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Category:MEETING MINUTES & NOTES--CORRESPONDENCE
MONTHYEARML20217M5371999-10-25025 October 1999
Summary of 990901 Meeting with Licensee in Rockville,Md Re Util Planned Conversion to Improved Sts.Attendance List & Agenda Encl
ML20211N2141999-09-0808 September 1999
Summary of 990720 Meeting with Util in Rockville MD Re Amend Currently Under Review by Staff Pertaining to Control Room Habitability at Plant Units 1 & 2.List for Attendees & Licensee Handouts Encl
ML20206Q6411999-05-12012 May 1999
Summary of 990426 Meeting with Util at NRC Headquarters Re Proposed Submittal of Amend to Implement Ists.List of Meeting Participants & Matls Presented by Licensee Encl
ML20196F6101998-12-0101 December 1998
Summary of 981029 Meeting with Northern States Power, Wisconsin Electric,Wisconsin Public Service & Alliant-IES in Rockville,Md Re Various Aspects of Potential Regulatory Issues Associated with Ongoing Cooperative Efforts
ML20210H3881997-08-0808 August 1997
Summary of 970805 Meeting W/Wepc & W in Rockville,Md to Discuss Plans to Submit Two TS Change Requests That Will Address 422V Fuel & Proposed Schedule for Review.List of Attendees & Licensee Presentation Encl
ML20135F7891997-03-0303 March 1997
Summary of 970224 Meeting W/Wisconsin Electric Power Co & Gls Enterprises,Inc in Rockville,Md Re Environ Qualified Equipment Inside Containment to Perform Function Following loss-of-coolant Accident Affected by Revised Profiles
ML20058B0031993-11-10010 November 1993
Summary of 931103 Meeting W/Util in Rockville Re Emergency Diesel Generator Addition Project.Attendance List,Discussion on Proposed Review Schedule & Licensee Summary of Emergency Diesel Generator Project Encl
ML20059B1201993-10-21021 October 1993
Summary of 931014 Meeting W/Util in Rockville,Md Re RCS Flow TS Change.List of Meeting Attendees & Handouts Encl
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
ML20056F8591993-08-16016 August 1993
Summary of 930727 Meeting W/Util in Rockville,Md Re Outstanding Licensing Issues.List of Participants Encl
ML20059P0041990-10-12012 October 1990
Summary of 900905 Meeting W/Util in Rockville,Md Re Plans for Upgrading Onsite Emergency Power Capabilities
ML20153G5481988-05-0404 May 1988
Summary of 880427 Telcon W/Utils in Region III Re Personnel Changes,Follow Up on Previous Items,Items of Interest from Sites & New Items
ML20154G9921988-04-26026 April 1988
Summary of 880331 Meeting W/Sandia Natl Lab,Numarc,Epri, Saic,Util,Westinghouse & ERC Intl Re Differences Between Industry Sponsored Analysis & Earlier Analysis of Same Plant Sponsored by NRC
ML20149K7541988-02-10010 February 1988
Summary of 880204 Meeting in Rockville,Md to Discuss Licensee Accident Reanalysis to Support Increased Allowable Core Peaking Factors at Facilities.Slides Used During Presentation & List of Meeting Attendees Encl
ML20237A9931987-12-0303 December 1987
Summary of 871104 Meeting W/Westinghouse & Utils in Bethesda,Md Re Susceptability of Facility Steam Generators to High Cycle Fatigue.Attendance List & Nonproprietary Westinghouse Handouts Encl
ML20237L1111987-08-28028 August 1987
Summary of Operating Reactors Events Meeting 87-28 on 870825 Re Events Which Occurred Since 870818 Meeting.List of Attendees & Significant Elements Encl
ML20215C8721987-06-0808 June 1987
Summary of Operating Reactors Events Meeting 87-10 on 870406 Re Events Which Occurred Since 870330 Meeting.List of Attendees,Events Discussed & Significant Elements of Events & Summary of Reactor Scrams & Significant Events Encl
ML20214W1621987-06-0505 June 1987
Summary of 870530 Meeting W/Util in Bethesda,Md Re Licensee Assessment of Flaw Indication Observed in Reactor Vessel nozzle-to-shell Weld for Safety Injection Sys.Attendees List Encl
ML20215D0631986-12-11011 December 1986
Summary of Operating Reactor Events Meeting 86-42 on 861201. List of Attendees & Viewgraphs Re Significant Elements of Events Discussed Encl
ML20215C9961986-12-11011 December 1986
Summary of Operating Reactor Events Meeting 86-41 on 861124.List of Attendees,Events Discussed & Significant Event Elements & Summary of Events That Will Be Input to NRC Performance Indicator Program Encl
NUREG-0518, Summary of ACRS 316th Meeting on 860807-09 in Washington,Dc Re Proposed Standardization Policy Statement & Review of Issues Related to Reorganization of TVA Mgt Structure & Shutdown of TVA Nuclear Power Plants1986-08-18018 August 1986
Summary of ACRS 316th Meeting on 860807-09 in Washington,Dc Re Proposed Standardization Policy Statement & Review of Issues Related to Reorganization of TVA Mgt Structure & Shutdown of TVA Nuclear Power Plants
ML20211G7781986-06-13013 June 1986
Summary of Operating Reactor Events Meeting 86-19 on 860609. List of Attendees,Events Discussed & Status of Previous Assignments Encl
ML20197F7721986-05-0808 May 1986
Summary of Operating Reactors Events Meeting 86-15 on 860505.List of Attendees,Events Discussed & Status of Previous Assignments Encl
ML20138N9841985-12-19019 December 1985
Summary of 851122 Meeting W/Licensees & Westinghouse to Present Status of Program for Developing New Upper Plenum Injection Evaluation Model.Nonproprietary Viewgraphs,List of Attendees & Agenda Encl
ML20137X5091985-11-29029 November 1985
Summary of Operator Reactor Events Meeting 85-24 on 851125 Re Briefing of Ofc Directors & Div Directors & Representatives on Events Which Occurred Since Last Meeting on 851118.List of Attendees Encl
ML20138P0081985-10-21021 October 1985
Summary of Operating Reactors Events Meeting 85-19 on 851007 W/Ofc Directors,Div Directors & Representatives on Events Which Occurred Since Last Meeting on 851007
ML20133F9941985-10-0707 October 1985
Summary of Operating Reactors Events Meeting 85-16 on 850916 Re Briefing of Director,Div Directors & Representatives on Events Occurring Since 850909 Meeting.List of Attendees & Viewgraphs Encl
ML20141E5521985-09-26026 September 1985
Summary of ACRS Subcommittee on Reactor Operations 850910 Meeting in Washington,Dc to Discuss Recent Operating Occurrences.Fr Notice,Meeting Schedule & List of Meeting Slides Encl
ML20209G6871985-09-0909 September 1985
Summary of Operating Reactor Events Meeting 85-14 on 850826 to Brief Director & Div Directors on Events Which Occurred Since 850813 Meeting.Computer Printout of 1985 Operating Reactor Events Meeting Topics to Date Encl
ML20133E0661985-07-25025 July 1985
Summary of 850628 Meeting W/Utils & Westinghouse Re Status of Development of New Upper Plenum Injection Evaluation Model.List of Attendees & Agenda Encl
ML20127N9021985-06-24024 June 1985
Summary of Operating Reactors Events Meeting 85-10 on 850612.Only 3 of 17 Items Scheduled for Completion by 850531 Remain Incomplete.List of Attendees,Summary of Events Discussed & Status of Previous Assignments Encl
ML20236Y4401981-07-0101 July 1981
Summary of Site Audit & 810609-11 Meeting W/Util Re Response to IE Bulletin 80-11 on Masonry Walls.Lists of Attendees & Action Items Resulting from Meeting Encl
ML20126L2331981-05-0101 May 1981
Summary of 810429 Meeting W/Pwr Owners Group Re Thermal Shock to Reactor Pressure Vessels.All Parties Agree That Thermal Shock W/Subsequent Repressurization Is Safety Concern Needing Prompt Evaluation
ML20196H3981978-07-0505 July 1978
Summary of 780622 Meeting W/Westinghouse Owners Group to Discuss Results of Phase a of three-phase Plan & Current Schedule for Resolution of Asymmetric LOCA Loads Isssue.List of Attendees Encl
ML20245C3211977-07-11011 July 1977
Summary of 770525 Meeting W/Westinghouse & Util Group Members Re Efforts to Prevent Reactor Vessel Overpressurization.W/O Encls
ML20196H3251976-06-29029 June 1976
Summary of 760525 Meeting W/Util & Westinghouse Re Proposed Approach to Solution of Reactor Vessel Lateral Loading Question.List of Attendees,Agenda & Viewgraphs Encl
1999-09-08
[Table view]
Category:MEETING SUMMARIES-INTERNAL (NON-TRANSCRIPT)
MONTHYEARML20217M5371999-10-25025 October 1999
Summary of 990901 Meeting with Licensee in Rockville,Md Re Util Planned Conversion to Improved Sts.Attendance List & Agenda Encl
ML20211N2141999-09-0808 September 1999
Summary of 990720 Meeting with Util in Rockville MD Re Amend Currently Under Review by Staff Pertaining to Control Room Habitability at Plant Units 1 & 2.List for Attendees & Licensee Handouts Encl
ML20206Q6411999-05-12012 May 1999
Summary of 990426 Meeting with Util at NRC Headquarters Re Proposed Submittal of Amend to Implement Ists.List of Meeting Participants & Matls Presented by Licensee Encl
ML20196F6101998-12-0101 December 1998
Summary of 981029 Meeting with Northern States Power, Wisconsin Electric,Wisconsin Public Service & Alliant-IES in Rockville,Md Re Various Aspects of Potential Regulatory Issues Associated with Ongoing Cooperative Efforts
ML20210H3881997-08-0808 August 1997
Summary of 970805 Meeting W/Wepc & W in Rockville,Md to Discuss Plans to Submit Two TS Change Requests That Will Address 422V Fuel & Proposed Schedule for Review.List of Attendees & Licensee Presentation Encl
ML20135F7891997-03-0303 March 1997
Summary of 970224 Meeting W/Wisconsin Electric Power Co & Gls Enterprises,Inc in Rockville,Md Re Environ Qualified Equipment Inside Containment to Perform Function Following loss-of-coolant Accident Affected by Revised Profiles
ML20058B0031993-11-10010 November 1993
Summary of 931103 Meeting W/Util in Rockville Re Emergency Diesel Generator Addition Project.Attendance List,Discussion on Proposed Review Schedule & Licensee Summary of Emergency Diesel Generator Project Encl
ML20059B1201993-10-21021 October 1993
Summary of 931014 Meeting W/Util in Rockville,Md Re RCS Flow TS Change.List of Meeting Attendees & Handouts Encl
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
ML20056F8591993-08-16016 August 1993
Summary of 930727 Meeting W/Util in Rockville,Md Re Outstanding Licensing Issues.List of Participants Encl
ML20059P0041990-10-12012 October 1990
Summary of 900905 Meeting W/Util in Rockville,Md Re Plans for Upgrading Onsite Emergency Power Capabilities
ML20153G5481988-05-0404 May 1988
Summary of 880427 Telcon W/Utils in Region III Re Personnel Changes,Follow Up on Previous Items,Items of Interest from Sites & New Items
ML20154G9921988-04-26026 April 1988
Summary of 880331 Meeting W/Sandia Natl Lab,Numarc,Epri, Saic,Util,Westinghouse & ERC Intl Re Differences Between Industry Sponsored Analysis & Earlier Analysis of Same Plant Sponsored by NRC
ML20149K7541988-02-10010 February 1988
Summary of 880204 Meeting in Rockville,Md to Discuss Licensee Accident Reanalysis to Support Increased Allowable Core Peaking Factors at Facilities.Slides Used During Presentation & List of Meeting Attendees Encl
ML20237A9931987-12-0303 December 1987
Summary of 871104 Meeting W/Westinghouse & Utils in Bethesda,Md Re Susceptability of Facility Steam Generators to High Cycle Fatigue.Attendance List & Nonproprietary Westinghouse Handouts Encl
ML20237L1111987-08-28028 August 1987
Summary of Operating Reactors Events Meeting 87-28 on 870825 Re Events Which Occurred Since 870818 Meeting.List of Attendees & Significant Elements Encl
ML20215C8721987-06-0808 June 1987
Summary of Operating Reactors Events Meeting 87-10 on 870406 Re Events Which Occurred Since 870330 Meeting.List of Attendees,Events Discussed & Significant Elements of Events & Summary of Reactor Scrams & Significant Events Encl
ML20214W1621987-06-0505 June 1987
Summary of 870530 Meeting W/Util in Bethesda,Md Re Licensee Assessment of Flaw Indication Observed in Reactor Vessel nozzle-to-shell Weld for Safety Injection Sys.Attendees List Encl
ML20215D0631986-12-11011 December 1986
Summary of Operating Reactor Events Meeting 86-42 on 861201. List of Attendees & Viewgraphs Re Significant Elements of Events Discussed Encl
ML20215C9961986-12-11011 December 1986
Summary of Operating Reactor Events Meeting 86-41 on 861124.List of Attendees,Events Discussed & Significant Event Elements & Summary of Events That Will Be Input to NRC Performance Indicator Program Encl
NUREG-0518, Summary of ACRS 316th Meeting on 860807-09 in Washington,Dc Re Proposed Standardization Policy Statement & Review of Issues Related to Reorganization of TVA Mgt Structure & Shutdown of TVA Nuclear Power Plants1986-08-18018 August 1986
Summary of ACRS 316th Meeting on 860807-09 in Washington,Dc Re Proposed Standardization Policy Statement & Review of Issues Related to Reorganization of TVA Mgt Structure & Shutdown of TVA Nuclear Power Plants
ML20211G7781986-06-13013 June 1986
Summary of Operating Reactor Events Meeting 86-19 on 860609. List of Attendees,Events Discussed & Status of Previous Assignments Encl
ML20197F7721986-05-0808 May 1986
Summary of Operating Reactors Events Meeting 86-15 on 860505.List of Attendees,Events Discussed & Status of Previous Assignments Encl
ML20138N9841985-12-19019 December 1985
Summary of 851122 Meeting W/Licensees & Westinghouse to Present Status of Program for Developing New Upper Plenum Injection Evaluation Model.Nonproprietary Viewgraphs,List of Attendees & Agenda Encl
ML20137X5091985-11-29029 November 1985
Summary of Operator Reactor Events Meeting 85-24 on 851125 Re Briefing of Ofc Directors & Div Directors & Representatives on Events Which Occurred Since Last Meeting on 851118.List of Attendees Encl
ML20138P0081985-10-21021 October 1985
Summary of Operating Reactors Events Meeting 85-19 on 851007 W/Ofc Directors,Div Directors & Representatives on Events Which Occurred Since Last Meeting on 851007
ML20133F9941985-10-0707 October 1985
Summary of Operating Reactors Events Meeting 85-16 on 850916 Re Briefing of Director,Div Directors & Representatives on Events Occurring Since 850909 Meeting.List of Attendees & Viewgraphs Encl
ML20141E5521985-09-26026 September 1985
Summary of ACRS Subcommittee on Reactor Operations 850910 Meeting in Washington,Dc to Discuss Recent Operating Occurrences.Fr Notice,Meeting Schedule & List of Meeting Slides Encl
ML20209G6871985-09-0909 September 1985
Summary of Operating Reactor Events Meeting 85-14 on 850826 to Brief Director & Div Directors on Events Which Occurred Since 850813 Meeting.Computer Printout of 1985 Operating Reactor Events Meeting Topics to Date Encl
ML20133E0661985-07-25025 July 1985
Summary of 850628 Meeting W/Utils & Westinghouse Re Status of Development of New Upper Plenum Injection Evaluation Model.List of Attendees & Agenda Encl
ML20127N9021985-06-24024 June 1985
Summary of Operating Reactors Events Meeting 85-10 on 850612.Only 3 of 17 Items Scheduled for Completion by 850531 Remain Incomplete.List of Attendees,Summary of Events Discussed & Status of Previous Assignments Encl
ML20126L2331981-05-0101 May 1981
Summary of 810429 Meeting W/Pwr Owners Group Re Thermal Shock to Reactor Pressure Vessels.All Parties Agree That Thermal Shock W/Subsequent Repressurization Is Safety Concern Needing Prompt Evaluation
ML20196H3981978-07-0505 July 1978
Summary of 780622 Meeting W/Westinghouse Owners Group to Discuss Results of Phase a of three-phase Plan & Current Schedule for Resolution of Asymmetric LOCA Loads Isssue.List of Attendees Encl
ML20245C3211977-07-11011 July 1977
Summary of 770525 Meeting W/Westinghouse & Util Group Members Re Efforts to Prevent Reactor Vessel Overpressurization.W/O Encls
ML20196H3251976-06-29029 June 1976
Summary of 760525 Meeting W/Util & Westinghouse Re Proposed Approach to Solution of Reactor Vessel Lateral Loading Question.List of Attendees,Agenda & Viewgraphs Encl
1999-09-08
[Table view] |
Text
_ _ - - .
APR 2 01988 MEMORANDUM FOR: Karl Kniel, Chief Reactor and Plant Safety Issues Branch Division of Reactor and Plant Systems, RES FROM: Roy Woods, Senior Task Manager Reactor and Plant Safety Issues Branch Division of Reactor and Plant Systems, RES
SUBJECT:
SUMMARY
OF MARCH 31, 1988 MEETING TO DISCUSS REANALYSIS OF DHR RISK AT POINT BEACH, WITH FOLLOWUP CORRESPONDENCE The meeting was held as described in the Meeting Notice (Attachment A).
In attendance were representatives from the NRC Staff, Sandia National Laboratory, NUMARC, EPRI, SAIC, Wisconsin Electric Power, Westinghouse, Southern Co. Services, CFA, Inc., and ERC International, as indicated on the attached Attendance sheet (Attachment B).
A package of material was distributed at the meeting (Attachment C) consisting of: (1) the subject EPRI/WOG/NUMARC analysis ("EPRI/W0G Analysis of Decay Heat Removal Risk at Point Beach," NSAC/113, March,1988); (2) a package of slides that were presented at the meeting ("Differences between Sandia and NUMARC Analysis of Deca)" Heat Pemoval Related Risk for Point Beach," 31 March 1988 Whit meeting (letter to Ms. Elaine Gorham-Bergeron, SNL, from Mr. John J. Haugh, NSAC, March 31, 1988, with attached ENCLOSURE, "Responses to SNL Questions on EPRI/WOG Analysis of DHR at Point Beach," March 30, 1988); (4) .1 set of three slides consisting of one map and two handwritten sheets regarding seismic hazards at various sites; and (5) a Sandia submittal for discussion at the meeting ("Supplemental Analyses and Coments/ Responses to EPRI/WOG Analysis of Decay Heat Removal Risk at Point Beach," by David M. Ericson, Jr. , ERC International for Sandia National Lab. , Final Draf t dated March 30,1988).
The purpose of the meeting was to discuss differences between the subject industry-sponsored analysis of Point Beach, and an earlier analysis of the same i plant which was sponsored by the NRC steff and performed by SNL as part of the resolution of Unresolved Safety Issue (USI) A-45, "Decay Heat Removal Requirements." The objective of the meeting was to provide the NRC Staff with sufficient infonnation to allow completion of a preliminary staff evaluation of the industry-sponsored analysis. An earlier meeting had been held, during which NRC Staff representatives had outlined the subjects (to be discussed at this meeting) where more information was needed from industry representatives as bases for the industry sponsored study (Memorandum to farl Kniel, NRC, from Roy Woods, NRC, "Minutes of Feb. 23, 1988 Meeting with Sandia and NUMARC Regarding EPRI/WOG/NUMARC Analysis of One USI A-45 Plant," March 3, 1988).
8805250187 800426 PDR P ADOCK 05000266 PDR j
Discussions concentrated on exploring core melt frequency differences, with a minor portion of the meeting devoted to cost and consequence differences as time permitted.
The package distributed at the meeting (Attachment C) presents the subjects discussed at this meeting in some detail. That level of detail will therefore not be re-iterated in this Sumary.
In summary, it was considered reasonable by the NRC Staff and Sandia representatives to allow more credit for lower frequency of the SBLOCA, presence of the new batteries, and lack of dependence of the SI pumps upon availability of the CCW system (the SOLOCA frequency change is the dominant one) as proposed in the EPRI/WOG study. It was not considered prudent by NRC/SNL to allow more credit for many of the operator recovery actions proposed ,
l in the EPRI/WOG study, The NRC staff believes that the approximate core damage frequency that would result from use of these agreements in a "revised" NRC staff sponsored analysis would be about 9E-05 per reactor year. This is below the NRC/SNL case study calculated value of 3E-04 per reactor year, and above the industry-sponsored study calculated result of IE-05 per reactor year.
Additional details concerning differences between the two analyses are d documented in Enclosure D. The material in this Enclosure was not presented at the meeting. Rather, it was produced as a result of the meeting and in fulfillment of the above stated objective of the meeting, to enable the NRC Staff to write a preliminary evaluation of the industry sponsored Point Beach Analysis. The material is presented with these minutes in order to provide a more complete, coherent record in one place for later reference. Enclosure D consists of the following: (1) Appendix D: Insights Gained From Industry-Sponsored Study of Point Beach, from the NRC Staff's Regulatory and Backfit Analysis: Unresolved Safety Issue A-45, Shutdown Decay Heat Removal Requirements, NUREG-1289 (Draf t), April,1988; (2) Letter from E. Bergeren (SNL) to R. Woods (NRC) April 27, 1988, with attached "Supplemental Analyses and Coments/ Responses to EPRI/WOG Analysis of Decay Heat Removal Risk a- Point Beach" by D. Ericson, Jr., ERC International, April ?5, 1988.
Roy Woods, Senior Task Manager Reactor and Plant Safety Issues Branch Division of Reactor and Plant Systems, RES DISTRIBUTION: RWoods FCoffman RPSIB R/F 'PDR-BSheron Ofc. of the Secy of the Commmission WMinners MCunningham Meeting Attendees JMurphy GMazetis ARubin CFC: RPSIB/DRPS
- RPSIB/DRPS * *see previous concurrences NAME: RWoods:sd GMazetis DATE: 4/ /88 4/ /88 l
Discussions concentrated on exploring core melt frequency differences, with a minor portion of the meeting devoted to cost and consequence differences as i time permitted. ,
i The package distributed at the meeting (Attachment C) presents the subjects l discussed at this meeting in some detail. That level of detail will therefore i not be re-iterated in this Sumary. l In summary, it was considered reasonable by the NRC Staff and ndi a representatives to allow more credit for lower frequency of th SBLOCA presence of the new batteries, and lack of dependence of the SI upon availability of the CCW system (the SBLOCA frequency change is the dominant one) as proposed in the EPRI/W0G study. It was not considered prudent by NRC/SNL to allow more credit for many of the operator recovery actions proposed in the EPRI/WOG study.
The NRC staff believes that the approximate core damage frequency that would result from use of these agreements in a "revised" NRC staff sponsored analysis would be about 9E-05 per reactor year. This is below the NRC/SNL case study calculated value of 3E-04 per reactor year, and above the industry-sponsored study calculated result of IE-05 per reactor year.
Additional details concerning differences between the two analyses are documented in Enclosure D. The material in this Enclosure was not presented at the meeting. Rather, it was produced as a result of the meeting and in fulfillment of the above stated objective of the meeting, to enable the NRC !
Staff to write a preliminary evaluation of the industry sponsored Point Beach )
Analysis. The material is presented with these minutes in order to provide a ;
more complete, coherent record in one place for later reference. Enclosure D l consists of the following: (1) Appendix D: Insights Gained From I Industry-Sponsored Study of Point Beach, from the NRC Staff's Regulatory and Backfit Analysis: Unresolved Safety Issue A-45, Shutdown Decay Heat Removal i Requirements, NUREG-1289 (Draf t), April,1988; (2) Letter from D. Erickson, ERC l International, to R. Woods, NRC Staff, with attached additional comments regarding the EPRI/WOG analysis, April 26, 1988.
Roy Woods, Senior Task Manager Reactor and Plant Safety Issues Branch Division of Reactor and Plant Systems, RES DISTRIBUTION:
RPSIB R/F POR BSheron Office of the Secretary of the Comission WMinners MCunningham fleeting Attendees JMurphy GMazetis A bbin RWoods F man 0FC: RPS / RPS R '! DRPS NAME: RWoods:sd G e is DATE: 4/m/88 4$ /88
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