|
---|
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
( -
4 Wisconsin i
1 Electnc POWER COMPANY t m a w eno r,to sc.;; a u o . w n a am:n:m i
I VPNPD-89 564
[,. >
NRC-89 133 October 26, 1989 U. S. NUCLEAR REGULATORY COMMISSION Document Control Desk Mail Stop P1-137 Washington, D.C. 20555 Gentlemen:
! RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION RELOCATION OF THE ALTERNATE EMERGENCY OPERATIONS FACILITY FOR POINT BEACH NUCLEAR PLANT, TACS 71760 AND 71761 By letter dated December 14, 1988 we requested permission to relocate our Alternate Emergency Operations Facility (AEOF) from its present location at the Wisconsin Public Service district office in Two Rivers, Wisconsin, to the Wisconsin Electric Power Company corporate headquarters in Milwaukee, Wisconsin. The attachment to this letter responds to the questions you included in your request for additional information dated June 23, 1989.
If you have any additional questions or require clarification on any item, please contact us.
Very truly ours,
? <
['o,v t /
C. W. Fa Vice President Nuclear Power Att achments I l
l
[GW <
8911030143 891026 :g
, PDR ADOCK 05000266
, s P. PNU ry. -
E i 5
gr - r
[ .
Attachment 1
- 1. Provide exact straight line and highway distances from the plant site to the proposed backup EOF at The Corporate Emergency Center (CEC) in Milwaukee, Wisconsin.
L The straight line distance from the primary EOF to the Wisconsin Electric Power Company corporate office is approximately 88 miles. The driving distance is 100 miles. (See map, attachment 2)
- 2. Provide the transit time using a motor vehicle between the CEC and the plant site under normal daylight and weather conditions, typical traffic patterns, and observing posted speed limits.
The driving time from the primary EOF to the CEC is approximately I hour 50 minutes under normal traffic and weather conditions.
- 3. Incicate the anticipated modes of transport, other than motor vehicle, if any, to oe used to transport emergency personnel between the CEC and the plant site and the typical transit time for each mode of transport.
The primary mode of transport used at this time is motor vehicle, either private or company owned. At least one four-wheel drive company vehicle is available for transport in Milwaukee; several four-wheel drive vehicles are availaDie at Point Beach. In addition, a number of private four-wheel drive vehicles are available at both locations. Helicopter and fixed-wing aircraft are tvailable for charter at Mitchell Field in Milwaukee (10 miles south of corpcrate headquarters). However, we have not estaDlished any standing arrangements for aircraft charter for two reasons: (1) the time required for aircraft preparation and for travel between the airport and corporate headquarters substantially offsets the time saved by air travel; and (2) under adverse weather conditions, motor vehicles are more reliable. Please refer to the answer to number two above for the typical transit time by motor vehicle.
4 Provide a description of the system to be used to make plant information available in the CEC including a list of emergency data acquisition system variables, and the installation and set-up time if it is not a permanent, full-time system.
Plant data is available in the CEC (proposed alternate EOF) on the Remote EOF Data System (REDS) via a terminal link by modem with the Plant Process Computer System at PBNP.
The software which implements REDS is resident on the PBNP Plant Process Computer System (PPCS). The time for terminal setup and access to the PPCS is approximately 10 minutes. It is our practice to activate the CEC at the same time the EOF is activated. Therefore, under conditions where EOF functions would be transferred to the alternate EOF located in Milwaukee, the REDS would already be in operation.
A list of the REDS variables is included as attachment three.
[
5.. Provide a map illustrating the locations of the Point Beach plant site, the CEC, the Kewaunee County Emergency Operations Center, the Manitowoc County
[ EOC.-the State of Wisconsin E0C, and the principal highways and topographical L features between these locations.
The Kewaunee and Manitowoc County EOCs.are located in the cities of i Algoma and Manitowoc respectively. The State of Wisconsin EOC is located in
[ Madison, Wisconsin.
See attachment 2.
- 6. Provide a detailed description of how the dispatch, resupply, communications and data coordination of offsite radiation monitoring teams will be handled if the EOF function is moved to the CEC.
In the event that EOF functions are moved to the corporate offices in Milwaukee, the Offsite Health Physics facility would also require evacuation.
The Offsite Health Physics Director will report to the Technical Support
' Center. He will coordinate the dispatch and actions of offsite monitoring teams from the TSC via FM radio. He will relay information to the Radeon/ Waste Manager in Milwaukee via telephone.
The offsite monitoring teams will transfer operations to the Kewaunee hetle3r Plant Site Access facility located approximately 6.9 miles north of Go M NP Offsite Health Physics Facility. This transfer of operations is w aanged from present practice and is described in PBNP Emergency Plan Implementing Procedure EPIP 6.4.4, Offsite Health Physics Facility (OSHPF)
Evacuation. A procedure change will be required to direct the Offsite Health Physics Director to report to the TSC in the event of an OSHPF evacuation.
- 7. Provide an estimate of the time required to move the EOF functions from the primary EOF at the plant site to the backup EOF at the CEC and provide a detailed description of how the EOF functions will be performed during the relocation.
Prior to evacuating the primary EOF, the Emergency Support manager (ESM) will formally turn over the EOF function to a qualified ESM in the CEC.
Therefore, there will be no disruption of EOF functions. Turnover will be expeditious, since CEC personnel normally monitor the functions of the plant and EOF and are cognizant of plant conditions and emergency response actions.
Under typical circumstances, at least one qualified ESM and one qualified RadCon Waste Manager are available at the CEC. Therefore in most circumstances, since the CEC is itself already operational, turnover could occur in less time than required for the present AEOF. We estimate turnover could occur in about 30 minutes; and, if desired, the original ESM and RadCon Waste Manager could resume their roles after the I hour and 50 minute drive time.
m' .; < c y
v f
Descrioe how the Emergency Director, located in the backup EOF will be able to 8.4 effectively coordinate Wisconsin Electric Power Company activities with state.
, local and' federal officials who will be located near the site.
The Emergency Director. as defined in the PBNP Emergency Plan, '
coordinates companywide activities and is normally located'at the corporate office. However, we assume that Emergency Director in the context of the question means the Emergency Support Manager (ESM) in the EOF, as defined in'
[ our Emergency Plan.- The ESM will coordinate company and government activities i n by telephone as he presently does from the primary EOF, ,
y Note that present procedures in state and local plans place primary
[ reliance.on telephone and radio communications rather than on face-to face communications. These communication links can be continued regardless of EOF location. Federal. officials relocating to the CEC would continue face-te-face communication; those electing to relocate to the County Emergency Center, JPIC, or other location would be accommodated by telephone. ,
- 9. Provide copies of letters from Kewaunee and Manitowoc Counties, as well as State of Wisconsin officials, indicating their acceptance or approval of the proposed relocation of the backup EOF to the CEC.
See attachments 4, 5, and 6.
i
-- - - . , - - - m-p..
.,-p- - 41,m.-,e -A,.4s--4 -J-AAE-A-r-iu.-% F-,wed--W .***e- 4 *4-di=-.8=A,a.m.w-.mmmd-- .hasm..m+.inem.45-Aw.M-euww. ---am- 4.eoa.-swe. -es44i - .ha-m->m. m -44 l
sim
~~'
g -
w ,
[ g. l-h m
- e. : ,
7\ . ;
.w <nMW l --
fh . A" kgl' MC]Q "A _j;Q.g$( [- l 4 ?
- 4. %.- %ym % \g, ~ g r
.t3 0\i p ss q
m :
9 = 13%%pg%gq%$ :
Ofc. e,mata ... .
E y % ,J a .
$- s, L _sMiltyg4G W
.2.==
ea -$ ~ . ,- -
gr Lr m
n -
gg 1
. ~ T: ;, .., 9% ,
@c=4s l l
^
. H E :.~ 2. ic: g. v.h u.
c E E "".9.EiE E "
Q2 %GW -
b E.@
j *+
M35 gdah, n,=, .: n
~
an===
q s ,
liii
. .:. .c.== -. -
- 3. -
b p- n
- en gg,l $ qn hG7
- ' * ^
.:s'iiE- t m :-w -
~..EE ;E'E'.~~. I, i .
M * !f ,a . :.s., ' W
-3 iLkW."dMV Yb./ ~* . cb
~
f
[3 p"d UM%w- ep Ah
".*j{g 1&I-Q ,- $ i ,
^
3
,i. & ,._fii-25 '.--gy h . .LpJm~gq?
.=
1 .
,sgg. %.* -- 1 t
'xi ., -
i >
)
R,I Qf
=
s,"'%s.v ,~ p, .
w p .:'
c }< L&
u A. 4
%po- -
w.;- =5 gr (
5.s (q.
[$,d. f~W. >Ls s m
S M 7.'(gmd &, hM g.. p yMp M b [ $ g wh h.7m. ,4.yt/
,, y ; .... .
tT l
N s
a
(Y#
6 EC C F E N 's- '- Si C?OR Gr:r >Pn
'E . Point Id! Deseristinn Row Colon smar=====...sussuusa asusuutu.......e==asus =========6.
F SYSA137 PROC REACTOR VES LEV (NAR RNG) 4 3 EYBA148 PROC kE ACTOR VES LEV (WJDE RNG) 4 11 SYSA134 PROC. PRESSURIZER WATER LEVEL 4 20 SYSA133N PROC RCS PREESURF (NORMAL) 4 31 SYSA15i PROC HOT LEG TEMP-(LOOP A) 4 40 SYSA159 PROC HOT LEG TEMP (LOOP B) 4 48 SYSA160N PPOC COLO LEG TEMP (LOOP A) NORM 4 61 E: YEA 161N: PP00 COLD > LEG TEMP. (LOOP B) NORM 4 69 i 4YSA136 PROC SUSC00 LING 9 4 SYSA176 PROC CG AttX FEED FLW (LOOP A) 9- 38 I" SYSA177 PROC SG AUX FEED FLW.(LOOP B) 9 26 F EYLA344 PROl UG H?O LEV (LOOP A)-NAR RNG 9 4D S YS AISI) PROL $G H2O LEV (L OOP B) NAR RNG 9 46 SYSA153: PROC 5.G. PREGBUPE-(LOOP A) 9 60 SYSA154- PPOC 3.G. PREiSUWR (LOOP B) 9 CYLA136 PROC RCt; CORE EX11 1EMPERA1URE 14 4 SYSA141 PROC CONTAINMEN T GUMP LEVEL 14 15 OYSA143 PFOC CONTAINMFNT RA0!AT]ON 14 76 SYSA151 PROC Sb H2O 1.EV (L OOP A) Ul0 RNG 14 40 FYLA357. PROC Sb H70 LEV (l.00P B) UlO RNC 14 46 SYSAS$1 LOOP A STEAMLINE RAD 14 59 FYLAG83 L OOP P. 01 E AML I NE P AD 14 70
, 4YSA179 PROC POWLW RANGE POWEP LKVEL 17 40 EYbA144 CSOC AIR EJEC TOR RADI A110N 18 65 Gd0$$ UN!! 1 GENERATOR GROSS MW 20 40 FYEAC46' COLOR CDE FOR CEF SUbCRITICALITY 17 23 SYSAC47 COLOR COE FOR CGF CORE COOLING 16 23
-i BYEAC49 COLOP CDE FOR CCF HEAT CINK 19 23 ,
SYSAC48 COLOR COR FOR-CSF RCS INTEGRITY 20 21 !
EYBACED COLO# CDE FOR CGF CONT AINMENT 71 ?3 !
SYSACst- COLOR COE FOP CSF RCS INVENTORY 22 23 i
r e
f k
n 5
~
c SCREEN o Mi Me Red Point Id Description Row Column
, m =========== ass ==ss$nst6rs======s.a=um==============ms.
i METUS UIND SPEED 15 MIN AVG S 16 METIAT INLAND AIR TEMP 15 MIN AVG S 61 METUD WIND DIR 15 MIN AVG 6 16 METLAT LAKE SHDRE AIR TEMP 15 M]N AVG 6 63 METUDSD WIND O!R STANDRD DEVIATION 7 16 METLUT LAKE WATER 1EMP 15 MIN AVG 7 63 l METLBRE2 LAKE BREEZE CDNDITIONS FLAG 9 27 METSTAB ATMDSPHERIC STABILITY CLASS 13 31 METRAIN RAINFALL $1NCE MIDNIGHT 9 62 METLAPSE AIR TEMP LAPSE RATE (TOWER 1) 10 23 RMSAUXB AUX BLDG VENT 15 MIN AVG 16 21 RMEDRUM DRUMMING AREA VENT 15 MIN AVG 16 62 RMSSTRIP GAS STRIPPER VENT 15 MIN AVG 17 21 RMSEJECT COMBINED AIR EJ 15 MIN AVG 17 62 RMS1PURG U1 PURG EXHAUST 15 MIN AVG 21 2
, RMS2PURG U2 PURG EXHAUST 15 MIN AVG 21 17 RM51 STEM U1 STEAM LINE ATMDS 15 MIN AVG 21 38 RMS2 STEM U2 STEAM LINE ATMDD 15 MIN AVG 21 51 i
p .
SCREEN o ~11 Coro
~
fi Peint Id Description Raw Column g SYSA134 PROC PRESSUR12ER WATER LEVEL 6 8 RTO REACTOR THERMAL OUTPUT 6 34 SYSA179 PROC POWER RANGE POWER LEVEL 6 63 SYSA180. PROC INTERMEDIATE RANGE PWR LEV 7 62 62
~
r SYBA165 PROC SOURCE RANGE POWER LEVEL B L SYSA146- PROC REACTOR VES LEV (UIDE RNG) 9 9 SYSA133N PROC RCS PRESBURE (NORMAL) 9 33
,, SYSA137 PROC REACTOR VES LEV (NAR RNG) 10 10 SDBANKA SHUTDOWN BANK A. STEP. COUNT 11 64 SDBANKS SHUTDOWN BANK ~B STEP COUNT 12 64 FT925 HIGH HEAD S1 FLOU 1-P15A 13 8
> FT924 HIGH HEAD Sl FLOU 1-P15B 14 8' TCAVG INST VALUE OF AVERAGE INCORE TC 14 39 BANKA CONTROL ROD BANK A STEP COUNT 15 63 TCHIGH INST VALUE OF HOTTEST INCORE TC 16 39
- BANKB CONTROL ROD BANK B STEP COUNT 16 63 SYSA965 PROC CHARGING FLOU 17 8 TCHilD 10 02 HOTTEST INCORE T/C 17 45 BANKC CONTROL ROD BANK C STEP COUNT 17 63 BANKD CONTROL ROD BANK D STEP COUNT 18 63 F1134 LETDOWN LINE FLOU 70 8 SYSA138 PROC SUSC00 LING 2D 3B i
D o
+' .
. SCREEN o 2i Conscinzent I
\ l Poins !d ' Description Row Column
======ama===assa......=6 ..........m=========
SYSA168 - PROC CONTAINMENT HYDROGEN 6 9 ;
T3283. CONTMT.A!R TEMP EL 71 FT 6 41 T3274 CONTMT VENT 1A REC AIR TEMP 6 61 i T3285 - CONTMT AIR ~ TEMP EL 71 FT 7 41 T3270 CONTMT VENT 1B REC AIR TEMP 7 61 ,
T3292 CONT TEMP AIR EL 66 8 41 T3276 CONTMT VENT 1C REC AIR TEMP 8 61 i SYSA143 PROC CONTAINMENT RADIATION 9 8 l T3272 CONTMT VENT 10 REC AIR TEMP 9 61 '
T3284 CONTMT AIR TEMP EL 51 FT 10 41 T3293 CONT TEMP AIR EL 46 ?.< 1 41 ,
T3220 CR SHROUD SUCTION HDR TEMP 12 10 1 SYSA141 PROC CONTAINMENT SUMP LEVEL 12 56 T3286 CONTMT AIR TEMP EL 38 FT 13 41 r T3287 CONTMT AIR TEMP EL 35 FT 14 41 l
, T3277 CAVITY COOLER DISCH TEMP 15 10
-T3294 CONT TEMP SUMP B 15 61 T3295 CONT TEMP SUMP B 16 61 i LT931 CONT SPRAY ADD-TANK LEVEL 1-T36 18 7 i SYSA14D PROC CONTAINMENT PRESSURE 18 41 .
PT968 CONT WR PRESSURE RED 19 40 -
PT969 CONT WR PRESSURE YLU 20 40 i M13208 CONTAINMENT HUMIDITY UNIT NO.1 20 56 FT962 CONT SPRAY FLOW 1-P14A 21 12 ,
FT963 CONT SPRAY FLOU 1-P14B 22 12 i
I I
- y w v
s 9
SCREEN o 3; Recctor Coolant Eystem Point Id Oescription. Row Column
....=== ................................................
SYSA160N PROC COLD LEG TEMP (LOOP A) NORM 6 5 SYSA161N PROC COLD LEG TEMP (LOOP B) NORM 6 14 ADT RC LOOP A-DELTA T 1/2 AVG 6 27 BDT RC LOOP B DELTA:T 1/2 AVG 6 36 SYSA155 PROC HOT LEG TEMP'(LOOP A) 6 47.
SYSA159 PROC HOT LEG TEMP (LOOP B) 6 56 SYSA960 PROC RCS LOOP A FLOW 6 64 SYEA961 PROC RCS LOOP S FLOW 6 72 T425- PR2R VAPOR TEMP 9 7 T421 PRZR SURGE LINE TEMP 9 34 T422 PRZR SPRAY TEMP LOOP 1-A 10 58 l' T423 PR2R SPRAY TEMP LOOP 1-B 10 66 PR2RP PRESSURIZER PRES 1/2/3/4 AVG 13 6 T424 PP2R LIQUID TEMP 13 34
[
SYSA134 PROC PRESSUR12ER WATER LEVEL 13 40
. T439 PR2R RELIEF TANK LIQUID TEMP 16 7 LT442 PR2R RELIEF TANK LEVEL 16 32 PT440 PR2R RELIEF TANK PRESEURE 16 61 SYSA133N PROC RCS PRESSURE (NORMAL) 19 6 SYSA148 PROC REACTOR VES LEV (WIDE RNG) 19 35
- PTO REACTOR THERMAL OUTPUT 19 61 i
i w e - ,
e
~
q SCREEN o 4; Seconcery Systea
' Point Id Description Row Column
...................r.................................a...
SYSA155 PROC S.G. FRED FLOW (LOOP A) 5 2 SYSA156 PROC S.G. FEED FLOW (LOOP B)~ 5 10 SYSA176- ' PROC SG AUX FEED FLW (LOOP A)- 5 30 SYSA177 PPOC SG AUX FEED FLW (LOOP B) 5 38 SYSA149 PROC SG H2O LEV (LOOP A) NAR RNG 5 58
[ BYSA150 PROC EG H2O LEV (LOOP B) NAR RNG 5 66 SYSA146 PROC S.G. STEAM FLOW (LOOP A) 9 2 SYBA147 PROC 0,G. STEAM FLOW (LOOP B) 9 9 SYSA166 PROC SG STM FLW/F0 FL MSMCH(LPA) 9 28
- . SYSA167. PROC SG STM FLW/F0 FL MSMCH(LPB) 9 36 L SYSA151 PROC SG H2O LEV (LOOP A) W10 RNG 9 60 SYSA15? SROC DG H?O LEV (LOOP B) WID RNG 9 68 SYSA150 PROC HOT LEG TEMP (LOOP A) 13 2
.SYSA159 PROC HOT LEG TEMP (LOOP B) 13 9 SYSA160N PPOC COLO LEG TEMP (LOOP A) NORM 13 31 L ,
. SYBA161N PROC COLO LEG TEMH (LOOP B) NORM 13 38 P T2105 SG 1A FiEDWATER TEMA 13 62 1?104 BG 1F. FiiEDWA1ER TEMP 13 70 SGATO 31M GKN A THERMAL OUTPUT 17 12 iGBTO b1M GEN 2 THERMAL OUTPUT 17 71 R2E231 .U2 STEAM PELEASE LINE A RAD 17 45 R7E?37 U? L1E AM RE L E. AEE L INE B R AD 17 55 SGAC STM GEN A STM P 1/2/3 AVG 21 16 SGBP ETM C.EN B OTM P 1/?/3 AVL 71 23 PT22cf SG 1A FEE 0WATiR PPFSSURE 21 46 PT2ND SG IE FEEDWATER FPESSURE ?1 55 i
i
3
.J i. ,
h1 - . SCREEN o 51 volume Centrol L RHR Point ld Demeription Row Column
============................................n======.....-
SYSA134 PROC PRESCURIZER WATER LEVEL 6 6 SYSA148 PROC REACTOR VES LEV (WIDE RNG) 6 40 T126 REGEN.HX CHARGING OUTLET TEMP 6 64-
.T630 RHR HX INLET (RHR FR RCS) 9 10 T127 REGEN HX LETDOWN TEMP 9 39 :
SYSA965 PROC CHARGING FLOW 9 64 3 PT135 LOW PEESCURE LETDOWN PRESS 12 8 :
T145 NON REGEN HX LTON OUTLET TEMP 12 . 39 FT134. LETDOWN LINE FLOW 12 65 PT139 VOLUME CONTRL TANK PRESS 15 9 i T140- VOLUME CONTROL TK OUTLET TEMP 15 3B LT112 VOLUME CONTROL TANK LEVEL 15 63 FT626 LOW HEAD'S1 / RHR FLOW 1-P10A 12 T622 RHR HX OUTLET TEMP 1-HX11A 18 41 FT928 LOW HEAD 51 FLOW 1-P106 19 12 T623 RHR HX OUTLET TEMP 1HX11B 19 41 ,
+
6 e
4 D
t 0
i,%.-
c:
t
[p SCREEN 6 6i Belence of Plant Point'Id' Deseription Row Column l
(. ==s===============================:======================
iE' XD2 -UNIT 1 MAIN AUX MU 1XD2 6 34 '
l
SYSA153 PROC S.G. PRESSURE (LOOP A) 7 7 SYSA154 , PROC S.G. PRESSURE (LOOP B) 7 14 SGASF STM GEN A CORR ST F 1/2 AVG 7 58
'SGBSF STM GEN B. CORR ST F 1/2 AVG 7 65
'PT485 1URBINE IST STAGE PRESS TREF' 10 7
.PT486' TURBINE 1ST STAGE PRESS STM OUMP 10 59 PT2115 CONDENSER PRESSURE' 13 5 GROSS UNIT.1 GENERATOR GROSS MU 13 32 FT619 CC HX CCU RETURN 19 60 T3510 CIRCULATING UTR-!NLET TEMP 13 59 LT3598- FOREBAY UATER LEVEL 16 7 '
T621 CCU HX OUTLET 19 6 T616 CCU PUMP SUCT1ON HDR TEMP 19 32 a
e
e- SCREEN o 71 RMS Centainmont/ Facade Point Id Description Row Column
============================================
R1E102 UNji 1 CONTAINMENT RADIATION 5 4 R2E102 UNIT 2 CONTAINMENT RADIATION 5 18 R1E107 U1 SEAL TABLE RADIATION 5 49 R2E107 U2 SEAL TABLE RADIATION 5 62 R1E212 U1 CONT GAS RADIATION 9 4 R2E212 U2 CONT GAS RADIATION 9 17 R3E211B U1 CONT GAS BACKGROUND RADIATION 9 52 R2E211B~ U2 CONT SAS BACKGROUND RADIATION 9 66 R1E211- U1 CONT A]R' PARTICULATE RAD 11 43 R2E211 U2 CONT AIR PARTICULATE RAD 11 64 R1E222- U1 BLOUDOUN TANK OUTLET RAD 16 10 R2E222 U2 BLOUDOUN TANK OUTLET RAD- 16 23 R1E231 U1 STEAM RELEASE LINE A RAD 16 52 R2E231 U2 STEAM RELEASE LINE A RAD 16 65 RE214 = AUX BLDG EXHAUST VENT GAS RAD 19 16 e R1E232 U1-STEAM RELEASE LINE B RAD 2D 53 R2E232 U2.51EAM RELEASE L]NE B RAD 2D 66 RE224 GAS STRIPPER BUILDING RADIATION 22 11 l
l l
1 l
7 _-
ECREEN a Bi RMS Aux Buildins Unit 1 L 2 Aroso i
[ Point Id Description Row Column
==============================================
R1E104 U1 CHARGING PUMP ROOM RADIATION- 5 34 R2E104 U2 CHARGING PUMP ROOM RADIATION 5- 57 L R1E134 U1 CHARGING PUMP ROOM HI RNG RAD 6 34 R2E134 U2 CHARGING PUMP ROOM HI RNG RAD 6 57 R1E106 U1 SAMPLING ROOM RADIATION 8 34 R2E106 U2 SAMPLING ROOM RAD 3ATION 8 57
!- R1E136 U1 SAMPLING ROOM HI RNG RAD 9 34 R2E136 U2 SAMPLING ROOM HI RNG RAD 9 57 R1E2168 U1 CONT FAN CLRS LlO BACKGND RAG 12 34
-R2E216B U2 CONT FAN CLRS LIO BACKGND RAD 12 57 R1E219B U1 S/G BLOUDOWN LIQUlO BKGND RAD 15 34 R2E219B' U2 S/G BLOUDOWN LIQUID BKGND RAD 15 57 R1E2298 U1 SERVICE WATER DISCH BKGND RAD 18 34 R2E229B U2 SERVICE WATER DISCH BKGND RAD 18 57 :
R1E109 U1 SAMPLE LINE RADIATION 20 34
. R2E109 U2 SAMPLE LINE RADIATION 20 57 I
i i
l I
r;; 'l
- SCREEN o'7; RMS Aux Buildine Common Aroc/sux Buildine Uctor Point Id Description Row Column S53R3333333333333333333E3338833333333A3333333355233333335
~RE103 RADIOCHEMISTRY LAB RADIATION 3 24 RE110 SAFETY INJECTION PUMP ROOM RAD 3 61 RE116 VALVE GALLERY RADIATION 4 24 RE140 S.I. PUMP ROOM HI RANGE RAD 4 61 RElli C-59 PANEL RADIAT]ON 5 24 ,
RE112 CENTRAL PAB RADIATION 5 61 RE1'13 AUX BUILDING SUMP RADIATION 6 24 RE114 CVCS HOLDUP TANK RADIATION 6 61 RE223B UST DIST'OVRBRD-LIO MON BKGD RAD 8 42 RE2189 UASTE DISP SYST LIO BKGND RAD 9 42 RE218 UASTE DISPOSAL SYSTEM LIQUID RAD 13 47 RE223 UASTE DIST OVRBRD L10 MON RAD 14 47 R1E216 U1 CONT FAN COOLERS LIQUID RAD 18 5 R2E216 U2 CONT FAN COOLERS LIQUID RAD 16 24 R1E217 U1 COMPONENT CLNG LOOP LIQ RAD 18 44 R2E217 U2 COMPONENT CLNG LOOP LIO RAD 16 62 R1E229 U1 SERV]rE UATER DISCHARGE RAD 21 62 R1E219 U1 S/G BLOUDOUN LIQUID RAD 22 4 R2E219 U2 S/G BLOUDOUN L10UID RAD 22 21
p, p f t;,
-[
l SCREEN lc~Al Drumming Area / Spont Fuel-Pool' l, Pointfid Description ~ Row Column 33333333333333333333333343533333333333333333333333333333 RE108 DRUMMING STATION RADIATION 3 -31 ,
RE221- ' DRUMMING AREA VENT GAS RADIATION 4 31
. RE105' . SPEND' FUEL PIT RADIATION 10- 41 : .c RE135 SPENT-FUEL PIT HIGH RANGE RAD 11 41
-RE220 SPENT FUEL plt LIQUID RADIATION ~ 12 41 13 ' 41-
,RE220B SPENT FUEL PIT LlOUID BKGND RAD t
[
9 4
D. . ..
~
SCREEN.5 Bl. Control Room / Turbine Half Point Id Description Row Column assammassmas,ssumesssssssammasssesssssssssssssssssssssamas R1E306' U1 CONT PURGE AREA MONITOR RAD 3 58 R7E306 U2 CONT PURGE AREA MONITOR RAD 4 58 RE316 AUX BLOG EXH AREA MONITOR BCKGND 5 56 RE234 CTRL RM VENT JODINE MONITOR RAD 9 39 RE234B CTRL'RM VENT IODINE ON BKGD RAD 1D 39 i RE235 CTRL RM VENT NOBLE GAS MON RAD 11 39-RE226 COMBINED AIR EJECTOR HI RNG RAD -15 45 RE23D LIOUlD RETENTION POND DISCH RAD 16- 45 RE23DB LIO RETN POND DISCH BKGND RAD 17 45 ,
3 R2E229 U2-SERVICE UATER DISCHARGE RAD 18 -45 !
R2E2298 U2 SERVICE UATER DISCH BKGND RAD 19 45 R1E215 U1 CONDENSER AIR EJECTOR GAS RAD 20 53 R2E215 U2 CONDENSER AIR EJECTOR GAS RAD 21 53 i
i
, i
=
I a l
i
7, px '
. ; :. gg s J Att BChmen't ; 4 -
T E SCHMlUt Oi .
i N ,
KEWAUNEE COUNTY if ARVEY DMMcW A*( J'8 c DMSION OF EMERGENCY co sn f GOVERNME NT--
416 F R1MONT ET.
J AlnOt.* A, WISCONSIN LeM1 ' ,
_Mr. C._W. Fay Vic o -' Pre s i den t , Nucicar Power y WISCONSIN-ELECTR C-POWER COMPANY t P.O. Box 2016 231 West Michigar., P377
-Milwaukee, Wisconsin- 53203
+
Dear.Mr. Fay:
L
, As:participante in rho radiological emergency planning efforts for the Point Beach Nuclear Plant, you requested our approval to reloceto the Alternate Emergency Operations Facility' ( ACOF) fcr l PD!iP-frem the Wisconsin Public Service District Office in Two Rivers, Wisconsin,-to the Wisconsin Electric Power Company corporate offices in Milwaukoc. This move is desirable since the-present- f acility is rio longer used as an Emergency Operations Facility by. Wisconsin-Public Service and that tho' space may be needed by them for future use.
We-agree with the proposed relocation of the AEOF to the corporato ,
l offices, and understand that this move will take place only upon the approvar of_the Nuclear Regulatory Commission.
Very truly yours,
- ?
.a -
/
Lyl E. Schmil.ing Harold Rockelberg Director Board Chairman Kowaunee County Emergency Kewaunce County
- Covernment >
z n
l l
i.auenico L SEP 011989 L POINT BEACH l
,l E O* T .,, '.CopiGsl to Lipko, Ecch CWF 8/15 /89 geg,,.,,q ,,g.,
ATTACHMENT 5-Q g- per n q y,.
ILt t . f i
- NANCY H. CROWLgy MOMNOW Qung 1026 South Nmth Street =
Manetowoe, w,econs,n ;
Emefpency Government Director Phone 414 4493071 August 14,:1989 .
- i h
-C. W. Tay Vice President, Nuclear Power ,
~ Wisconsin Electric Power Company' P.O. Box 2046 Milwaukee, WI_-53201
Dear Mr. Tay:
I Manitovoc County has no objection to Wisconsin Electric Power Company establishing an Alternate Emergency Operations Tacility (AEOT) at WEPCO's corporate offices in Milwaukee. It is our understanding the ,
move is desirable since your present AEOF, located at-the Wisconsin-Public Service Company District Office in Two Rivers, is no longer used as an Emergency Operations Tacility by WPS and it may be needed for c,ther use by that company in future.
Manitowoc County officials feel comfortable with the fact excellent communications exist-between your on-site EOF and the County. -We are confident that would most' assuredly also be the case between a relocated AEOT, even if it is located more than 20 miles from the plant l site-and the County EOC,
- We understand this move will take place only upon the approval of the.
1 Nuclear Regulatory Commission.
L.-
Sincerely, I:
) MASITOWOC C0t'NTY EMERGENCY GOVERNMENT l '
<~. .
L k*
ancy' . Crowley Donald A. Rehbein, Chairman D' rect r Manitowoc County Board ]
l b'C h mlp \
corr \cvfay l l
1--
l l
1 nerivto NUCLEAR LhGELR.hG AUG 151989 i
F ..* ...,.. ;... .r...,.....
x .. .
B/25/89. '
Tome > G.%ompson Maihng Address:
L w ' Gosernor _ Post Oike Bos 76tf
- Janws R. Elemmer , Madison. WI !)707 '665 :
1 Secretary Phone: 606 066 3 30 .
. . ATTACHMENT 6 g State Of WISCORSm
' Department of ~ Administration- -
4800 Sheboygan Asenue. Ronm 99A
- August 23,1989 NOLP!.'.MA'i!!Ji, _Yr.;
. 7 hLt N3. __
Mr. C. W. Fay Vice President, Nuclear Power
' Wisconsin Electric Power Company '
P.O. Box 2046 231 West Michigan P377 ;
Milwaukee, WI 53201 s / --
Dear Mr. Fay:
As participants in the radiolt,gical emergency planning efforts for the Point Beach Nuclear Plant, you requested our approval to relocate the Alternate Emergency Operations Facility (AEOF) for PBNP from the Wisconsin Public Service District Office in Two Rivers, Wisconsin, to the Wisconsin Electric Power Company corporate offices in Milwaukee. This move is desirable since the present facility is no longer used as an Emergency Operations Facility by Wisconsin Public Service and that the space may be needed by them for future use.
We agree with the proposed relocation of the AEOF to the corporate offices, and understand that this move will take place only upon the approval of the Nuclear Regulatory Commission, Very truly yours,
- WISCONSIN DIVISION OF EMERGENCY GOVERNMENT l ' .' m
) ..D 1
k < t b y . % .8 K k .<
Richard.I. Braund Administrator l
l Ilk 2 1:
l~
l-1 ptCttV' s g 2:19E9 NUCL! Ail E W h 8