027 April 1999 Forwards 1998 Annual Monitoring Rept, for Pbnps Units 1 & 2.Revised ODCM & Environ Manual Are Encl ML20206C2361999-04-22022 April 1999 Forwards 1998 Annual Rept to Stockholders of Wepc Which Includes Certified Financial Statements,Per 10CFR50.71 NPL-99-0230, Submits Clarification of Which Portions of OMa-1988 Parts 6 & 10 Are Being Utilized at Pbnp for IST Program Implementation & Cold SD & RO Justifications,Per 990218 Telcon with NRC1999-04-19019 April 1999 Submits Clarification of Which Portions of OMa-1988 Parts 6 & 10 Are Being Utilized at Pbnp for IST Program Implementation & Cold SD & RO Justifications,Per 990218 Telcon with NRC 05000301/LER-1999-002, Forwards LER 99-002-00 Re Discovery That Cable Necessary to Provide Plant Parameter Required to Be Monitored for App R Safe SD Location Was Not Routed Independent of Appropriate Fire Zone.Commitments in Rept Indicated in Italic1999-04-16016 April 1999 Forwards LER 99-002-00 Re Discovery That Cable Necessary to Provide Plant Parameter Required to Be Monitored for App R Safe SD Location Was Not Routed Independent of Appropriate Fire Zone.Commitments in Rept Indicated in Italics NPL-99-0219, Provides Final Notification of Change to Commitments Documented in LER 266/97-022-00 Re Electrical Short Circuits During CR Fire1999-04-15015 April 1999 Provides Final Notification of Change to Commitments Documented in LER 266/97-022-00 Re Electrical Short Circuits During CR Fire 05000266/LER-1999-001, Forwards LER 99-001-01,describing Discovery That Common Min Recirculation Flow Line Return to RWST for Safety Injection & Containment Spray Pumps Was Partially Frozen & Would Not Pass Flow.New Commitments Indicated in Italics i1999-04-0808 April 1999 Forwards LER 99-001-01,describing Discovery That Common Min Recirculation Flow Line Return to RWST for Safety Injection & Containment Spray Pumps Was Partially Frozen & Would Not Pass Flow.New Commitments Indicated in Italics in Rept NPL-99-0174, Confirms Completion of Requested Actions in Accordance with Required Response of GL 96-01 for Unit 2.Confirmation of Completion for Unit 1 Was Provided in Ltr Npl 98-0591,dtd 9807141999-03-30030 March 1999 Confirms Completion of Requested Actions in Accordance with Required Response of GL 96-01 for Unit 2.Confirmation of Completion for Unit 1 Was Provided in Ltr Npl 98-0591,dtd 980714 ML20206B8231999-03-30030 March 1999 Forwards Final Exercise Rept for Biennial Radiological Emergency Preparedness Exercise Conducted on 981103 for Point Beach Power Plant.One Deficiency Identified for Manitowoc County.County Corrected Deficiency Immediately NPL-99-0177, Forwards Decommissioning Funding Status Info for Pbnp,Units 1 & 2,per 10CFR50.751999-03-30030 March 1999 Forwards Decommissioning Funding Status Info for Pbnp,Units 1 & 2,per 10CFR50.75 05000301/LER-1999-001, Forwards LER 99-001-00,re Loss of Safeguards Electrical Bus During Refueling Surveillance Testing Which Resulted in Temporary Unavailability of One Train of Decay Heat Removal. Commitments Made by Util Are Identified in Italics1999-03-10010 March 1999 Forwards LER 99-001-00,re Loss of Safeguards Electrical Bus During Refueling Surveillance Testing Which Resulted in Temporary Unavailability of One Train of Decay Heat Removal. Commitments Made by Util Are Identified in Italics NPL-99-0122, Forwards Relief Requests RR-1-19 & RR-2-25,requesting Relief from Section XI of ASME B&PV Code, Rules for Inservice Exam of NPP Components, 1986 Edition,No Addenda.Requirements for Relief Apply to Third ten-yr ISI Interval for Units 1 &1999-03-0303 March 1999 Forwards Relief Requests RR-1-19 & RR-2-25,requesting Relief from Section XI of ASME B&PV Code, Rules for Inservice Exam of NPP Components, 1986 Edition,No Addenda.Requirements for Relief Apply to Third ten-yr ISI Interval for Units 1 & 2 NPL-99-0111, Informs NRC That IAW Provisions of ASME Boiler & Pressure Code,Section Xi,Paragraphs IWA-2430(d) & IWA-2430(e),WEPC Has Extended Third 10 Yr Interval for Pressure Testing Program at Pbnp,Unit 1 by 21 Months1999-03-0303 March 1999 Informs NRC That IAW Provisions of ASME Boiler & Pressure Code,Section Xi,Paragraphs IWA-2430(d) & IWA-2430(e),WEPC Has Extended Third 10 Yr Interval for Pressure Testing Program at Pbnp,Unit 1 by 21 Months NPL-99-0116, Forwards Proprietary & non-proprietary Revised Point Beach Nuclear Plant Emergency Plan IAW 10CFR50.54(q).Proprietary Plan Withheld1999-03-0101 March 1999 Forwards Proprietary & non-proprietary Revised Point Beach Nuclear Plant Emergency Plan IAW 10CFR50.54(q).Proprietary Plan Withheld NPL-99-0115, Forwards Proprietary & non-proprietary Revised EPIPs to Point Beach Nuclear Plant,Units 1 & 21999-03-0101 March 1999 Forwards Proprietary & non-proprietary Revised EPIPs to Point Beach Nuclear Plant,Units 1 & 2 NPL-99-0114, Provides Results of Wepcs Insp,Replacement & Mechanical Testing of Reactor Internals Baffle Former Bolts During Recent Point Beach Refueling Outage1999-02-25025 February 1999 Provides Results of Wepcs Insp,Replacement & Mechanical Testing of Reactor Internals Baffle Former Bolts During Recent Point Beach Refueling Outage NPL-99-0086, Documents Commitment Change Which Is to Discontinue Actions Contained in Util Ltr Dtd 970613,after NRC Approval of LAR & Lower Containment Leak Rate Limit Is Implemented. Change Is Acceptable IAW Applicable Plant Procedure1999-02-24024 February 1999 Documents Commitment Change Which Is to Discontinue Actions Contained in Util Ltr Dtd 970613,after NRC Approval of LAR & Lower Containment Leak Rate Limit Is Implemented. Change Is Acceptable IAW Applicable Plant Procedure NPL-99-0101, Forwards Proprietary & non-proprietary Version of Rev 20 to EPIP 3.2, Emergency Response Organization Notification & Revised Index.Proprietary Info Withheld1999-02-19019 February 1999 Forwards Proprietary & non-proprietary Version of Rev 20 to EPIP 3.2, Emergency Response Organization Notification & Revised Index.Proprietary Info Withheld ML20203F7301999-02-10010 February 1999 Forwards Revs to Security Plan Sections 1.2,1.3,1.4,2.1,2.5, 2,6,2.8,6.1,6.4,6.5,B-3.0,B-4.0,B-5.0 & Figure R Dtd 990210. Evaluation & Description of Plan Revs Also Encl to Assist in NRC Review.Encls Withheld NPL-99-0067, Submits 30 Day Rept of Changes & Errors Discovered in ECCS Evaluation Models for Pbnp,Unit 21999-02-0202 February 1999 Submits 30 Day Rept of Changes & Errors Discovered in ECCS Evaluation Models for Pbnp,Unit 2 NPL-99-0064, Forwards Revised TS Bases Page 15.4.4,correcting References to Pbnp FSAR Re Reactor Containment Design.Changes Are Administrative Only & Do Not Alter Facility or Operation,As Described in FSAR or Any TS Requirement1999-02-0202 February 1999 Forwards Revised TS Bases Page 15.4.4,correcting References to Pbnp FSAR Re Reactor Containment Design.Changes Are Administrative Only & Do Not Alter Facility or Operation,As Described in FSAR or Any TS Requirement NPL-98-1032, Forwards Revs to Pbnp Security Plan Sections 1.1,1.2,2.1, 2.6,2.8,6.1 & 6.4 & Revs to Pbnp ISFSI Security Plan Sections 1.0 & 7.0,per 10CFR50.54(p).Encl Withheld1999-01-27027 January 1999 Forwards Revs to Pbnp Security Plan Sections 1.1,1.2,2.1, 2.6,2.8,6.1 & 6.4 & Revs to Pbnp ISFSI Security Plan Sections 1.0 & 7.0,per 10CFR50.54(p).Encl Withheld 05000266/LER-1998-029, Forwards LER 98-029-00,describing Discovery of Isolation of Autostart Feature for Svc Water Pumps from Unit 2,safeguards Buses During Modifications1999-01-26026 January 1999 Forwards LER 98-029-00,describing Discovery of Isolation of Autostart Feature for Svc Water Pumps from Unit 2,safeguards Buses During Modifications NPL-99-0031, Informs That Wepc Reviewed Contents of NEI to NRC & Have Verified Info Provided in Ltr Pertaining to WOG Member Plants Is Applicable to Pbnp.Attachment Responds to NRC Questions by Ref to Info in 981211 NEI Ltr1999-01-15015 January 1999 Informs That Wepc Reviewed Contents of NEI to NRC & Have Verified Info Provided in Ltr Pertaining to WOG Member Plants Is Applicable to Pbnp.Attachment Responds to NRC Questions by Ref to Info in 981211 NEI Ltr NPL-99-0004, Provides Status Update on Program Activities & Schedule for Final Resolution of Items Re Verification of Seismic Piping Class Interfaces for Point Beach Nuclear Plant,Units 1 & 21999-01-11011 January 1999 Provides Status Update on Program Activities & Schedule for Final Resolution of Items Re Verification of Seismic Piping Class Interfaces for Point Beach Nuclear Plant,Units 1 & 2 NPL-99-0012, Forwards Proprietary & Nonproprietary Revs to Epips. Proprietary Version of EPIPs Withheld1999-01-0808 January 1999 Forwards Proprietary & Nonproprietary Revs to Epips. Proprietary Version of EPIPs Withheld 1999-09-30
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e Wisconsin Electnc POWER COMPMN m w Mc89voc occ4suvur-auntit mumi ne VPNPD 37 5 NRC 12 4 October 28, 1991 Document Control Desk U. S. NUCLEAR REGULATORY COMMISSION Mail _ station Pi-137 Washington, DC 20555 Gentlemen:
DQCKET NOS. 50-266 AND 5.9.1.q1 lifffQllSE TO GIHERLCJETTER 91-D1 AD10UACY OP_ SAFETY-REIATED _ DC POliER SUPPLIES POINT ltFACH NUCLEh8 PLAllTm UNITS 1 k_2 NRP Generic Lotter (GL) 91-06, dated April 29, 1991, requested that licenuces answer a series of questions regarding the adequacy of nafety-related do power supplies. An enclosure to GL 91-06 listed the specific questions to which we were to respond. Attachment 1 to'this letter provides our response to al? questions that were included in the enclosure to GL 91-06.
Please contact us if you have any questions concerning the information provided in this response. _
Veryqtruly yours, /
% No "
Jamt . J.=Zach Vico President Nuclear Power Copy to: NRC Resident Inspector NRC Regional Administratou Subscribed and sworn to before me this2v0 day of /A\ ybc . , 1991.
.t at w / k rs -t t+a
_ Notary Public, StatY of Wisconsin
'My Commission expires G - 2 ? '/ Z. :-.
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ATTACHMENLA The following information, regarding the adequacy of cafety-related de power nupplien at Point Beach Nuclear Plant, Unita 1 and 2, is provided in renponre to Generic 1,etter (Gb) 91-06. GI, 91-06 requented that licensees renpond to a serien of questions that were provided an Enclosure 1 to the generic letter. Our renponne to each of the subject quentionn in detailed below.
Figures 8.2.8, 8.2.9, 8.2.10, and 8.2.11 in the Point Beach Pinal Safety Analynis Report (PSAR) are electrical schematica of point Beach electrical syntems. These figuren uhould be consulted to provido a description of the basic de syntom configuration.
- 1. U n i t s .L.o n(LL ._l'pj nt_hcAch_ N y tlea r_l'liu1L t
- 2. a. The number of independent redundant divisions of Class 1E or safety-related de power for the plant, is t w o_,_
Two battery buses are used to supply each of the two safety-related dc power divisions. The iirot division of dc power, which in designated "A" train, in aupplied by station battery busco D01 and D03. The redundant division of de poser, which in designated "B" train, in powered by station battery busen 002 and D04. *l t ene redundant divisions of de power are independent.
- b. The number of functional satoty-related divisions of de power necessary to attain safe shutdown for this unit is gne t
- 3. Does the control room at this unit have the following separate, independently annunciated alarms and indications for each division of de power?
The below linted annunciatora provide indications in the control room for the name de power train from which they are powered, no the annunciatorn are not independently energized. Consequently, upon loan of an entire de power train all unnunciators anuociated with that train Will also lose power. Each train, however, han an independent lous of power annunciator that la powered by 120V ac power. This design war established to provide independence of the de bunen and to ensure that the loss of power to one de train would not affect the operation of the second de train.
- a. alarms
- 1. Dattery dinconnect or circuit breaker open? _.yepu Two train specific annunciatorn are provided in the control room to alarm when their annociated
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battery breakern open. One annunciator nerven the "A" train battery breakern (for batterieu DOS and D105) and the necond annunciator serven the "h" train battery breakern (for batterien D06 and D106). Upon receipt of the annunciator alarm, the operator must check the control room battery breaker statun 11ghts to determine which breaker han opened.
- 2. Dattery charger disconnect or circuit broaker open (both input ac and output dc)? ,_ _H h _
The position of the ac input breaker to the battery charger is not monitored by an annunciator circuit. Instead, an undervoltage sensor on the ac input to each battery charger will canno the renpective battery charger trouble annunciator to alarm when the ac input power in lont. The ac undervoltage coil will adequately alert the operator upon the lona of ac power into the charger.
The battery charger de output breakern, which are installed within the battery charger cabinet, have contactn installed that will cauno the battery charger trouble annunciator to alarm woon tlm breaker openn.
A neparate breaker in installed in serien in between each battery charger de output breaker and its renpoetive de bus. These breakern are located in the anccciated de bun cabineta (D01, D02, D03, and D04). There are no alatms annociated with thene breakern. In the control r o o ") , however, there in currently breaker position indication for the de input breakers to the D03 and D04 bunen.
Additionally, au part of our de syntem upgrado, which will involve the addition of a nafety-related swing battery, we are planning to install control room breaker position indication for the de input breakers to the D01 and D02 banon. This modification in scheduled to be completed in mid-1993.
- 3. DC system ground? _,_Yres _
A de ground will cause the battery charger trouble annunciator to alarm. Because the de ground detection cir.:uitry in an integral part of the battery charger circuitry, the ground detector in available only when the battery charger in on line. We believe that this ground detection
_2
capability is adequate because the de buses are normally energized by a battery charger at all times.
- 4. DC bus undervoltage? Yes.
Two annunciators are provided for de system
> undervoltage. One serves the "A" train (D01 and D03 buses), and tne other serves "B" train (D02 and D04 buses). Upon receipt of the alarm, the operator must use the associated control room bus voltmeters to determine which bus has the low voltage condition.
The D03 and 004 dc bus undervoltage coils sense voltage dire .ly on the D03 and D04 buses, respeccively.
The D01 and D02 de bus voltage is sensed by undervoltage coils that are on the D11 and D13 buses, respectively. Because D11 and D13 buses are energized by the D01 and D02 buses, respectively, we believe that this undervoltage annunciation is adequate for the D01 and D02 buses. We are, however, currently investigating the feasibility of installing control room undervoltage annunciators that sense voltage directly on the D01 and D02 buses.
- 5. DC bus overvoltage? Yes.
Two annunciators are provided for de system overvoltage. One serves the "A" train (D01 and D03 busea), and the other serves "B" train (D02 -
and 004 buses). Upon receipt of the alarm, the operator must use the associated control room bus voltmeters to determine whir aus has the overvoltage condition.
The D03 and D04 de bus overvoltage coils sense voltage directly on the D03 and D04 buses, respectively.
The D01 and D02 dc bus voltage is sensed by overvoltage coils that are on the D11 and D13 buses, respectively. Because D11 and D13 buses are energized by the D01 and D02 buses, respectively, we believe that this overvoltage annunciation is adequate for the D01 and D02
buses. We are, however, currently investigating the feasibility of installing cont rol room overvoltage nnnunciatora that nrna voltage directly on 1.he n01 a C D02 bus s
- 6. Battery charger failuro? Ves.
?. Dattery discharge? !{g, No battery discharge annunciators are installed.
A charge / discharge ammeter, however, is installed in the control room for each battery. This meter -
will indicate a discharge when the battery in nupplying its respective bun.
If the bette.y charger doea fall, resulting in a battery dicchargo, the operator will normally be alerted by the battery charger troubic annunciator. Additionally, the de bun undervoltage annunciators are set to alarm at a voltage slightly below the normal f' oat voltage of -
the charger / battery. Consequently, the de bus undervoltage annunciator will alarm shortly after its respective battery begins to discharge. The battery charger output voltage le normally set at approximately 134 volta. The D01 and D02 undervoltage annunciator alarma at 128 volto and the D03 and LO4 undervoltage annunciator alarms at 131 volts.
- b. Indications
- 1. Battery float charge current? Yng.
This battery charge / discharge ammeter is a wide range meter that shows the current flow into or out of the battery. While the battery la on a float, the meter will indicate a smal) current flow into the battery. The meter, however, is calibrated and scaled for the large discharge currents that would be expacted if the charger failed and the battery was supplying all of the de loads. Consequently, because the scale on the charging side of the meter is so Inrgo, operators are unable to quantitatively measure the magnitude of the relatively small charging currents.
Nonetheless, the small deflection of the meter is adequate to allow operators to qualitatively determine whether or not the battery is on a floot.
-4 I_ _ _ _ _ . . ___ _ . . _ _ _ _ ._______ _____ -.________.________ _ ____ _____ _ ___ _ _ _
We do not maint ain battery floatn by establinhing a specific float current. Inntead, our battery floatn are entablinhed by maintaining a specific battery charger or.tput voltage. To maintain the proper float current, the charger output voltage in readjusted monthly baned on the temperature of the pilot cell.
- 2. TVIary circuit output current? Y e p.,
An doneribed in question 3.b.1 above, a battery charyo/ discharge meter in provided in the control room. This meter will give an accurate indication of the battery bun current if the battery in supplying power to the de bus.
- 3. Dattery discharge? _ _Yenn_._
An doncribed in quention 3.b.1 above, a battery charge /dincharge ammeter in provided in the control room.
- 4. Dus voltage? Yea, The D03 and D04 bunen have voltmetern located in the control room that nenne voltage directly on the respective bunen.
The D01 and D02 bunen do not have voltmeters that sense voltage directly from the respective bunen.
Instead, voltmeters are provided in the control room for the D11 and D13 bunen, which are supplied by the D01 and D02 bunen respectivolv. If the input breakern to the D11 or D13 b s are opened, voltage indication for the respe- '
c.ource bun will be loc.t. Nonethclenn, the
- 4 .m' D13 voltmetern provide an accurate c w.lon of the voltagen on the D01 and D02 bunen .aapectively.
We are, however, currently investigating the fennibility o; installing control room overvoltage annunciatorn that nenne voltage directly on the D01 and D02 bunen.
- c. Does the unit have written procedures for renponso to the above alarms and indications? Yes2 The Alarm Response Book describen the renponse to individual annunciators and refern operatorn to the atpropriate proceduren. Although no proceduren are written specifically for the above mentioned indicationn, abnormalition in these indicationn are adequately addrenced in our operation and maintenance proceduren.
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- 4. 'Does the unit have indication of bypassed and inoperable status of circuit breakers or other devices that can be used to disconnect the battery and battery charger from its do bus and the battery charger from its ac power source during maintenance or testing? Yes The battery breakers have position indications in the control room, opening the de output breakers of the battery charger will cause the battery charger trouble annunciator to alarm. As described in question 3.a.2 above, opening the ac input breaker to the charger will cause the battery charger trouble annunciator to alarm due to the resulting ac undervoltage condition.
As described in question 3.a.2 above, the de input breakers to the D03 and D04 buses have position indicators in the control room. Additionally, we are planning to install position indicators in the control room for the dc input breakers to the D01 and D02 buses.
- 5. If the answer to any part of question 3 or 4 is no, then provide information justifying the existing design features of the facility's safety-related de systems.
See the individual questions abo _ve.
- 6. a. Have you conducted a review of maintenance and testing activities to minimize the potential for human error causing more than one de division to be unavailable?
No.
We currently do not have any operational or maintenance procedures that make a division of de power unavailable. Consequently, we have not conducted a review of maintenance and testing activities to minimize the potential for human error causing more than one dc division to become unavailable. The procedure for paralleling battery chargers, however, has been written to preclude the inadvertent loss of a division of de power.
We are currently planning to install a swing safety-related battery by mid-1993. This project is described below in more detail in our responce to question 7.c.4.
As part of this installation we will be upgrading associated procedures that involve the de system. As we rewrite these procedures, we will incorporate human engineering factors to minimize the potential for human errors.
l
'b. Do plant procedures prohibit maintenance or testing on redundantado divisions at the same time? l{p .
Current plant maintenance does not' result in the doonorgization of a de power division. Consequently, our procedures do not specifically prohibit maintenance on redundant de divisions of power. Wo would not,
-however, typically perform maintenance on redundant de divisions at the same time.
- 7. Are maintenance, surveillance and test procedures regarding station-batteries conducted routinely at this plant?
specifically:
a.- At least once per 7 days are the f d 'owing verified to be within acceptable limits:
At Point Beach, monthly battery maintenanco is performed in accordance with the requirements for i monthly maintenance found in ANSI /IEEE Std 450-1987, the Point'Boach Technical Specifications, and the manufacturer's recommendations. All of the maintenanco:
described in this question 10 included in our monthly battery maintenance proceduro. Wo believe that the monthly periodicity for this maintenance is adequato and that it providos us with sufficient scatus of the battery condition. q i
- 1. Pilot cell electrolyte level? No .
Pilot cell electrolyto lovel is checked during monthly maintenance.
- 2. Specific gravity or charging current? No .
Pilot coll specific gravity is checked during monthly maintenance.
- 3. -Float voltage? No .
The float voltage is checked during monthly maintenance. Additionally,-during the monthly maintenanco, a new float voltage is determined based on the temperature of the pilot coll. The float voltage is then roadjusted as necessary, d
- 4. Total bus voltags on float chargo7 Mo .
Total battery voltage is determined during monthly maintenance.
_.~
- 5. The float voltage of each cell? No .
9 The voltage of each cell is measured during monthly maintenance.
- 6. Visually inspect or measure resistance of terminals and connectors (including the connectors at the do bus)? No .
Each month all battery connections (including -
cable to lug connections) are checked for excessive corrosion or deterioration. Battery cells are also chceked for signs of leakage and cracks.
- b. At least once per 92 days, or within 7 days after a battery discharge, overcharge, or if the pilot cell readings are outside the day surveillance requirements are the following verified to be within acceptable limits:
At Point Beach, the following battery maintenance is performed on a monthly or quarterly basis. Our Technical Specifications, however, do not require us to perform this maintenance after a discharge, overcharge, or if the pilot cell readings are outside the monthly surveillance requirements. Nonetheless, our-procedures require us to investigate and correct problems when readings are outside normal specifications'. In such cases, our good engineering practices would dictate that-we conduct-the quarterly maintenance, as appropriate.
- 1. Electrolyte level of each cell? No.
-This-is performed on a quarterly basis only.
C. The average specific gravity of all cells? No.
This is performed on a quarterly basis only.
3 . -- The specific gravity of each cell? No.
l This-is performed on'a quarterly bacis only..
- 4. The average electrolyte temperature of a representative number of cells? No.
This is performed on a quarterly basis only.
_ g.
=gyyy gm
4
- 5. The float voltage of each cell? __Not Thin in portormed on a monthly banin only.
- 6. Visually innpect or measure resintance of terminals and connectors (including the connootors at the do bun)? No,_
The vluuni innpoetion in performed on a monthly banin. Tho roulutanco mennuromonto of terminnlo and connector i nro performed on an nnnuni bania.
- c. At loant ovary la months are the fe'. lowing verified
- 1. Low resistance of each connection (by tout)?
12On-Thic tout in conducted annually.
- 2. Physical condition of the battery? Ypa t__
The phynical condition of the Enttery in checkod during both the monthly and quarterly maintenanco.
- 3. Battery charger capability to deliver rated ampore output to the do bus? _ Nq, Wo are currently purnuing tho fonulbility of purchasing a land tout call that would allow un to perform charger capacity touting.
- 4. The capability of the battery to deliver its design duty cycle to ti.e do bun? _ _ Ngu _
We currently do not perform thin toat on a periodic bania. The tonting would involvo the manual dinconnection of the bnttory, connection of the battery to n ronintor bank, and the subsequent tonting, rocharging, and reconnection of the battery. Unned on our experience with touting bnttoriou DIOS and D106 in 19119 (72-hour LCO'n),
we determined that tonting of thin naturo cannot
.o completed within the 24-hour LCO currently upocifiod for batterion DOS and D06. We nre planning to install n fifth nnfoty-related swing battery that will allow un to tnko one battery off-lino to conduct battery nervice tenta.
By letter dated May 10, 1991, we proposed a change to the point llench Technlen1 Spocificatlona that includon a now ourvallianco requiremont for o battory acrvice tout that in to be conducted ovory
18 monthn. Thin tent will verify that the battery capacity in adequate to nupply and maintain in operable statun all of the actual or nimulated emergency londo for the design duty cycle. Thin nervice tenting in to begin nubsequent to the mid-1993 inntallation of the swing natety-related battery. We conducted the S-year required performance tents f or batterien D10's and D106 in tall 1989 (they were installed in 1984), and wo installed batterien D05 and D06 in 1989. An indicated in our May 10, 1991 letter, because of the relative newncon of the batterien, we bellove that it in acceptable to delay further battery nervice tenting until the owing nafety-related battery in inntalled.
- 5. Each individual call voltage is within acceptablo limito during the service tost? __t{m__
Ao part of the nervice tent that we are planning to establish (an discunned in question 7.c.4 above), individual cell voltagen will be monitored for acceptability during the tent.
- d. At least ovary 60 months, is capability of each battery verified by performance of a dischargo test? ,_ _ lea,_
natterien D10S and D106 were tested in 1989, five yearu after their installation. Because batterien DOS and D06 were not installed until 1989, they have not yet been tested other than their initial acceptance tent in 1989.
- o. At least annually, is the battery capacity verifiod by performanco discharge test, if the battery shows signs of degradation or has reached 85% of the cupacted servico life? ___R h In our Technical Specification change requent, dated May 10, 1991, we propound a new surveillance requirement that will require un to perform the discharge tent annually on a battery that shows signs of degradation or that han reached 85% of its nervice lite. This requirement in to be implemented subsequent to the installation of the noing nafety-related battery.
- 8. Does this plant have operational features such that following loss of one safety-related de power supply or bust
- a. capability is maintaino$ for ensuring continued and adequato reactor cooling? _ _ yew _ _ _
-in-
- . . - _ _ _ _ _ . _ _ _ ~ _ _ _ ._
At Point Beach there are two redundant de systems. As
_a-result,-_the loss of.one safety-related do power supply will not affect our ability to maintain reactor cooling.
- b. Reactor coolant system _ integrity and' isolation capability are maintained? Yes.
At Point Beach there are two redundant de systems. As a result, the loss of one safety-related de power supply will'not affect reactor coolant system integrity
'and isolation,
- c. Operating procedures, instrumentation (including indicators and annunciators), and control functions are
-adequate to initiate systems as required to maintain adequate _ core cooling. Yes.
-At Point-Beach there are two redundant de systems. As a result. the loss of one safety-related de power supply will'not affect our ability to initiate core cooling.
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- 9. If the answer to any part of question 6, 7 or 8 is no, then ,
provide your basis for not performing the maintenance, surveillance and test procedures described and/or the bases
'for not including the operational features cited.
See individual questions above.
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- . _ _ , _ .