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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
[Table view] Category:UTILITY TO NRC
MONTHYEARML20059H9391990-09-13013 September 1990 Forwards Amended Response to Notice of Violations Noted in Insp Repts 50-266/89-27 & 50-301/89-26.Corrective Action: Revised Procedures Will Not Be Issued Until After Unit 2 Refueling Outage.Other Changes Anticipated by 901231 ML20059G7211990-09-0505 September 1990 Responds to Generic Ltr 90-03, Vender Interface for Safety- Related Components. Implementing Formal Vendor Interface Program for Every safety-related Component Impractical ML20028G9071990-08-31031 August 1990 Advises That long-term erosion/corrosion-induced Program for Pipe Wall Thinning in Place,Per Generic Ltr 89-08.Program Assures Erosion/Corrosion Will Not Lead to Degradation of Single & two-phase High Energy Carbon Steel Sys ML20059G8741990-08-31031 August 1990 Forwards Revised Security Plan,Per NRC .Summary of Revs Listed.Rev Withheld (Ref 10CFR3,50,70 & 73) ML20064A4711990-08-29029 August 1990 Forwards Semiannual Monitoring Rept,Jan-June 1990, Rev 1 to Process Control Program, Rev 7 to Environ Manual & Rev 5 to Odcm ML20058N6771990-08-0303 August 1990 Forwards Public Version of Revised Procedures to Emergency Plan manual.W/900813 Release Memo ML20058L1471990-08-0303 August 1990 Responds to NRC Re Weaknesses Noted in Insp Repts 50-266/90-201 & 50-301/90-201 Re Electrical Distribution. Corrective Actions:Design Basis Documentation Will Be Developed to Alleviate Weaknessess in Diesel Generators ML20058L5041990-07-30030 July 1990 Discusses & Forwards Results of fitness-for-duty Program Performance Data for 6-month Period Ending 900630 ML20055J2031990-07-25025 July 1990 Responds to NRC Bulletin 89-002 Re Insp of safety-related Anchor/Darling Model S350W Check Valves Supplied w/A193 Grade B6 Type 410 SS Retaining Block Studs.Studs Visually Inspected & No Cracks Found ML20055H7781990-07-24024 July 1990 Forwards Corrected Monthly Operating Rept for June 1990 for Point Beach Unit 2.Correction on Line 18 Regards Net Electrical Energy Generated ML20055H6621990-07-23023 July 1990 Forwards Central Files & Public Versions of Revised Epips, Including Rev 2 to EPIP 1.1.1,Rev 16 to EPIP 4.1,Rev 6 to EPIP 6.5,Rev 20 to EPIP 1.2,Rev 8 to EPIP 6.3,Rev 0 to EPIP 7.3.2,Rev 10 EPIP 10.2 & Rev 11 to EPIP 11.3 ML20058K8941990-07-23023 July 1990 Forwards June 1990 Updated FSAR for Point Beach Nuclear Plant Units 1 & 2.Steam Generator Upper Ph Guideline in Table 10.2-1 Changed from 9.3 to 9.4 ML20044A9091990-07-0606 July 1990 Responds to NRC Bulletin 90-001 Re Loss of Fill Oil in Transmitters Mfg by Rosemount.None of Listed Transmitters Installed at Plant in Aug 1988 Identified as Having High Failure Fraction Due to Loss of Fill Oil ML20055D4421990-07-0303 July 1990 Forwards Reactor Containment Bldg Integrated Leak Rate Test Point Beach Nuclear Plant Unit 1,1990, Summary Rept ML20055D3471990-06-29029 June 1990 Provides Addl Response to Bulletin 88-008, Thermal Stresses in Piping Connected to Rcss. Engineering Evaluations Performed to Assure Code Compliance Due to Unanalyzed Condition of Thermal Stratification Addressed ML20055D6221990-06-29029 June 1990 Provides Suppl to Re Loss of All Ac Power.Test Demonstrated That Ventilation Mod & Recalibration of High Temp Trip for Auxiliary Power Diesel Improved Performance of Gas Turbine Generator as Alternate Ac Source ML20055D2291990-06-22022 June 1990 Informs NRC That Gj Maxfield Promoted to Plant Manager effective,900701 ML20055D6231990-06-22022 June 1990 Advises of Decision to Proceed W/Leak Testing of Sys During Plant Refueling Outage Due to Delay in Delivery of Gamma-Metrics Hardware Fix Kits.Test Revealed That Both in-containment Cable & Detector Assembly Cable Had Leaks ML20044A0011990-06-18018 June 1990 Provides Current Implementation Status of Generic Safety Issues at Plant,In Response to Generic Ltr 90-04 ML20043D6511990-05-25025 May 1990 Discusses Cycle 18 Reload on 900519,following 7-wk Refueling & Maint Outage.Reload SER for Cycle 18 Demonstrates That No Unreviewed Safety Questions,As Defined in 10CFR50.59, Involved in Operation of Unit During Cycle ML20043B1481990-05-18018 May 1990 Advises That Necessary Info Received from Westinghouse Re Revised Administrative Controls for NRC Bulletin 88-002, Rapidly Propagating Fatique Cracks in Steam Generator Tubes. ML20043B1101990-05-17017 May 1990 Documents Status of Evaluations Committed to Be Performed Re IE Bulletin 79-14 Program.Support CH-151-4-H50 Modified During Unit 1 Refueling Outage & Now in Code Compliance. Meeting Proposed During Wks of 900618 or 900716 ML20043A9921990-05-16016 May 1990 Advises of Typo in Item 2.C Re Emergency Diesel Generator Meter Accuracy in Submittal Re Corrective Actions in Response to Concerns Identified During Electrical Insp.Meter Calibr Reading Should Be 3,050 Kw Not 350 Kw ML20043B0481990-05-16016 May 1990 Updates 890330 Response to NRC Bulletin 88-010, Nonconforming Molded Case Circuit Breakers. Util Will Replace Unit 1 Inverter & Battery Charger Circuit Breakers within 30 Days After Receipt & QA Verification ML20043A7631990-05-15015 May 1990 Responds to Notice of Violation & Forwards Civil Penalty in Amount of $87,000 for Violations Noted in Insp Repts 50-266/89-32,50-266/89-33,50-301/89-32 & 50-301/89-33. Addl Employees Added in QA & Corporate Nuclear Engineering ML20042H0201990-05-10010 May 1990 Forwards List of Concerns Identified at 900417 Electrical Insp Exit Meeting to Discuss Preliminary Findings of Special Electrical Insp Conducted on 900319-0412 Re Adequacy of Electrical Distribution Sys ML20043A2181990-05-10010 May 1990 Forwards Nonproprietary & Proprietary Version of Point Beach Nuclear Plant,Emergency Plan Exercise,900314. ML20042G7441990-05-0909 May 1990 Forwards LER 90-003-00 ML20042G7361990-05-0808 May 1990 Forwards LER 90-004-00 ML20042E4571990-04-10010 April 1990 Documents Basis for Request for Temporary Waiver of Compliance of Tech Spec 15.3.7.A.1.e Re Diesel Generator Fuel Oil Supply ML20012F2961990-03-29029 March 1990 Withdraws Tech Spec Change Request 120 Re Staff Organization Changes & Deletion of Organizational Charts,Based on Further Corporate Restructuring within Util ML20012D8301990-03-20020 March 1990 Responds to Generic Ltr 89-19, Safety Implication of Control Sys in LWR Nuclear Power Plants. No Limiting Condition for Operation Required for Overfill Protection Sys at Plant ML20012D4241990-03-0808 March 1990 Forwards Public Version of Revised Epips,Including Rev 17 to EPIP 1.3,Rev 8 to EPIP 3.1,Rev 15 to EPIP 4.1,Rev 1 to EPIP 6.7,Rev 1 to EPIP 7.1,Rev 11 to EPIP 7.2.1 & Rev 11 to EPIP 7.2.2 ML20011F7531990-02-26026 February 1990 Informs NRC of Apparent Inconsistency Between Min Level of Boric Acid Solution to Be Maintained in Boric Acid Storage Tanks Per Tech Specs & Amount of Deliverable Boric Acid Assumed in Safety Analyses ML20006B7091990-01-25025 January 1990 Responds to NRC Bulletin 89-002 Re Check Valve Bolting Insp. All Anchor-Darling Model S35OW Check Valves Inspected for Cracked Internal Bolting During Refueling Outage of Unit.No Indications of Cracks Found ML20006A3381990-01-18018 January 1990 Forwards PDR & Central Files Versions of Rev 16 to EPIP 9.2 & Forms, Radiological Dose Evaluation. ML20006A3411990-01-16016 January 1990 Forwards Rev 16 to EPIP 9.2, Radiological Dose Evaluation to Be Inserted in EPIP Manual ML20005G0901990-01-12012 January 1990 Responds to Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment. Outside of Intake Structure Will Be Inspected for Excessive Corrosion on Semiannual Basis & Forebay & Pumphouse Inspected ML20005G1751990-01-12012 January 1990 Responds to NRC 891213 Ltr Re Violations Noted in Insp Repts 50-266/89-30 & 50-301/89-30.Corrective Action:Procedure RP-6A, Steam Generator Crevice Flush (Vacuum Mode), Initiated ML20005H0551990-01-11011 January 1990 Responds to NRC Bulletin 89-003, Potential Loss of Required Shutdown Margin During Refueling Operations. Util Will Provide Specific Training to All Members Responsible for Refueling Operation to Emphasize Importance of Procedures ML20005G9031990-01-0909 January 1990 Forwards Monthly Operating Repts for Dec 1989 for Point Beach Nuclear Plant Units 1 & 2 & Revised Monthly Operating Rept for Nov for Point Beach Unit 2 ML20005G5641990-01-0808 January 1990 Updates Progress Made on Issues Discussed in Insp Repts 50-266/89-12 & 50-301/89-11 Re Emergency Diesel Generator Vertical Slice SSFI Conducted by Util.By Jul 1990,revised Calculation Re as-built Configuration Will Be Performed ML20005E5441989-12-29029 December 1989 Describes Actions & Insps Completed During Recent U2R15 Refueling Cycle & Proposed Schedule for Completion of NRC Bulletin 88-008 Requirements,Per Util 881221 & 890616 Ltrs. Extension Requested Until 900631 to Submit Data Evaluation ML20005E5451989-12-28028 December 1989 Advises That Addl Info Required from Westinghouse to Meet Util 890621 Commitment to Adopt Administrative Control Re Rapidly Propagating Fatigue Cracks in Steam Generator Tubes Per NRC Bulletin 88-002.Info Anticipated by End of Mar 1990 ML20005E5381989-12-27027 December 1989 Provides Update of Status of Implementation of Resolution of Human Engineering Discrepancies Documented During Dcrdr. Lighting Intended to Document Deficiencies Per NUREG-0700, Eleven Human Engineering Discrepancy Computers Resolved ML19354D5781989-12-21021 December 1989 Certifies Implementation of Fitness for Duty Program Which Meets Requirements of 10CFR26 for All Personnel Having Unescorted Access to Plant Protected Areas.Periodic Mandatory Random Chemical Testing Will Commence on 900103 ML20005D8071989-12-21021 December 1989 Forwards Response to Violations Noted in Insp Repts 50-266/89-29 & 50-301/89-29.Response Withheld (Ref 10CFR73.21) ML20005E2301989-12-21021 December 1989 Forwards Reactor Containment Bldg Integrated Leak Rate Test Point Beach Nuclear Plant Unit 2, Summary Rept,Per 10CFR50,App J.Type A,B & C Leak Test Results Provided ML20042D2391989-12-21021 December 1989 Responds to Violations Noted in Insp Repts 50-266/89-27 & 50-301/89-26.Corrective Actions:Superintendent of Health Physics Discussed Log Book Entry Requirements W/Health Physics Contractor Site Coordinator ML19354D6231989-12-15015 December 1989 Responds to Generic Ltr 89-10 Re safety-related motor- Operated Valve Testing & Surveillance.Util Intends to Meet All Recommendations Discussed in Ltr Except for Item C Re Changing motor-operated Valve Switch Settings 1990-09-05
[Table view] |
Text
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"s/ * .
Wisconsin
' Electnc
' POWER COMPANY 231 W Michgan. RO. Box 2046, Mdwoukee WI 53201 (414)221 2345 VPNPD 267 NRC 05 3 May 5', 1989 Document Control Desk U.S. NUCLEAR REGULATORY COMMISSION Mail Station Pl-137 i Washington, D.C. 20555 Attention: Mr. Warren Swenson, Project Manager PWR Project Directorate III-3 Gentlemen: i DOCKET NOS. 50-266 AND150-301 !
FSAR CHANGE - TABLE 8.2-3 !
MAJOR BATTERY LOADS !
POINT BEACH NUCLEAR PLANT UNITS 1 AND 2 l l
As you are aware, Wisconsin Electric Power Company is replacing l the station batteries at our Point Beach Nuclear Plant. The D05 station battery for Point Beach Unit 1 is being replaced during j the present spring 1989 outage. The D06 station battery for Point '
Beach Unit 2 is scheduled for replacement during the fall 1989 outage.
1 In order to facilitate these battery replacements and still meet l the requirements of our Technical Specifications, we have procured l and installed a temporary battery to take the place of either D05 j or D06 while the physical replacement of the respective battery is ]
taking place. This was necessary because Technical Specification )
15.3.7.B.I.f permits power operation for only twenty-four hours if j either DOS or D06 is inoperable. Although Unit 1 will be shutdown 1 during the DOS replacement, Unit 2 could continue in power opera-tion for greater than twenty-four hours only if both D05 and D06 j were operable. ,
4 As mentioned above, our solution is to provide a qualified tem- !
porary battery during the DOS change out. This temporary battery is identical to the replacement battery, is situated in a seis- ;
mically qualified installation, and has been tested to estab- j lish its capability to carry all the loads delineated in FSAR ;
Table 8.2-3. Because the installation of the station batteries j will be done when a unit is shutdown, we plan to tag out the two l 8905150136 890505 , c' PDR ADOCK 05000266 g6 !
t p PDC '
.4 subsism ofIliamhL)wGupadon i \\
l
^
Document Control Desk May 5, 1989 Page 2 major loads on the station battery that is being replaced, the
! Turbine Emergency Bearing Oil Pump and the Air Side Seal Oil Back-up Pump, during the period that the DC buses are supplied by the temporary battery. For that reason, the temporary battery can be connected to its DC bus through only a 600 amp DC breaker.
As a part of the approval process for the plant modification to replace the station batteries, a 10 CFR 50.59 evaluation of the temporary battery arrangement was conducted. That evaluation concluded that the battery replacement and substitution of the temporary battery could be accomplished without prior NRC review and approval, since no unreviewed safety question was identified and no Technical Specification change was necessary. In the course of discussions held with members of the NRR and Region III staffs at the Region III headquarters on May 4, 1989, and by telephone with Mr. W. Swenson on May 5, 1989 regarding battery capacities and testing, we agreed to promptly provide the staff with copies of our relevant 10 CFR 50.59 evaluations in this regard. Copies are attached herewith.
We also are taking this opportunity to provide you with a revision to Table 8.2-3 of the Point Beach Final Safety Report. This table, entitled " Major Battery Loads Following Loss of Outside Power" is referenced in Technical Specification 15.4.6.B.4 which concerns monitoring of station battery capacity. The table has been revised to acknowledge that certain non-safety related loads, as identified by an asterisk in the revised table, may be removed from the battery loading to facilitate component maintenance.
Should these loads be removed, the table further acknowledges that the station battery capacity shall be sufficient to carry the remaining loads delineated in the table for the length of time specified in the table. Such action by the licensee, of_ course, may only be accomplished without prior NRC approval provided all the provisions of 10 CFR 50.59 have been satisifed.
Please contact us if you have any questions regarding the enclosed evaluation or our revision to this FSAR table.
Very truly yours,
/
W QU C . W. Fay Vice President Nuclear Power Copies to NRC Resident Inspector NRC Regional Administrator, Region III
TABLE 8.2-3 MAJOR BATTERY LOADS FOLLOWING LOSS OF OUTSIDE POWER Station Station Station Station Battery Battery Battery Battery Unit 1 DOS D06 D105 D106 Turbine Emerg. Bearing 011 Pump (50 HP)* 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Air Side Seal Oil Backup Pump (10 HP)* 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />
' Emergency Lighting (4 KW) 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Feedwater Pump Lube Oil Pump 1-P73C (5 HP) 1 minute Feedwater Putnpj Lube Oil Pump 1-P73D (5 HP) 1 minute Inverter 1DY01 2 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> i Inverter 1DY02 3 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Inverter 1DY03 4 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Inverter IDYO4 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Unit 2 Turbine Emerg. Bearing Oil Pump (60 HP)* 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Air Side Seal Oil Backup Pump (10 HP)* 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Feedwater Pump Lube Oil Pump 2-P73C (5 HP) 1 minute Feedwater Pump) Lube Oil Pump 2-P73D (5 HP) 1 minute Inverter 20Y01 2 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Inverter 2DY02 3 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> inverter 2DY03 4 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Inverter 20Y04 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Common Inverter DY0A l2 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Inverter DYOB 3
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Inverter DY0C 4 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> !
Inverter DY0D 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> I
- These DC loads are not nuclear safety related and may be removed from the battery supplied distribution buses to facilitate maintenance of the components or for other similar reasons. Battery capacity shall be sufficient to supply the remaining loads for the specified times in order to essure operability of the station catteries as specified in the Technical Specification.
I 1,2,3,4 On'y 2 of 3 inverters can be supplying load at a given time.
l i
p ,.i A 9 _. e s ._ e 9 Fr R I 14816 PBNP P.O2 i POINT SE&CH NUCLEAR PLANT DOCUN DT& TION OF SERIAL REVIEW & APPROV&L DOCUMENf SMP #978, MINOR, STATION BATTERY D05 CHANGEOUT - UNIT COMMON AMb Mt &&-oMM C to e n so.re t yn wmea Revision 0 Date _ Date Performed 17 NeJ9 )
(If applicable) Unit l
NOTE: 1. THIS FORN M&T 88 USED TO RECORD THE SERIAL REVI N AND APPROVAL OF DOCUMENFS WHICH REQUIRE SUPERVISORY STAFF REVIEW AND MANAGER APPROVAL.
1
- 2. THE PROVISIONS OP 10 CFR 50.59 APPLY TO ALL CHANGES AND MUST BE l EVALUATED AND DOCUMErfED IN ACCORDANCE NITH QF 3-3, "AUTHORIZ& TION 4 0F CHANGES, TESTS AND EXPERIMENTS." &TTACH QF 3.3.1 IP REVIEW 15 REQUIRED.
- 3. TIQBfICAL SPECIFICATION 15.6.8 APPLIES FOR ALL PROCEDURAL OIENGES. A QUORUN OF MSS MINBERS (POUR) MUST REVIEW THE PROPOSED CN&NGE PRIOR TO APPROV&L ST 1958 MANAGER.
- 4. FOLLOWING COMPLETION PROCEDURES ARE TO BE ROFFID TO THE SUPERVISOR'-
STAPP SERVICES. ALL OTHER DocunsrPs ARE T0 at ROUTED to nit
&DNINISTRATIVE SPECIALIST - EQRS.
Date - By General $ gerintendent Date d7[ff sy A ew-- Supt - Operations Date __M!a*7/ N __ By Md Supt - EQRS Date _ t}f1.9lr+
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5 4 t - Naint & Const Date By F Supt a chemistry Date By Supt - Health Physics Date By Supt - I&C Date 8.67-df py __ r -
o Supt - Reactor Engineering Date By Supt - Training Date By Title __
Date By Title f
Date g
47 k4 gvi Approved . .h g
2 1 Manager - PBNP Noted for Record: MSSN (N By !O b
EQR-26d (On-as)
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' sir, el __ __ _ i leifersace coeumsnt ei MR 85 3 0H 4 C. I (Attach additiSnel piges if necessary) section ! - Determanetton if safety Evaluetton is Aequired prief Description of proposed Change, Test, or superiments cMNatovf StarroAl harvtaty DOS
, 1. will any erstem, structure, or component (s#C), as described in the PONP r$AR, including its figures, be altered? '
/ Yes too
- 2. Could, within reasonable selbility, the reposed change affect the function or method of a SSC which described in t e PSAAF YES # NO
). Will any procedure or procedures as described in the PbMP r$AR be altered? YES g NC
'4.
Will a test or e geriment which le not described in the r5AA be performed? YES # NC
- 3. Will a prior 'cocumented technical conusitment to the NRC be altered? YEG _ NO
- 6. Ze a potential change to the facility or its operation as described in the 18AR involved? YES y NO ,
7 Is an evaluation required fare any of the above questions answered YES)? / YES NO NOTE: If no, then provide basis for decielen in eusenary section.
List the licensing beste documente and sections where the system, structure, component, procedure, test, or emperiment is described. (rSAR Chapters i thru 15 and appendices, and technical 35C commitments),
F'$$ $ 5 tC'ro0AJS 8. l.I, 8. 2.. L 8. *t . /
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y pg ra gs.e t B. t. '3,, If.4. I- t section II - Determination at an onreviewed safety guestion le rnvolved:
- 1. Does the proposed activity increase the orokebility of occurrence of an /
neci*at previously in t.w nApr
_ Yes i HC List the accidert(s) prewtovely evaluated in ahd sAs with which the proposed shan e to the ,$5C or procedure, or the proposed test or esperisset could have any pesettle bearing, of set, or association, and describe the bearing, effect, or assectaelon. Describe why and/or how the probah111ty of occurrence will or will not be increased.
g $ptp, S E c 4*te et 84 t.11 = i.e s t ofAu.nC 1% wars. TO TMt S Y* rted A3'""M t e- - -- 31* c on 's~r se - r *rce o er wAeown Txto Je eWC4. W @ t-1$ est rsn' esseavy s urt*L4 64 dr A v s"Ad ,,
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- 2. Does the proposed activity incrosse the consequences of an es_cident previously evaluated in the sap? 7
/
YE8 NO Describe why and/or how the consequences of the accident (el listed in it will or will not be incrossed gf Oc r ^ ^M g g if coatnLavow ar es t.*tr de Pcunsa. *r* 2 TA rt *4 A u erst.n sus.) ACs rese NO 1" tacn4Asse pusea g 4.rrse 4 194c a . a s** /** * ' 4.* '~*
- L L S4 A u sc s*e t 4 be ntt ad C ed.+Ne dee r N 0c c.r.r.
- 3. Does the proposed activity increase the r>robability of occurrence of a /
malfunet ton of equipment leportant to sarety previously evaluated in the sap? Ytd i NO List the malfunction el of equipment previously evaluated in the SAR with which the proposed change to the Sec or procedure, or the proposed test or emperament could have any poselble bearings, effect, or association, and describe the bearing, effect or association. Describe why and/or how the probability of occurrence wi!! or will not be increased.
A/OAIdC.
Form CP J.J.!
eev. 2
- MAy-05 FRI 14 gie PBNP *
' 4. Does tha proposes tetivity increase the consequences of a malfunction of equipment important to Safety p(eviously ava4uessa en the nami - j Yts 4 No Describe increased.why and/or how the consequences of the malfunction (el listed in 93 wall or will not be EU l.
Does the proposed activ&ty create the possibility of an Mcident of a different type than any previously evaluated in the SAAP YES / NO List any possible accident that may be created as e result of the propored activity. Describe why in theand/or SA8. how each accident is or le not of a different type than any previovely evalveted N O^t E f s i 4.
I Does the proposed activity create the possibilit'y of a malfunction of equipment important to safety of a different type then any previousar evaluated in the SAA?
YES _ NO List any possible selfunction of equipment that may be created as a reault of the proposed activity.
Describe how Previously evaluated in theand/or SAR. why each malfunction is or le not of a different type than any L0$$ Of 4 "VA A !4
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Does for anythe proposed technical activity redues the sarein of safety se defined in the basis speelfication?
_ 13s / No List any technical bearing, specification association, or effect, with which the proposed change, test, or expert.sent has any and deseribe the bearing, association, or effect. Describe why 11sted and/or how will not bethe margin of safety 44 defined in the beels for the techatcat specifications redweed.
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l Form CP 3 2.1 Nov. 2
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Page 1 of 3 NUCLEAR POWER DEPARTMn:T 2KFR50.59 REPORT Ser, el l Reference Document al p 68 - o T 4 4 8. I cAttach addational pages af necessary)
Sectaon 3 - Determanat non af Safety Evaluation as Required l A/ St,4 L L. WM eese,asey j',e r rarary Brief Description of Proposed Change, Test, or Experimer.t tal App RocM. /
- 3. Will any system, structure, or component (SSC), as described in the PBNP FSAR, YES M wo including ats fagures, be altered?
- 2. Could, within reasonable possibil'ity, the proposed change af fect the function YES ! No or method of a SSC whach as descri' bed in the FSAR7 Wall any procedure or procedures as described in the pBNP FSAR be altered? YES # NO 3.
Wall a test or experiment which is not described in the FSAR be performed? YES / No 4.
YES NO
- 5. Wall a prior documented technical coramitment to the NRC be altered? I I
- 6. Is a potential change to the f acility or its operation as described in the YES NO h FSAR anvolved?
YES NO
- l . Is an evaluation requared (are any of the above questions answered YES)?
t NOTE: If no, then provide basis for decision in summary section.
Last the 31 censing basin documents and sections where the system, structure, component, procedure, test, or experament as described. (FSAR Chapters 3 thru 15 and appendaces, and technical NRC commitments). es~. 3. 4-pg sccsosts 8,l. 8, 6.'s.1u, 6 L ) 8 4. I. It, pyA, F/Gu/LE S. 'L * / O l
yspg -rA 51.E. 82~5 J f
' Section II - Determination af an Unreviewed safety Question in Involved Does the proposed activity increase the probability of occurrence of an
( 3.
accadent prevaously an the SAR? YES NO List the accident (s) previously evaluated in the SAR with which the proposed change to the SSC or I procedure, or the proposed test or experament could have any possable bearang, effect, or association, and 6-scribe the bearing, effect, or assoelation. Dascribe why and/or how the M KJc.s.d48dI probability of occurrence wall or wall not be ancreased.
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- 2. Does the proposed activity increase the consequences of an seendent prevaeusly YES y NO evaluated in the SAR?
Describe why and/or how the consequences of the accident (s) listed in el will or will not be . (
increased.
jgg $>s? ** MM l'
- 3. Does the proposed activity increase the probability of occurrence of a YES
/
V NO malfunction of equapment important to safety prevaously evaluated in the SAR?
Last the malfunction (s) of equipment previously evaluated in the SAR with which the proposed change to the SSC or procedure, or the proposed test or experament could have any possible bearangs, effect, or association, and describe the bearing, effect or assocastion. Describe why and/or how the probability of occurrence will or will not b increased.
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- 4. Does the proposed activity inerssas the con **outness of a malfunction of -
YES. NO equipment important to safety previously eveJusted an the 5AR7
- Deeeribe why and/or how the consequences of the malfunction (s) listed in 93 will of will not be ancreased.
k Does the proposed activity create 'the possibility of an accident of a different 7
/.
- 5. YES NO type than any previously evaluated an the SAR7 of the proposed activity. Describe List any posalble accident that may be created as a resultof a dif ferent type than any previously evaluated why and/or how each accident is or is not in the SAR.
N06 4
l Does the proposed activity create the possibility of a malfunction of equipment.
6.
important to safety of a different type than any previously eveJusted in the YES
/ NO f SAR7 j
List any possible malfunction of equipment that may be created asofa aresult 'of the proposed -
different type than any -
activity. Describe how and/or why each malfunction as or is not previously evaluated in the SAR.
(
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i
- 7. Does the proposed activity reduce the margin of saf ety as defined in the basis YES / NO for any technical specification? ,
or experiment has any List any technical specification with'which the proposed change, test,and describe the bearing, association, or effect. De bearing, association, or effect, why and/or how the margan of safety as defaned in the basis for the technical specifications
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YES NO DOES THE CHANGE TEST, OR EXPERIMENT INVOLVE AN UNREVIEWED SArETY QUESTIOH?
Section !!! - Determination if a Technical Specification change as Involved Does the change, test, or experiment involve a change in the technical YES [NO apecilacations?
If a change is required, briefly describe what the change should be and why it YES NO j is required.
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- Section IV - Evaluation Summary - (Ettach add 2tional piges af nJessstry)' .'
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I Prepared by i _ e we Date 7M8 N Rev&ewed by // a Date "b MSS Ho.
for the MSS p,g, Manalef
2n lieu of MSS and Manager signature, attach EQR-26d if serial review has been conducted.
Form OP 3 3.3 pey, 2
- - - - - - _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ - - - - - - _ - - - - _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - - - - - - - - - - _ _ _ _ _ . _ _ _ _ _ _ _ _ "------.1___________J
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< 1 M.R. 88-074*B 10 CFR 50.59 REPORT ATTACHMENT Modification Request 88-074*B is to temporarily install a 125 volt Class IE station battery in the AFP room, east of the tunnel.
I Removal of the battery will be controlled by a different design l package. The basic function of this battery will be to provide back-up emergency power to buses D01 and D02 while the existing emergency power sources, DOS and D06, are replaced. This instal-lation is required since change-out activities for one battery, which will be controlled by other design packages, will take longer than the allowed 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of having one of DOS or D06 out of service while one or both reactors are generating power.
Technical Specification 15.3.7.B.1.f delineates the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> LCO by stating "One of the batteries DOS or D06 may be inoperable for a period not exceeding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> provided the other three batteries and four battery chargers remain operable with one charger carrying the DC loads of each DC main distribution bus." While DOS and D06 are specifically called out in this LCO, the intent of l having a Class lE battery connected to the main distribution buses will be met during battery change-out.
l l Sections 8.1.1, 8.2.2, and 8.2.3 of the FSAR describe the D.C.
distribution system and Figure 8.2-10 shows the system diagram-matically. All descriptions given will still apply while the Page 1 of 6
' battery of'this design package is connected to the bus (es) except Figure 8.2-10 which shows both DOS and D06 as 60 cell strings.
This is not consistent with all other FSAR data nor is it con-sistent with the existing installations which show both DOS and
'D06 are-made of 59 cells connected in series. The battery to be installed will also be made of 59 cells. 'Therefore, Figure 8.2-10 should be changed to indicate both D05 and-D06 are 59 cell batteries, not 60 cell batteries.
I~ The design bases criteria for a station battery, as documented in the FSAR, is that it must be able to withstand, without undue risk to public safety, the forces that may be imposed by natural phenomena.such as earthquake, tornado, flooding, high wind, or heavy ice. The station battery to be installed here will be able to withstand the forces of a tornado, flooding, high wind, or heavy ice since it will be installed in the Class 1 portion of the i
Turbine Building. Some forces due to an earthquake will be transmitted to the battery. The battery system will be qualified to withstand the maximum expected seismic forces with a 100%
margin. Existing equipment in the area of battery installation may not, however, meet this criterion creating the potential for this equipment to fall on the battery system rendering it inoperable. All equipment that has a potential for falling on the battery was evaluated to determine the seismic mounting adequacy.
The evaluation shows only two flourescent lights, two service air rubber hoses, and a cover over the W46 pulleys are inadequately Page 2 of 6 l
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supported to withstand a seismic event. The lights and hoses will be removed for the period the battery is actually connected to a bus and the pulley cover mounting will be improved in order to remove these seismic hazards. Removing the lights will cause no personnel hazard since lighting will be available from other fixtures in the room which have no potential for falling on the battery. Emergency lighting for the area, which is seismically mounted, will remain intact.
The design bases criteria for either DOS or D06, as delineated in Bechtel's Information Exchange on Electrical Design for PBNP, is that the batteries must provide power to all essential DC loads for one hour upon loss of station AC power and supply DC power required to actuate and operate the Engineered Safeguards System at any time including the one hour period following the complete loss of station power. Bechtel determined the battery size necessary to meet these criteria by considering the worst case
-(i.e., loss of station AC coincident with an SI actuation) and included a 100A contingency throughout the required one hour th duration. The battery to be installed will have the capability to exceed these maximum power delivery requirements.
Section 14.1.11 summarizes the evaluation of a loss of all AC power to the Station Auxiliaries Accident. Step 1 of the Turbine Trip sequence states that vital instruments are supplied by emergency power sources. The emergency power sources for the red Page 3 of 6
O and blue instrument buses are the emergency back-up batteries connected to Buses D01 and D02. This modification will not change the probability of this accident occurring since power avail-ability at the Station Auxiliaries is independent of ths emergency power source. The consequences of this accident remain unchanged since the battery system is designed to supply the necessary loads i
under these circumstances.
No other documented design basis criterion exists.
Since the AFP room has steam lines in it, and the DOS and D06 battery rooms do not, the battery will be more susceptible to a malfunction caused by a steam line break. If such a steam line break caused the battery to malfunction in a way to cause the loss of the associated bus, the steam line break could not be isolated by MOVs 2019 and 2020 since their control power comes from that bus. However, manual valves 235 and 237 could be used in this event. Note that these manual valves would have to be used if the j
steam line break occurred in the governor sensing lines for the l
l steam driven AFPs.
I Section 14.2.5 of the FSAR analyzes the effects of a steam line 1
break and states that the following systems provide the necessary 1
protection: 1. Safety Injection System Actuation
- 2. Reactor Trip
- 3. Redundant Isolation on Main FW lines, and
- 4. Trip of the Steam Line Isolation Valves Page 4 of 6
Loss of either D01 or D02 would not render any of these systems inoperable. Therefore, the consequences of the accident are not increased.
A hydrogen gas fire and/or explosion due to an excessive concen-tration buildup (i.e. greater than 2%) from the battery could hypothet0.adg 9dd Potentially cause a steam line rupture. Calculation N-89-002 shows that it would take no less than 133 days with no ventilation to reach a 2% concentration of hydrogen. The redundancy and air circulating capabilities of the existing HVAC system for the area assure such a concentration buildup will not occur. In the highly unlikely event that all air circulating capabilities were lost, the hydrogen generation from the battery could be stopped before creating any hazard by removing its float voltage since the battery only needs to be able to supply emergency power for no more than several weeks. Therefore, the probability of a steam line rupture is not increased by the installation of this design package.
Since the service water headers in the AFP room are not sleeved, I
and these headers are sleeved in the existing DOS and D06 battery l rooms, the battery will be more susceptible to a malfunction caused by a service water header leak. Such a service water header malfunction can be mitigated by isolating that portion of the pipe. Neither Bus D01 nor D02 operability is required to l
provide such isolation. Therefore, no safety issue is raised by placing an emergency back-up power supply for either D01 or D02 in Page 5 of 6 w _ __ _
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a room with unsleeved service water headers since either or both
-units can be operated safely without such an emergency back-up I
power supply,available assuming battery loss does not cause loss of the bus. 'If the bus is: lost, the operating unit would trip due to the loss of the associated instrument bus.
Installing the. battery in the AFP room will not cause the existing Halon' fire suppression system to be overloaded. Halon is the only recommended type of fire suppression system for batteries and is used in the existing DOS and D06 battery rooms.
All Appendix R feeder cables powered by the bus to which the battery will be connected, are routed through the same fire zone that the battery will be installed in. One fire could cause all
' Appendix R loads powered by this bus to loose their power source by burning these feeder cables. If this were to occur, there would be no Appendix R need for the power source, and therefore, no Appendix R issues are raised.
The installation location of the battery will impair access to the local control stations mounted on the AFP room east wall. Suffi-cient room will be left such that no special equipment (such as ladders) will be required to access the panels.
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