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Category:MEETING MINUTES & NOTES--CORRESPONDENCE
MONTHYEARML20134M3841997-02-13013 February 1997 Summary of 970128 Meeting W/Util to Discuss Program to Dispose of Weapons Grade Pu Through Use as Mixed Oxide Fuel. List of Attendees & Matl Used in Presentation Encl ML20059J8071994-01-19019 January 1994 Summary of Operating Reactors Events Meeting 94-02 on 940112 ML20217D4611993-12-0808 December 1993 Summary of 931206 Meeting W/Commonwealth Edison Co Re Items of Mutual Interest Re Operations at Utilities Nuclear Power Plants,W/Special Attention Devoted to Activities at Quad Cities Nuclear Station,Units 1 & 2 ML20058M5891993-09-27027 September 1993 Summary of Operating Reactors Events Meeting 93-36 on 930922 ML20058M1861993-09-22022 September 1993 Summary of Operating Reactors Events Meeting 93-35 on 930915 ML20149D6051993-09-15015 September 1993 Summary of 930708 Region III Annual Training Managers Conference in Glen Ellyn,Il.Purpose of Meeting to Provide Forum for Discussion on Rev 7 of Operator Licensing Examiner Stds & to Discuss Operator Licensing Issues ML20059C9731993-09-0808 September 1993 Summary of 400th ACRS Meeting on 930805-06 in Bethesda,Md Re Proposed Resolution of GSI 57, Effects of Fire Protection Sys Actuation on Safety-Related Equipment & Lessons Learned from LaSalle Fire & Report on ABWR Fire Safety Issues ML20056D7471993-07-27027 July 1993 Summary of 930617 Meeting W/Util to Discuss Steps Being Taken by Licensee to Resolve Reactor Vessel Water Level Instrumentation Degassing Issue.List of Attendees Encl ML20059C7311993-01-30030 January 1993 Summary of 391st ACRS Meeting on 921105-07 in Bethesda,Md Re NRC Regulatory Analysis Guidelines & Reactor Operating Events & Occurrences,Shearon Harris Plant Loss of High Head SI & LaSalle Overfill Due to Failure of MFW Pumps to Trip ML20011F6111990-02-28028 February 1990 Summary of Operating Reactors Events Meeting 90-05 on 900228 ML20006E7251990-02-12012 February 1990 Summary of Operating Reactors Events Meeting 90-03 on 900207.List of Attendees & Viewgraphs Encl ML20005E8421989-12-27027 December 1989 Summary of Operating Reactor Events Meeting 89-045 on 891227.List of Attendees & Significant Elements Discussed Encl ML20005D8121989-12-18018 December 1989 Summary of Operating Reactors Events Meeting 89-044 on 891213.List of Attendees & Viewgraphs Encl ML19332G0601989-12-0707 December 1989 Summary of Operating Reactors Events Meeting 89-43 on 891206.On 891128,high Cycle Fatigue Failure of Master Connecting Rod Assembly Occurred at South Texas,Unit 2.RHR Leakage Noted on 891201 at Braidwood,Unit 1 ML20005D6871989-12-0101 December 1989 Summary of Operating Reactors Events Meeting 89-042 on 891129.List of Attendees & Viewgraphs Encl ML19332D2821989-11-16016 November 1989 Summary of Operating Reactors Events Meeting 89-040 on 891115 ML19327C0541989-11-0202 November 1989 Summary of 891019 Meeting W/Sys Energy Resources,Inc, Louisiana Power & Light & Arkansas Power & Light Re Antitrust Concerns W/Consolidation of Operations Under Entergy Operations,Inc.List of Attendees & Viewgraphs Encl ML19325E8981989-11-0101 November 1989 Summary of Operating Reactors Events Meeting 89-38 on 891101 to Brief Senior Managers from Nrr,Aeod,Res,Region Ofc & Commission on Selected Events That Occurred Since 891018 Meeting.List of Attendees Encl ML19325E1761989-10-24024 October 1989 Summary of Operating Reactors Events Meeting 89-37 on 891018.List of Attendees & Events Briefing Encl ML19325D9211989-10-19019 October 1989 Summary of 891012 Meeting W/Sys Energy Resources,Inc, Arkansas Power & Light,Inc & Louisiana Power & Light,Inc at NRC Headquarters to Discuss Consolidation of Operations Under Entergy Operations,Inc.List of Attendees Encl ML20247R0161989-09-21021 September 1989 Summary of Operating Reactors Events Meeting 89-34 on 890920 to Brief Senior Managers & Regional Offices on Selected Events That Occured Since Last Meeting ML20247E3641989-09-0606 September 1989 Summary of 890717 Meeting W/Numarc,B&W Owners Group & Representatives of Lead Plants Re Status of STS Amends & Outstanding Issues Associated W/Lead Plant STS Submittals ML20247D5291989-09-0505 September 1989 Summary of Operating Reactors Events Meeting 89-31 on 890830.Significant Event for Input Into NRC Performance Indicator Program Identified ML20247K2471989-08-24024 August 1989 Trip Rept of Staff 890718-19,21 & 0801-02 Visits to Nuclear Power Plants to Gather Info Re Industry Actions to Address Loss of Oil Malfunctions of Rosemount Models 1153 & 1154 Transmitters ML20246K2171989-08-24024 August 1989 Summary of Operating Reactors Events Meeting 89-30 on 890823 Re Reactor Trip W/Multiple Instrumentation & Equipment Failures at DC Cook Unit 2 on 890814 & Auxiliary Feedwater Flows at Hb Robinson ML20248B5171989-08-0303 August 1989 Summary of 890725 Interface Meeting W/Util in Birrmingham,Al Re Sonopco/Util Corporate Organization Including Generic Activities & Initiatives Re Plants.Agenda & Viewgraphs Encl ML20245G5421989-08-0303 August 1989 Summary of Operating Reactors Events Meeting 89-28 on 890802.List of Attendees,Events Discussed & Significant Elements of Events & Summaries of Reactor Scrams for Wks Ending 890723 & 30 Encl ML20246P7771989-07-13013 July 1989 Summary of Operating Reactors Events Meeting 89-26 on 890712.Events Discussed & Significant Elements of Events Presented in Encl 2.List of Attendees Also Encl ML18153B7971989-07-0606 July 1989 Summary of 890612 Meeting W/Util in Rockville,Md Re Plant Configuration Mgt Program.Informs That Goal of Program Is to Confirm That as-built Plants in Conformance W/Licensing Design Basis as Described in FSAR ML20246F8691989-06-22022 June 1989 Summary of Operating Reactors Events Meeting 89-24 on 890621.On 890615,potential Unmonitored Primary Coolant Release Path to Environ Discovered at WPPSS-2.On 890617,loss of Offsite Power Occurred at Brunswick,Unit 2 ML20245G6411989-06-15015 June 1989 Summary of Operating Reactors Events Meeting 89-23 on 890614.On 890607,multiple Electrical Distribution Sys Problems Occurred at Oconee,Units 1,2 & 3.On 890610,unit Power Signal Caused Scram ML20245F2221989-06-0808 June 1989 Summary of Operating Reactors Events Meeting 89-21 on 890531.List of Attendees & Related Info Encl ML20245A3851989-05-30030 May 1989 Summary of Operating Reactors Events Meeting 89-20 on 890524.List of Meeting Attendees & Viewgraphs Encl ML20247M7961989-05-24024 May 1989 Summary of 890502 Meeting W/Util,Sargent & Lundy & Rl Cloud Assoc in Rockville,Md Re Nonlinear Piping Analyses Used to Justify Removal of Snubbers & Pipe Supports.List of Attendees & Presentation by Licensee & Contractors Encl ML20247K0901989-05-23023 May 1989 Summary of 890517 Meeting W/Inpo Re Similarities & Differences Between Performance Indicator Programs.Detailed Discussion Encl ML20247J7051989-05-19019 May 1989 Summary of 890501 Meeting w/C-E Owners Group in Rockville,Md Re Diverse Emergency Feedwater Actuation Sys,Per 10CFR50.62 Requirements.List of Meeting Attendees & Viewgraphs Encl. Record Copy ML20247J6991989-05-19019 May 1989 Summary of 890501 Meeting w/C-E Owners Group in Rockville,Md Re Diverse Emergency Feedwater Actuation Sys,Per 10CFR50.62 Requirements.List of Meeting Attendees & Viewgraphs Encl ML20247K1011989-05-16016 May 1989 Summary of 890517 Meeting W/Inpo in Bethesda,Md Re Similarities & Differences Between INPO & NRC Performance Indicators ML20247D3441989-05-16016 May 1989 Summary of Operating Reactors Events Meeting 89-19 on 890510.List of Attendees,Events Discussed & Significant Elements of Events & Rept of long-term Followup Assignments & Summary of Scrams for Wk Ending 890507 Encl ML20246L7281989-05-0505 May 1989 Summary of 890503 Meeting W/Util in Rockville,Md Re Containment Vessel Structural Integrity Tech Specs for Plants.List of Attendees & Licensee Presentation Encl ML18153B7071989-05-0404 May 1989 Summary of 890419 Meeting W/Util in Rockville,Md Re Followup on NRC Bulletin 80-11, Masonry Wall Design. NRC Requested Documentation of as-built Boundary Conditions, Available Conservatisms & Field Verifications ML20246C3261989-05-0404 May 1989 Summary of Operating Reactors Events Meeting 89-18 on 890503 ML20246B5161989-04-28028 April 1989 Summary of 890419 Operating Reactors Events Meeting 89-16. List of Attendees & Handouts Encl ML18153B6791989-04-11011 April 1989 Summary of 890330 Meeting W/Util in Rockville,Md Re Util Overall long-term Improvement Plan to Enhance Plant Operations ML20248K3761989-04-10010 April 1989 Summary of Operating Reactors Events Meeting 89-014 on 890405.List of Attendees,Events Discussed & Significant Elements of Events & Summary of Reactor Scrams for Wk Ending 890402 Encl ML20247F1991989-03-24024 March 1989 Summary of Operating Reactors Events Meeting 89-12 on 890322.List of Attendees,Events Discussed & Significant Elements,Summary of Reactor Scrams & Comparison of Weekly Statistics W/Industry Averages for Wk Ending 890319 Encl ML20246N9201989-03-16016 March 1989 Summary of Operating Reactors Events Meeting 89-010 on 890308.List of Attendees,Significant Events Identified for Input to NRC Performance Indicator Program & Summary of Reactor Scrams for Wk Ending 890305 Encl ML20247A8971989-03-16016 March 1989 Summary of Operating Reactors Events Meeting 89-11 on 890315.List of Attendees,Events Discussed & Significant Elements of Events & Four Events Identified for Input to NRC Performance Indicator Program & Summary of Scrams Encl ML20245H8011989-02-23023 February 1989 Summary of Operating Reactors Events Meeting 89-08 on 890222.Attendee List & Events Discussed & Significant Elements of Events Encl ML20235M1671989-02-17017 February 1989 Summary of Operating Reactors Events Meeting 89-07 on 890215.List of Attendees,List of Events Discussed,Summary of Events for Long Term Followup or Input to NRC Performance Indicator Program & Summary of Reactor Scrams Encl 1997-02-13
[Table view] Category:TRIP REPORTS
MONTHYEARML20247K2471989-08-24024 August 1989 Trip Rept of Staff 890718-19,21 & 0801-02 Visits to Nuclear Power Plants to Gather Info Re Industry Actions to Address Loss of Oil Malfunctions of Rosemount Models 1153 & 1154 Transmitters ML20154L1661988-05-10010 May 1988 Trip Rept of 880412-15 Mgt Team Visit to Plant Sites,Two Matls Licensees & Region I Ofcs.List of Team Members & Summary of Observations & Perceptions from Visit Encl.Info Deleted ML20196F9951988-02-24024 February 1988 Partially Withheld Trip Rept of 880209-11 Mgt Team Visit to Region V & San Onofre & Trojan Sites Re Integrated Assessment of Mgt Effectiveness Associated W/Regionalized NRR & NMSS Programs ML20151W0041987-03-12012 March 1987 Submits After Trip Rept ML20147E8911986-08-20020 August 1986 Trip Rept of 860721-25 Visit to Plant to Observe INPO Accreditation Team Evaluation of Six Training Programs, Including Instrumentation & Control Technician,Mechanical Maint & Electrical Maint.List of Team Members Encl ML20213F8661986-07-31031 July 1986 Trip Rept of 860514-15 Site Visit Re Seismic Design Issues Concerning Cable Trays,Conduit Qualification,Hvac Concerns, CRD Return Lines,Ie Bulletins 79-14 & 79-02 & Nonessential Piping.Request for Addl Info Re Vermont Yankee Encl IA-86-778, Trip Rept of 860514-15 Site Visit Re Seismic Design Issues Concerning Cable Trays,Conduit Qualification,Hvac Concerns, CRD Return Lines,Ie Bulletins 79-14 & 79-02 & Nonessential Piping.Request for Addl Info Re Vermont Yankee Encl1986-07-31031 July 1986 Trip Rept of 860514-15 Site Visit Re Seismic Design Issues Concerning Cable Trays,Conduit Qualification,Hvac Concerns, CRD Return Lines,Ie Bulletins 79-14 & 79-02 & Nonessential Piping.Request for Addl Info Re Vermont Yankee Encl ML20206J6561986-06-23023 June 1986 Trip Rept of 860612 Training Session in Lacey,Wa Re Federal Radiological Emergency Response Plans & Meeting W/Utils & State of Wa Concerning Potential Emergency Preparedness Issues.Attendees Listed & Training Agenda Encl ML20244D8391986-05-0707 May 1986 Trip Rept of 860415 Site Visit Re Demonstration for Ultrasonic Exam Procedure of Statically Cast Stainless Steel Primary Loop Welds.Issue of Preservice Ultrasonic Exam of Welds Resolved.Trip Repts by Inel & Bnwl Encl ML20244D8401986-04-22022 April 1986 Trip Rept of 860415 Site Visit Re Demonstration of Ultrasonic Exams Performed on Cast Stainless Steel Primary Piping Welds.Exam Procedure Appears to Meet or Exceed ASME Code Requirements.Written Procedure Not Available ML20154L9181986-03-0606 March 1986 Trip Rept of 851021-24 Site Visits Re Wrong Unit/Wrong Train Events to Determine Whether Simple,Low Cost Improvements Can Be Identified & Implemented ML20237C9681986-02-19019 February 1986 Trip Rept of Attendance at State of Il 860213 Meeting Re Training Session on NRC Incident Response Program & NRC Participation in 860408 Plant Emergency Exercise.List of Attendees & Partial Agenda Encl ML20141H8551986-01-10010 January 1986 Trip Rept of 851112-15 Site Visits Re Wrong Unit/Wrong Train Events.Visit Conducted as Part of short-term Effort to Determine If Low Cost Improvements Can Be Identified & Implemented to Reduce Frequency of Events ML20138A1201985-09-23023 September 1985 Trip Rept of 850617-20 Site Visits Re Reduction of Wrong Unit/Wrong Train Events at Facilities ML20147E2301985-06-0303 June 1985 Trip Rept of 850420-22 Visit to Port Gibson,Ms,To Participate in Field Test of Draft Training Review Criteria & Procedures at Plant.Nrc Teams Observed Licensed Operator & Nonlicensed Operator Training ML20133B8781985-03-15015 March 1985 Trip Rept of 850315 Site Visit Re Presentation of Licenses to Senior Reactor Operators & Reactor Operators.Subjs Discussed During Visit Stated ML20133B8521985-02-26026 February 1985 Trip Rept of 850207-08 Site Visit Re Status of Licensee Performance Enhancement Program & Status of Action Plan Being Used to Improve Overall Training Effort ML20136F6871985-02-0505 February 1985 Trip Rept of 841203-07 Visit to Bechtel in Norwalk,Ca Re Structural Engineering Design Audit Based on Util 841031 Submittal of Design Rept.List of Attendees,Agenda & Addl Info Required for Satisfactory Question Response Encl ML20199G3181985-01-15015 January 1985 Trip Rept of 841114-16 Site Visit Re Meetings W/Qa/Qc Inspectors to Emphasize That All Safety Issues Must Be Resolved Before Units Can Be Licensed ML20147E0431985-01-10010 January 1985 Trip Rept of 850930-1004 Observation of INPO Accreditation Team Evaluation of Plant Training Programs,Including Licensed Reactor Operator,Nonlicensed Operator & Shift Technical Adviser.Inpo Evaluation Team Member List Encl ML20237D0071985-01-10010 January 1985 Trip Rept of 871112-15 Visit to Sites to Determine Whether Simple,Low Cost Improvements Can Be Identified & Implemented to Reduce Frequency of Wrong Unit/Wrong Train Events ML20209D3321984-09-21021 September 1984 Trip Rept of 840816-22 Visits to Lasl & Plant Re DHR & Unresolved Safety Issue A-45 ML20136F1681984-08-31031 August 1984 Trip Rept of 840621-22 Site Visits to Examine Clastic Dikes of Coastal Plain ML20136F1281984-08-0707 August 1984 Trip Rept of 840724 Site Visit Re Radiation Protection Facilities.Attendee List Encl ML20133B9461984-07-0505 July 1984 Trip Rept of 840703 Site Visit Re Training Organization & Programs.Program Not Implemented Due to Lack of Senior Mgt Support ML20127B5101984-04-13013 April 1984 Trip Rept of Site Visit During Wk of 831031 Re Physical Arrangement & Installation of Electrical,Instrumentation & Control Equipment.Compliance W/Nrc Design Criteria Confirmed IA-85-160, Trip Rept of Site Visit During Wk of 831031 Re Physical Arrangement & Installation of Electrical,Instrumentation & Control Equipment.Compliance W/Nrc Design Criteria Confirmed1984-04-13013 April 1984 Trip Rept of Site Visit During Wk of 831031 Re Physical Arrangement & Installation of Electrical,Instrumentation & Control Equipment.Compliance W/Nrc Design Criteria Confirmed ML20149B6101984-03-28028 March 1984 Trip Rept of 840323 Visit to INPO to Respond to INPO Concerns Re Training & Qualifications Rulemaking Package (SECY-84-76).Accreditation Team Rept on McGuire Station Read & Questions Answered ML20115A0941984-02-0909 February 1984 Trip Rept of 830124-25 Site Visit Re Control Room Habitability.Hvac Sys Generic General Concerns & Overall Perspective Addressed ML20138M9741983-12-20020 December 1983 Trip Rept of 831129-30 Site Visit Statistical Analysis of Backfit Insp Program ML20132B6931983-11-21021 November 1983 Trip Rept of 831104-05 Site Visit & Meeting to Formulate Final Objectives,Guidance & Schedule for Initial full-scale Exercise ML20080D2771983-10-31031 October 1983 Trip Rept of 830622-24 Caseload Forecast Panel Site Visit Re Plant Status Review.Projected Fuel Load Date Comparisons Listed ML20080D2631983-10-31031 October 1983 Draft Trip Rept of Caseload Forecast Panel 830222-24 Site Visits Re Const Progress Review & Estimating Resource Needs for Licensing Activities ML20209C3391983-08-0808 August 1983 Trip Rept of Attendance at 830727 Meeting in San Francisco, CA Between Idvp & Util Re Status of Closure Efforts on Open Items in Idvp Final Rept.Projected Date for Issuance of Idvp Final Rept Suppl Is mid-Sept 1983 ML20080D2971983-07-27027 July 1983 Summary of 830622-24 Caseload Forecast Panel Site Visit Re Plant Status Review ML20151H8231983-07-26026 July 1983 Trip Rept of 830712 & 15 Site Visit Re Fire Protection Site Audit.List of Agreements & Concerns Discussed Encl ML20209C3101983-07-25025 July 1983 Trip Rept of 830607 Visit to San Francisco,Ca to Observe Test Program Developed by Util & Bechtel.Program Was to Determine Statistically Spot Weld Capacity of Superstrut Matl Installed at Plant ML20209C2311983-06-30030 June 1983 Trip Rept of Attendance at 830512 Technical Interchange Meeting W/Util & Independent Verification Program Staff Re Containment & Turbine Bldgs & Control Room.Attendee List Encl ML20209C1171983-04-29029 April 1983 Trip Rept of 830425 Visit to Bechtel in Gaithersburg,Md to Review Grand Gulf Cable Tray Support Calculations for Use in Resolution of Allegation Concerning Superstrut Spot Welds at Diablo Canyon ML20080D2551983-03-18018 March 1983 Marked-up Draft Summary of Trip Rept of Caseload Forecast Panel 830222-24 Meetings Re Const Progress Review & Mgt Decision on Allocation of Staff Resources During Licensing Review ML20205T5371983-02-15015 February 1983 Trip Rept of 830126 Meeting in Bethesda to Discuss Question of Corrective Actions to Be Required of Util Re Finding of Uncertified QC Inspectors at Site ML20209B9941983-02-14014 February 1983 Trip Rept of 830126 Meeting W/Rl Cloud & Assoc in Berkeley, CA to Clarify Items Re Interim Technical Rept (Itr) 12, Independent Design Verification Program (Idvp) - Piping & Itr 17, Idvp - Piping,Addl Samples ML20209B8411983-01-10010 January 1983 Trip Rept of 821202 Meeting W/Teledyne Engineering Svcs, Bechtel,Bnwl,Norton,Burke,Berry & French,Util,State of CA, Hhb & Urs/Blume to Discuss Listed Portions of Independent Design Verification Program ML20070V1351982-12-20020 December 1982 Trip Rept of 820913-17 Visit to Facility to Review Seismic & Dynamic Qualification Methods,Procedures & Results for safety-related Mechanical & Electrical Equipment & Observe Field Installation of Equipment ML20209B7941982-11-30030 November 1982 Trip Rept for 821112 Info Exchange Meeting Between Teledyne Engineering Svcs & Util in Waltham,Ma to Review Corrective Action Plans for Annulus Structure ML20209B7801982-10-28028 October 1982 Trip Rept of 820920-23 Visit to Site & Escondido,Ca Re NRC & Us Coastal Engineering Research Hydrologic Engineering Review Comments on Breakwater/Intake Structure Repts for Jul 1982 ML20134B4611982-09-16016 September 1982 Trip Rept of 820830-31 Visit to Bechtel,Norwalk,Ca to Observe Region IV Insp Concerning Effectiveness of Util/ Bechtel Processing of Field Change Notices for Facility Const.Supporting Documentation Encl ML20083L8031982-09-0202 September 1982 Trip Rept of 820813 Site Visit Re Replacement of Recirculation Sys Piping ML20069D1861982-08-30030 August 1982 Trip Rept of 820915-18 Seismic Qualification Review Team Site Visit Re Performance of Plant Site Review for Selected safety-related,mechanical & Electrical Equipment.Revision to Site Visit Rept Encl.W/O Encl ML20080D6561982-08-19019 August 1982 Trip Rept of Caseload Forecast Panel 820811-13 Site Visits Re Status of Const & Preoperational Testing Evaluation. Related Info Encl 1989-08-24
[Table view] |
Text
[g* Rf 4 k NUCLEAR REGULATORY COMMISslON 9
UNITED STATES g
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CLEN ELLYN, ILUNOl$ 601 M February 19, 1986 MEMORANDUM FOR: Jack A. Hind, Director, Division of Radiation Safety and Safeguards THRU:
W. D. Shafer, Chief Emergency Preparedness and Radiological Protection Branch FROM:
Monte P. Phillips, Chief, Emergency Preparedness Section
SUBJECT:
TRIP REPORT - MEETING WITH STATE OF ILLINOIS DEPARTMENT OF NUCLEAR SAFETY - FEBRUARY 13, 1986 On February 13, 1986, Wayne D. Shafer, Pat Hyland, and I attended a meeting with representatives from the Illinois Department of Nuclear Safety. A copy of the attendance list and partial agenda are attached. During the meeting, I presented a training session on the NRC Incident Response Program. In addition, a discussion was held regarding NRC participation in the April 8, 1986 LaSalle emergency exercise. Emphasis, was placed on the various response modes of the A
NRC and which location, (Headquarters, Region, or Site), had the lead for the j
V agency in these various response modes.
i State DNS personnel presented a description of the REAC facility, including its capability to monitor over 1,300 individual data point parameters from each of the Nuclear units within the state. These data points were at least as comprehensive as all infomation available in any licensee's control room. The state was in the process of developing computer algorithms to provide an early alert to problems occurring at the plant, prior to the notification from the facility. NRC representatives cautioned them that, based on the number of LERs submitted, the state could expect a significant number of situations where their algorithms could indicate a significant emergency when, in fact, there was only a minor, non-emergency condition at the facility.
The various responsibilities for the State were clarified, as well as logistics and communications arrangements. Access to the REAC for an NRC liaison was l
discussed. The NRC liaison individual would reach the REAC by proceeding South 9
on Interstate 55 to the South Grand Avenue Exit. They would then proceed l
westbound until McArthur Avenue, where they would turn left (south); and then l
proceed to Outer Park Drive, where they would turn right (west) and travel one city block. The REAC is located on the fifth floor of 1035 Outer Park Drive.
i Access would be arranged by hav %g one of the members of the NRC's Base Team contact the REAC facility with the name and NRC badge number of the individual dispatched to the facility. All communications with the REAC would be made i
over the telephone number (217) 785-0600. This phone number should be used to talk with either then NRC liaison individual or any member of the REAC staff.
O I
f 8712220288 871210 8
PDR FOIA SHDLLYB7-737 PDR
4 l
Jack A. Hind February 19, 1986 IDNS presented a brief discussion of how protective actions are fomulated at the REAC. Although the REAC Comander had the ultimate authority to issue a recommendation to the Head of IDNS, the decision was coordinated between the Reactor Analyst and Environmental Analyst. The Reactor Analyst would want i
to be in contact with NRC's Reactor Safety personnel to discuss the l
consequences of the event and potential for severity or recovery. Similarly, the Environmental Analyst would want to be in contact with the NRC's Protective Measures personnel to discuss dose assessment, environmental field readings, l
and protective action recommendations.
IDNS representatives were concerned I
that, although they now had the telephone numbers for Base Team counterparts, no such numbers were available for NRC Headquarters personnel, although the NRC Headquarters staff had the lead for the Agency decisions and coordination during the Initial Activation Mode.
The meeting concluded with a brief discussion of a proposal from Department o,f Nuclear Safety personnel to revise the flow-chart currently used by Commonwealth Edison to fonnulate default protective action recommendations for a General Emergency. A copy of the proposed flow chart is attached, along with copies of IE Information Notice 81-23, and the current CECO flow chart.
We stated that we would provide an advance copy to the NRC reviewer for CECO; however, no action to approve or disapprove of the proposal would be made until CECO submitted the request..for such action to the NRC.
O If you have any questions regarding this meeting please let me know.
%fPAA}
Monte P. Phillips, Chief Emergency Preparedness Section
Attachment:
As stated cc w/ attachment:
- f Perkins, IRB, 0IE R. Lickus, SGA, RIII L. Kers, ERC, RIII O
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NAME REPRESENTING
}
Monte P. Phillips NRC - Chief,.0perational Support Section I
Mike Parker IDNS - Chief. Engineering Division j
Andrea Pepper IDNS - Emergency Planning Steve Dunas
'IDflS - Chief. Emergency Planning Gene Field IDNS - Emergency Planning.
l l
Frank Sprague IDNS. - Emergency Planning.
Patrick L. Hiland NRC - Resident Inspector, Clinton Wayne D. Shafer NRC - Chief, Emergency Preparedness Jim Blackburn Assistant Manager, Office of Nuclear Facility Safety Gary Wright Manager, Office of Nuclear Facility Safety Denis Smiley Chief, Radiation Assessment r0 l
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Tentatative Agenda
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NRC - Region III February 13, 1986 10:00 a.m.
I.
Overview of DNS Emergency Organization; Capabilities Welcome - Terry Lash Overview - Gary Wright DNS Data Link - Mike Parker Remote Monitoring - Jim Blackburn Communications - Steve Dunas II.
Clarification of Communication Links (Entity / Position - Location / Telephone Number)
Information to be Exchanged Plant Status Data -* R*"6' bl d
/
kedRadn Protective Action Recomendatioh E komed./ A4,/ psf Public Infomation III. Proposed Revision to General Emergency Default Protective Action Recommendations t
l Goal - Achieve Consistency between:
- NRC - NUREG-0654
- Ceco - GSEP
- DNS - IPRA Attendees:
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1 FIGURE 6.3-1 LYCOMENDED PROTECTIVE ACTIONS - CENERAL EMERCDCY GENERAL EMERCDCY Od 1
I I
l ans sa YES as ta's't um emancnoms sensas avuLa&L8 NO
.mmmmme ass esam 4D E'M sen is 9C.'C. H. & F l
l Mn". d'"'"ng' 9/(10 miles) l
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is -
is W (10 miles)
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enem$cNn ES YES TES h i NARS YES' 4
FORM (E) (E) (E)
)
a anu to tasto du, I
4D.6C.7A 4D.6C.7A 4D.6C.7A 9W (10 miles) 98f (10 miles) 9d.I.J.& K
~
- 9C
(10 miles)
NO NO NO NO a
v u
l RECOMMEND RECO69END RECOMMEND i
NARS FORM NARS FORM NARS FORM l
(E) (S) (P)
(E) (S) (S)
(E) (E) (S) j i
ir u
ir 9
4D ts 9C J K. & L 9g(g6 miles) ritmai armatst
,a rm,at 43 ct ygs amourtas yrs RECOMMEND tevn emunom LN NARS TORM ana' en no' s a (E) (E) (E)
NO NO 4D a
4D d
9 ( 0 mil s g
( 0 mil s enaTv YES RECOMMEND "E,,
TES RE N uun, E
' NARS FORM Jaco t;o
- NARS FORM "cEtu (E) ($) (P) to, (E) (E) (E) m
=
,vn O
CONTINUE TO ASSESS USING THIS f
IIDWCHART IN CONJUNCTION WITH CSEP RECOMMEND 4D TABLES 6.3-1, 6.3-2, & 6.3-3 AND 4
NARS FORM 9C. I. J. & K CUIDANCE OF CSEP SECTIONS $ AND 6 (g) (g) (s) 9g (10 miles)
'l i
I Evacuation, when noted. is the reconsunded protective action when evacuation can be completed prior to plume arrival; f
Shelter is then the protective action to be recommended.
1 Availability of. Dose Projections means the TSC or EOF g CCC are manned by Environmental Personnel.
1
- Recoaunended protective actions are radial for 0-2 miles and the three (3) downwind sectors for 2-5 miles and 5-10 miles.
I (O
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i O
L-_-_____.___.________.-_-_______-___--_-._-.__-.-._.--_
.-__-.2
i FLOW CHART FOR GENERAL EMERGENCY OFFSITE PROTECTIVE DECISIONS q
The fonowine eetions win be bee.4 on predetermine.d oneervebie instrum.ntation end pient steeve indi et.,e.
(EALS) contained in the emergency plan and that have been reviewed by offefte officiele, tiowever, responsible offette off6ciale must decide the feasibility of implementing the protective actione et the time of the ace 6 dent.
Ab CONTROL ROOMSTAPF DETECT j
GENERAL EMERGENCY I
P RECOMMENO SHtLTER I MILE RAOlVS E MIL 83 DOWNwlNO CONTINUE l
8 11)
A8stSSMENT d
I 1 P NO j
l
$USSTANTIAL CORE CAMAGE EPA Pace vis gg pRooRggs om NO PROJECTED PROJECT 307 TO et Y
(ACTUAL 04 EXCetDEDP POTENTIAL POR 3% PUEL DAMAGE) l
- O LARGE FtSSION VtS TE8 NO INVE OR IN I I
, CONT AINMENT7 IMORE THAN RECOMMEND
\\
QAP)
PROTICityt ACTIONS IN ACCORDANCE WITH EPA PAGe 3 r q 7 RECOMME NO SHELTER POR eMutNEst?
AREAS THAT eMMimeNT PeOACTED CANTet PROJECTIO Yts EVACUATED' VES CONTAINMENT CONTAsNutNT SEFORE PLUME FAILURE OR rAILURt AND A A ATV AL -
RELEASE ComtDAMAGEOR tvACUATE UNDERWAY?
RgiEAst CTHERs et1 Melan
- (21 DesDiRWAT (2 4 MILESI N;
l eg 1 t I r RECOMutNO RtCOMMEND EVACUATtON Of EVACUATION OF 5 MILE RADIUS.
2 MeLE RAO#US.
to MILES 00WNwtND E MrJS DOWNW1NO
'I1ka
- 1114 4 1 f i f SOURCE; Appenes 1 NUREG4eW/ FEM A-REP.1. Rev. t
- (11 SITUATIONS REQUIRING URGENT ACTION BY OFFSITE OFFICIALS Itseed on Control Room Indicators. No Does Projections Requirodi.,
- 15 Minute Declaionmaking, Activation of Alerting System and EBS Message
- (2) Actuel et projected release of 20% gap from core.
'l3) " Puff" rolesee trate much greater then designed leek retel.
- (4) For eR ovecussione, shelter the remainder of the plume EPZ end resecate the population effected by any ground contamination promptfy following plume passage.
- (5) Concentrate en evecuation of stees near the plant (e.g., may be time to evacuate 2 mile radius and not the a -es.
,h en
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