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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:EXTERNAL CORRESPONDENCE
MONTHYEARML20081G2581995-03-15015 March 1995 Forwards Petitioner Petition for Review in Citizens Utility Board Vs Public Svc Commission of Wi,Along W/Appropriate Filing Fee.Requests Copies Be File Stamped & Returned to Messenger ML20079H5561991-09-18018 September 1991 Forwards Matl Requested Through R Samworth Re Inservice Testing Program at Facility ML20059P0651990-10-10010 October 1990 Forwards USGS Quadrangle Map Showing Plant Location & Facility Outfalls (Latitude/Longitude Verification),Per Wpdes Permit WI-000957 ML20006C8311990-02-0202 February 1990 Forwards Storm Water Permit Application for Plant,Reflecting Util Effort to Comply W/Requirements of Clean Water Act ML20148B3831988-03-0101 March 1988 Forwards Scope & Objectives for Plant Medical Emergency Drill Scheduled for 880316.Drill Being Conducted in Conjunction W/Annual Util Medical Emergency Drill & Designed to Allow for Succesful Demonstration of Offsite Objectives ML20207S5481987-03-11011 March 1987 Responds to 870306 Request for Info Re Use of Energy Absorbers on Main Steam Dump Sys to Complete Ser.Proposed Use of Energy Absorbers in Inservice Insp Program Described. Stated Encls Withheld ML20209J2701987-01-22022 January 1987 Marked-up Confirmation of Responses to Questions Re Modeling of Piping in Relief Valve Manifold,Per Mainstream Outside Containment Energy Absorber application.ME101 Analysis of Sys Weight & Thermal Expansion Load Also Encl.W/O Encls ML20209J4961986-12-16016 December 1986 Forwards Bechtel-generated Artificial Time History for SSE Horizontal Component Used in Analysis of Main Steam Dump Sys,Per 861211 Meeting.Bechtel Review of SRP 3.7.1 Also Discussed.W/O Encls ML20209J3201986-12-0808 December 1986 Forwards ME101 Analysis Listing & Computer Generated Plot for Main Steam Dump Sys Supported W/Energy Absorbers. Analysis Listing Includes Original Input Listing,Interpreted Listing for Weight & Seismic Analyses.W/O Encls ML20076B2311983-08-0505 August 1983 Advises That State of Wi Dept of Natural Resources Notified on 830603 That Ph of Retention Pond Discharge Was 9.4. Investigation Failed to Reveal Cause.Util Requested Removal of Ph Limits on Sewage Treatment Plant & Pond Effluents ML20072C5051983-06-16016 June 1983 Requests Mod to Wpdes Permit WI-0000957-2,removing Ph Limitations on Sewage Treatment Plant & Retention Pond Effluents.Mod Will Allow Operation of Plant & Pond W/Reduced Additions of Dissolved Solids to Environ ML20072F1431983-06-16016 June 1983 Requests Mod to Wpdes Permit WI-0000957-2 to Remove Ph Limitations on Sewage Treatment Plant & Retention Pond Effluents.Removal of Limits Will Allow Operation W/Reduced Additions of Dissolved Solids to Environ ML20027D0981982-10-25025 October 1982 Advises That Util Requested to Send FSAR Chapter 14 Safety Analyses to Wi Environ Decade,In Ref to 821018 Telcon.Svc List Encl.Related Correspondence ML20065P9971982-10-22022 October 1982 Ack Receipt of Requesting Documents.Util Will Cooperate But Is Not Required to Respond Since Nonparties Not Entitled to Discovery ML20063M2221982-09-0303 September 1982 Clarifies Agreement Re Licensee 820722 Discovery Requests Commemorated in Wi Environ Decade .Svc List Encl. Related Correspondence ML20054M7651982-07-0606 July 1982 Forwards RA Wiesemann 811117 Affidavit,Page 5.Westinghouse No Longer Claims Affidavit Entirely Proprietary But Only Contains Proprietary Info.No Arguments Waived by Furnishing Page 5.W/o Encl ML20054K6251982-06-29029 June 1982 Responds to Util 820621 Response to Second Interrogatories, Correcting Unwarranted & Gratuitous Comments ML20054J0711982-06-22022 June 1982 Lists Errors in Transcription of Ga Reed 770718 Memo to Burstein & TR Wilson Re Meeting W/Westinghouse on Steam Generator Tube Plugging.Svc List Encl ML20011A6871981-10-23023 October 1981 Confirms That Recipient Will Serve Encl Documents on ASLB & Nrc,For Wi Environ Decade.Documents Consist of Interrogatories Directed to Util,Response to Util Motion for Summary Disposition & Decade 811023 Ltr.W/O Encl ML20010E4281981-08-27027 August 1981 Forwards Addl Info Re Environ Qualification of Electrical Equipment Installed to Meet NUREG-0737 Requirements,In Support of Franklin Research Ctr Review of Util 810130 Response to IE Bulletin 79-01B,Suppl 3.W/o Encl ML20064K4201980-12-0909 December 1980 Notifies That Lakeshore Citizens for Safe Energy Is Being Disbanded Per 781208 Agreement ML19338F5241980-09-30030 September 1980 Responds to 800912 Request for Permission to Perform eddy-current Insp on Several Hot Leg Steam Generator Tubes. Insp May Be Scheduled During Nov Outage.Ga Reed Should Be Contacted for Scheduling & Security Details ML19331D1691980-08-0404 August 1980 Submits Info Requesting NRC Support of Adjudicatory Hearing to Examine Tube Degradation Problem & Related Safety Issues ML19208B7921979-09-17017 September 1979 Responds to 790906 Ltr Re Aug Tube Failures.Forwards Repts Re Outages.Implication That Present & Anticipated Tube Failures Are Related to Major Accidents Is Not Supportable. W/O Encl 1995-03-15
[Table view] Category:EXTERNAL LETTERS ROUTED TO NRC
MONTHYEARML20006C8311990-02-0202 February 1990 Forwards Storm Water Permit Application for Plant,Reflecting Util Effort to Comply W/Requirements of Clean Water Act ML20148B3831988-03-0101 March 1988 Forwards Scope & Objectives for Plant Medical Emergency Drill Scheduled for 880316.Drill Being Conducted in Conjunction W/Annual Util Medical Emergency Drill & Designed to Allow for Succesful Demonstration of Offsite Objectives ML20207S5481987-03-11011 March 1987 Responds to 870306 Request for Info Re Use of Energy Absorbers on Main Steam Dump Sys to Complete Ser.Proposed Use of Energy Absorbers in Inservice Insp Program Described. Stated Encls Withheld ML20209J2701987-01-22022 January 1987 Marked-up Confirmation of Responses to Questions Re Modeling of Piping in Relief Valve Manifold,Per Mainstream Outside Containment Energy Absorber application.ME101 Analysis of Sys Weight & Thermal Expansion Load Also Encl.W/O Encls ML20209J4961986-12-16016 December 1986 Forwards Bechtel-generated Artificial Time History for SSE Horizontal Component Used in Analysis of Main Steam Dump Sys,Per 861211 Meeting.Bechtel Review of SRP 3.7.1 Also Discussed.W/O Encls ML20209J3201986-12-0808 December 1986 Forwards ME101 Analysis Listing & Computer Generated Plot for Main Steam Dump Sys Supported W/Energy Absorbers. Analysis Listing Includes Original Input Listing,Interpreted Listing for Weight & Seismic Analyses.W/O Encls ML20076B2311983-08-0505 August 1983 Advises That State of Wi Dept of Natural Resources Notified on 830603 That Ph of Retention Pond Discharge Was 9.4. Investigation Failed to Reveal Cause.Util Requested Removal of Ph Limits on Sewage Treatment Plant & Pond Effluents ML20072F1431983-06-16016 June 1983 Requests Mod to Wpdes Permit WI-0000957-2 to Remove Ph Limitations on Sewage Treatment Plant & Retention Pond Effluents.Removal of Limits Will Allow Operation W/Reduced Additions of Dissolved Solids to Environ ML20072C5051983-06-16016 June 1983 Requests Mod to Wpdes Permit WI-0000957-2,removing Ph Limitations on Sewage Treatment Plant & Retention Pond Effluents.Mod Will Allow Operation of Plant & Pond W/Reduced Additions of Dissolved Solids to Environ ML20027D0981982-10-25025 October 1982 Advises That Util Requested to Send FSAR Chapter 14 Safety Analyses to Wi Environ Decade,In Ref to 821018 Telcon.Svc List Encl.Related Correspondence ML20065P9971982-10-22022 October 1982 Ack Receipt of Requesting Documents.Util Will Cooperate But Is Not Required to Respond Since Nonparties Not Entitled to Discovery ML20063M2221982-09-0303 September 1982 Clarifies Agreement Re Licensee 820722 Discovery Requests Commemorated in Wi Environ Decade .Svc List Encl. Related Correspondence ML20054M7651982-07-0606 July 1982 Forwards RA Wiesemann 811117 Affidavit,Page 5.Westinghouse No Longer Claims Affidavit Entirely Proprietary But Only Contains Proprietary Info.No Arguments Waived by Furnishing Page 5.W/o Encl ML20054K6251982-06-29029 June 1982 Responds to Util 820621 Response to Second Interrogatories, Correcting Unwarranted & Gratuitous Comments ML20054J0711982-06-22022 June 1982 Lists Errors in Transcription of Ga Reed 770718 Memo to Burstein & TR Wilson Re Meeting W/Westinghouse on Steam Generator Tube Plugging.Svc List Encl ML20011A6871981-10-23023 October 1981 Confirms That Recipient Will Serve Encl Documents on ASLB & Nrc,For Wi Environ Decade.Documents Consist of Interrogatories Directed to Util,Response to Util Motion for Summary Disposition & Decade 811023 Ltr.W/O Encl ML20064K4201980-12-0909 December 1980 Notifies That Lakeshore Citizens for Safe Energy Is Being Disbanded Per 781208 Agreement ML19338F5241980-09-30030 September 1980 Responds to 800912 Request for Permission to Perform eddy-current Insp on Several Hot Leg Steam Generator Tubes. Insp May Be Scheduled During Nov Outage.Ga Reed Should Be Contacted for Scheduling & Security Details ML19331D1691980-08-0404 August 1980 Submits Info Requesting NRC Support of Adjudicatory Hearing to Examine Tube Degradation Problem & Related Safety Issues ML19208B7921979-09-17017 September 1979 Responds to 790906 Ltr Re Aug Tube Failures.Forwards Repts Re Outages.Implication That Present & Anticipated Tube Failures Are Related to Major Accidents Is Not Supportable. W/O Encl 1990-02-02
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Wisconsin 1 Electnc POWfR CO?.fPANY Pont Beocn Nuc'ect Pont /S4) 755*U21 6610 Nuc'ect Rd Two T<ven.VA 54241 March 1, 1988 Mr. Wallace Weaver FEMA Region V 175 W. Jackson, 4th Floor Chicago, IL 60604
Dear Mr. Weaver:
SCOPE AND OBJECTIVES - POINT BEACH NUCLEAR PLANT MEDICAL EMERGENCY DRILL, MARCH 16, 1988 Enclosed is a copy of the "Scope and Objectives for the Point Beach Nuclear Plant Medical Emergency Drill," scheduled for March 16, 1988. As you know, this is a drill and not an. exercise. This drill is being conducted in conjunction with tre annual utility medical emergency drill and is designed to allow for successful demonstration of offsite objectives pertaining to medical services, the conduct of this medical drill is in keeping with the requirement of the FEMA guidance memorandum MS-1, "Medical Services," and specific objectives to be demonstrated are described in the November 4,1987 draft of FEMA guidance memorandum EX-3, "Managing Pre-Exercise Activities and Post-Exerciso Meetings."
A time schedule of real and simulated events for the drill is also enclosed.
If you have any questions regarding the content of the enclosures, please contact our emergency planning coordinator, David R. Stevens at (414)755-2321.
Very truly yours, f
/
Me w 'b Je MabesJ.Zach ger - PBNP Pah ll } ,
l Attachments bec: R. I. Braund D. R. Stevens N. H. Crowley J. J. Zach/11150100
- Ray Kellogg NRC Document Control Desk ,
l F.. J. Lipke/R. A. Newton NRC Region III l L. Schmiling NRC Resident Inspector, PBNP
( D. R. Seehave 1
8803210491 G80301 l EDq ADOCK 05000266 4,g,ga,,. g u;yons, 3,p c,3y,f,
o POINT BEACH NUCLEAR PLANT MEDICAL EMERGENCY DRILL MARCH 16, 1988
1.0 INTRODUCTION
1.1 This drill will involve activation ot'onsite and offsite human
~
resources and facilities necessary to respond to a simulated medical emergency at the Point Beach Nuclear Plant involving radioactive contamination of the victim.
1.2 The drill will be conducted during normal day shift working hours and will last from 4 to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
1.3 This drill is designed to satisfy the requirements of:
1.3.1 Point Beach Nuclear Plant Emergency Plan, Chapter 8.0, Section 3.5.3.
1.3.2 NUREG 0654, Planning Standard N.2.c.
1.3.3 FEMA Guidance Memorandum MS-1, Medical Services.
1.3.4 FEMA Guidance Memorandum (Draft, November 4, 1987)
EX-3, Objectives 23 and 24.
_s .
- MEDICAL EMERGENCY DRILL Page 2 2.0 PARTICIPATING ORGANIZATIONS 2 .1 - Wisconsin Electric Power Company 2.1.1 Nuclear Power Department 2.1.2 Communications Department 2.1.3 Other departments as required 2.2 Manitowoc County The Manitowoc County Sheriff's Department will participate in the drill primarily from a communications standpoint. However, the department will coordinate the actual dispatch of a medical emergency vehicle to the Point Beach Nuclear Plant. It should be noted that the ambulance service and hospital facilities used during this drill are the same as those which would be used should an accident occur which involved injury and radioactive contamination of a member of the offsite public in Manitowoc County. -
2.3 Two Rivers Community Hospital The Two Rivers Community Hospital (TRCH) will implement appropriate portions of their "Condition Black - Nuclear" emergency response plan,
- as required by the scenario.
2.4 Mishicot Area Ambulance Service The Mishicot Area Ambulance Service will respond, to the fullest extent, to the simulated medical emergency.
! 2.5 Kewaunee County Kewaunee County will participate in the drill from a communications standpoint. It should be noted that the ambulance service and hospital facilities used during this drill are the same as those which would be used should an Occident occur which involved injury l
i and radioactive contamination of a member of the offsite public in Kewaunee County.
2.6 State of Wisconsin I
The 31 vision of Emergency Government will support the drill from a I
commc71 cations standpoint. Communicators will participate from Warning Center 2 at the State EOC.
. MEDICAL EMERGENCY DRILL Page 3 3.0 OBJECTIVES 3.1 Wisconsin Electric 3.1.1 General
- a. Involve a local ambulance service in a medical emergency response to PBNP involving a victim with injuries complicated by radioactive contamination.
- b. Provide a situation which will cause the PBNP Health Physics group to work with a local ambulance service in transporting a contaminated-injured person from the plant site to the Two Rivers Community Hospital.
- c. Provide a number of simulated victims with varying injuries or radiation overexposures which will cause the Two Rivers Hospital to implement their "Condition Black-Nuclear" policy.
- d. Provide a simulated event which will cause implementation of various portions of:
- 1. EPIP 11.2, "Injured Person's Immediate Care"
- 2. EPIP 11.3, "Hospital Assistance"
- e. Demonstrate the ability of onsite personnel to assess the nature of a victim's injuries and to administer appropriate first-aid in response to that assessment.
- f. Demonstrate the ability of onsite personnel to muster necessary first-aid equipment (e.g., trauma kit, stretcher, etc.) at the scene of the injury.
- g. Demonstrate the ability of onsite personnel to notify the control room in a timely fashion following discovery of an injured person.
- h. Demonstrate the ability of onsite personnel discovering an injured person to communicate the following information to the control room:
- 1. Location of accident scene
- 2. Assistance required l
t MEDICAL EMERGENCY DRILL Page 4
- 1. Demonstrat' timely notification of onsite emergency response personnel of an emergency plan activation.
- j. Demonstrate timely notification of key corporate emergency support personnel:
- 1. Emergency support manager
- 2. Emergency director
- 3. Vice-president communications (or designee)
- k. Demonstrate the ability of emergency response facilities to communicate using, as appropriate, the following:
- 1. Dedicated telephone lines
- 2. Radio
- 1. Demonstrate the ability to provide regular (e.g., hourly) status reports to the NRC.
- m. Demon' strate the ability of personnel using radios to communicate effectively.
3.1.2 Control Room .
- a. Demonstrate the ability to coordinate the immediate response to a report of personnel injury complicated by radioactive contamination.
- b. Demonstrate the ability to perform communications necessary to obtain offsite medical assistance for PBNP ,
personnel with injuries complicated with radioactive contamination. This includes notification of:
- 1. The Manitowoc County Sheriff's Department
- 2. The Two Rivers Community Hospital
- c. Demonstrate the ability of control room perscnnel to accurately communicate the following information to the Two Rivers Community Hospital in advance of their receipt of injured personnel:
- 1. Number of victims
- 2. The victims' condition
, MEDICAL EMERGENCY DRILL Page 5
- 3. Whether the victims are clean or contaminated
- 4. Expected time of arrival of ambulance at the nuclear first aid room (NFAR).
- d. Demonstrate the ability of control room staff to correctly classify an emergency event using EPIPs 1.1 and 1.2.
- e. Demonstrate the ability to notify onsite personnel of emergency classification using the plant Gai-tronics and alarm system.
- f. Demonstrate the ability to notify the State DEG and both counties of event classification within 15 minutes using
-EPIP 1.3.
- g. Demonstrate the ability to notify the NRC within one hour of event classification using EPIP 1.3.
- h. Demonstrate the ability to provide regular (e.g. , hourly) status reports to appropriate state and county agencies,
- i. Demonstrate the ability of the shift superintendent to request of the Manitowoc County Sheriff's dispatcher that a contaminated ambulance remain at.the TRCH until decontamination is complete.
3.1.3 Health Physics Support
- a. Demonstrate the ability to organize, dispatch, and manage a first aid team into a contaminated area.
Demonstrate the use of respiratory protection equipment b.
and associated communications equipment (skull mikes, boom boxes, etc.) as is deemed necessary by the supervisor in charge.
Demonstrate the ability to monitor and control exposure c.
of all persons assigned to the medical emergency l
response.
- d. Demonstrate the ability and resources necessary to properly outfit response teams with protective clothing based upon anticipated environmental conditions.
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. MEDICAL EMERGENCY DRILL Page.6
- e. Demonstrate the ability to assure contamination control:
- 1. At.the plant site
-2. In the ambulance
- f. Demonstrate the ability to assist offsite medical' -
emergency responders in donning protective clothing. !
- g. Demonstrate the d3111ty to arrive at the Two Rivers Community Hospital nuclear first aid room in advance of an ambulance dispatched from the PBNP site.
- h. Demonstrate the ability to set up the nuclear first aid room at the TRCH in a timely fashion.
- i. Demonstrate the ability to provide contamination and exposure centrol during transfer of a contaminated-injured victim from a contaminated area to a medical emergency vehicle.
- j. Demonstrate the ability to provide contamination and exposure control at the nuclear first aid room.
- k. Demonstrate the ability to assist hospital personnel in the decontamination of the victim.
- 1. Demonstrate the ability to control and minimize the spread of contamination at the Two Rivers Community Hospital.
- m. Demonstrate the ability to monitor hospital personnel entering and leaving the restricted area estahlished at the TRCH.
i n. Demonstrate the ability to decontaminate the treatment room, adjoining areas, equipment and the ambulance as required.
1 l o. Demonstrate the ability to bag and label all disposable or contaminated items at the TRCH.
3.1.4 Security
! a. Demonstrate the ability to obtain preassembled emergency entrance packets for dissemination to the ambulance crew following notification from the Control Room.
,. MEDICAL EMERGENCY DRILL Page 7
- b. Demonstrate the ability to rezero dosimeters contained in the emergency entrance packets.
- c. Demonstrate. the ability to provide a rapid entry of a medical emergency vehicle to the plant site.
- d. Demonstrate the ability to obtain the last name of each offsite medical emergency responder upon entry to the site.
- e. Demonstrate the daility to control access to the plant site.
3.1.5 Communications Department
- a. Demonstrate the ability to provide accurate and timely information to the public.
- b. Demonstrate the ability to provide advance coordination with offsite agencies of information released to the public.
3.2 Mishicot Ambulance ~
Demonstrate the adequacy of vehicles, equipment, procedures and personnel for transporting contaminated, injured or exposed individuals. (FEMA Objective #23) 3.3 Two Rivers Community Hospital 3.3.1 Demonstrate the adequacy of hospital facilities, equipment, procedures and personnel for handling contaminated, injured or exposed individuals. (FEMA Objective #24) 3.3.2 Demonstrate the ability to staff the nuclear first aid room with one doctor and one nurse trained to handle a radiological medical emergency.
3.4 Manitowoc County 3.4.1 Demonstrate the adequacy of vehicles, equipment, procedures and personnel for transporting contaminated, injured or exposed individuals. (FEMA Objective #23) 3.4.2 Demonstrate the adequacy of hospital facilities, equipment, ,
procedures and personnel for handling contaminated, injured or exposed individuals. (FEMA Objective #24) ,
, MEDICAL EMERGENCY DRILL Page 8 3.5 Kewaunee County 3.5.1 Demonstrate the adequacy of vehicles, equipment, procedures and personnel for transporting contaminated, injured or exposed individuals. (FEMA Objective #23) Although the Mishicot Ambulance is not the primary responder to an offsite contaminated-injury event in Kewaunee County, such service would be provided under the provisions of mutual aid agreements.
3.5.2 Demonstrate the adequacy of hospital facilities, equipment, procedures and personnel for handling contaminated, injured or exposed individuals. (FEMA Objective #24)
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- MEDICAL EMERGENCY DRILL Page 9 4.0 DRILL SCOPE The 1988 Point Beach Nuclear Plant Medical Emergency Drill will require implementation of portions of the Point Beach Nuclear Plant Emergency Plan Implementing Procedures. Response by Health Physics, operations, Security, and Communications personnel will be required. Additional company groups may become involved depending-upon the actions of drill players.
The drill will require dispatch of the Mishicot Area Ambulance by the Manitowoc County Sheriff's Department to the Point Beach Nuclear Plant and subsequent transport of at least one contaminated-injured victim from the plant site to the Two Rivers Community Hospital.
The drill scenario will require implementation of the Two Rivers Community Hospital "Condition Black - Nuclear Policy." Implementation of this policy will result in use, at a minimum, of the nuclear first aid room (NFAR), for patient decontamination and treatment.
The events which lead up to the required medical emergency response are as follows:
A routine transfer of radioactive resins from a storage tank to a shipping liner will be simulated at the Point Beach Nuclear Plant. During the transfer operation a leak develops at the camlock hose fitting on top of the shipping liner. Immediate attempts to secure the resin flow are unsuccessful due to a valve sticking open (A0V-14). A contractor technician climbs atop the shipping liner and attempts to retighten the camlock to prevent the leakage. Upon touching the camlock, the hose blows off the fitting, contaminating and knocking the technician from the liner top to the floor. As a result of the fall, the technician suffers a severe laceration of the head and a compound fracture of the leg. He is conscious and bleeding severely. Contaminated resin continues to flow from the hose for about 60 seconds. The radwaste supervisor in charge of the transfer operation is severely exposed, but not contaminated.
The drill will be terminated upon satisfaction of drill objectives. This is likely to occur shortly af ter the contaminated victim has been decontaminated, medical conditions have been stabilized and he has been moved to a "clean" area for continued medical evaluation and treatment.
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4 POINT BEACH NUCLEAR PLANT MEDICAL EMERGENCY DRILL MARCH 16, 1988 TIME SCHEDULE OF REAL AND SIMULATED SCENARIO EVENTS 0730 Plant employees begin work day.
0745 Pre-job discussion with contractor HPs, Operations supervisor, shift superintendent, 9E HPs and auxiliary operators in preparation for resin transfer per Operating Instruction 20, Attachment F.
"Resin Transfer from Storage Tank T112 to Shipping Liner on Truck Via ATCOR Bypass Line."
0800 Initiate resin transfer procedure.
0805 Resin flow into shipping liner begins.
0810 Dump hose connection on fill head begins to leak.
0811 Chem-nuclear technician and radwaste supervisor position ladder on the west side of the liner to observe and verify the leak. Leak appears to be caused by loose wing on the camlock fitting.
Radwaste supervisor orders the resin dump to be terminated.
Air operated valve 14 (A0V 14) sticks open preventing immediate tenmination of the resin dump.
0812 Chem-nuclear technician goes on top of the shipping liner and attempts to resecure the camlock. fitting. Upon touching the camlock, the dump hose blows off the fitting initiating a spill of radioactive resin and water.
The Chem-nuclear technician is knocked from the shipping liner top to the floor by the resin dump hose. He has suffered a severe laceration to the face and compound fracture of the leg. He is conscioun, but bl:2 ding severely from the fracture wound. He is 1kying in an area now contaminated by water and resin.
0813 The radwaste supervisor's protective clothing is slightly contaminated and he has received a significant overexposure.
Area radiation monitor, RE-l'80 alarms in the control room indicating high activity in the radwaste area.
d 0815 WE personnel report to the accident scene; a limited plant evacuation is possible.
0820 Dose rates in the general area are reduced by factor of 10 due to the resin pile going down the drain to the -19'. sump.
Area radiation monitor, RE-108 clears in the control room.
(0825) PBNP control calls the Manitowoc County sheriff to request an ambulance.
(0830) Manitowoc County Sheriff's Department notifies the Mishicot Ambulance Service that a response to PBNP is required.
(0835) - The Two Rivers Community Hospital is notified by the Point Beach Control Room that at least one injured person will be transported to the TRCH.
(0840) Two Rivers Community' Hospital calls PBNP to verify the message received from PBNP.
(0845) The Mishicot Ambulance arrives at the PBNP southgate.
(0855) Emergency medical technicians arrive at scene of victim.
PBNP Health Physics personnel depart for the Two Rivers Community Hospital to aid in setup of the NFAR.
(0915) PENP will activate the technical support center to coordinate event response and post-accident cleanup.
(0915) The victim is moved from the PBNP controlled zone to the Mishicot Ambulance. The ambulance becomes contaminated.
(0925) PBNP declares an Unusual Event due to the transportation of a seriously injured person to a hospital from the plant site.
(0930) The Mishicot Ambulance departs the PBNP site for the Two Rivers
, Community Hospital.
(0940) The state and counties are notified of the Unusual Event declaration by PBNP.
(0945) The Mishicot Ambulance arrives at the Two Rivers Community Hospital.
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(1000) The NRC is notified of the Unusual Event declaration by PBNP.
(1015) The injured victim's medical condition is stabilized.
(1030) The injured victim has been successfully decontaminated.
The Mishir:ot Ambulance has been surveyed and decontaminated.
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(1045)
(1100) The TRCH nuclear first aid room has been successfully decontaminated.
(1130) The drill is terminated when the injured victim has been stabilized and transporteo 2 rom the NFAR and when the exposed victim has been evaluated and a treatment plan developed.
(1230) Post-drill critique at the Two Rivers Community Hospital
- 1. Hospital staff
- 2. Mishicot Ambulance staff
- 3. Wisconsin Electric HP supervision from the site and the NFAR Times noted in parenthesizes are estimated. The time that each of the events occurs is dependent upon player actions and response.
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