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MONTHYEARML20216H8631999-09-24024 September 1999 Summary of 990714 Meeting with Cyap & Bpc Re Hazards Analysis of Proposed Installation of Natural gas-fired, Turbine Driven Electric Generation Facility on Site of Haddam Neck Plant.List of Attendees & Meeting Notes Encl Project stage: Meeting 1999-09-24
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Category:MEETING MINUTES & NOTES--CORRESPONDENCE
MONTHYEARML20212H1911999-09-24024 September 1999 Summary of 990819 Meeting with Util & DOT to Discuss Packaging & Applicable Regulations for Haddam Neck Rv Shipment Scheduled for September 2000 ML20216H8631999-09-24024 September 1999 Summary of 990714 Meeting with Cyap & Bpc Re Hazards Analysis of Proposed Installation of Natural gas-fired, Turbine Driven Electric Generation Facility on Site of Haddam Neck Plant.List of Attendees & Meeting Notes Encl ML20212J5991999-06-28028 June 1999 Summary of 990602 Meeting with Licensees to Discuss Safety & Licensing Requirements Applicable to Installation of Natural gas-fired,turbine-driven Electric Generation Facility on Site at Haddam Neck Plant ML20151W9361998-09-10010 September 1998 Summary of 980902 Meeting W/Duke Engineering & Services in Rockville,Md Re Plans to Transport Haddam Neck Reactor Vessel to Disposal Site in Barnwell,Sc.List of Meeting Attendees & Agenda,Encl ML20137Y9151997-04-21021 April 1997 Summary of 970410 Meeting W/Util in Rockville,Md Re Defueled Safeguards Plan.Portion of Meeting Concerned Proprietary Safeguards Info & Closed to Public.List of Attendees & Meeting Agenda Encl ML20140H5481996-12-19019 December 1996 Summary of 436th ACRS Meeting on 961107-09 Re Proposed Rule & Reg Guide Concerning SG Integrity.Completed Repts,Ltrs, Memos & Draft Repts Listed.Highlights of Key Issues, Considered by Committee,Submitted ML20129G7911996-10-23023 October 1996 Summary of 960904 Meeting W/Cyap in Rockville,Md Re Licensee Evaluation That Concluded That Loads on SW Sys Would Be Unacceptable Following LOCA or MSLB Accident W/Concurrent LNP Event.List of Attendees Encl ML20056H0291993-07-15015 July 1993 Summary of Operating Reactors Events Meeting 93-25 on 930707.Attendance List,Significant Elements of Discussed Events & Reactor Scram Statistics for Wk Ending 930704 Encl ML20062C8111990-10-16016 October 1990 Summary of Operating Reactors Events Meeting 90-25 on 901010.List of Attendees,Reactor Scram Statistics & Tabulation of Events Encl ML20059B7331990-08-23023 August 1990 Summary of Operating Reactors Events Meeting 90-21 on 900822.Reactor Scram Statistics Encl ML20058L5721990-08-0101 August 1990 Summary of 900628 Meeting W/Util in Berlin,Ct Re Licensing Issues Associated W/Facilities,Including Generic Ltrs ML20058K4531990-06-28028 June 1990 Summary of 900613 Meeting W/Util Re Status of Crdr at Facilities.Util Agreed to Provide Isap Ranking of All Human Engineering Discrepancies Identified at Plants by 900830. Meeting Handout Encl ML20247B9101989-03-20020 March 1989 Summary of 890228 Meeting W/Util in Rockville,Md to Discuss New Switchgear Bldg Compliance W/App R.Handouts,Plant Design Change Requests,Attendance List & Agenda Encl ML20236A0601989-03-0808 March 1989 Summary of 890214-17 Meetings W/Util & Foxboro Co Re Review of Reactor Protection Sys Upgrade Implemented During 1987 Outage ML20207K9461988-10-0404 October 1988 Summary of 880830 Meeting W/Util in Rockville,Md Re Fire protection-related Issues.Draft Fire Protection Engineering Evaluation, Cables on Svc Bldg Outside Wall & List of Attendees Encl ML20154N5221988-05-24024 May 1988 Summary of 880510 Meeting W/Util Re Single Failure Problem W/Charging Pumps Sys.List of Attendees Encl ML20154N4501988-05-24024 May 1988 Summary of 880510 Meeting W/Connecticut Yankee Atomic Power Co & Northeast Utilities to Discuss Plans to Convert from Stainless Steel to Zircaloy Core.List of Attendees & Handout Encl ML20153F0081988-05-0202 May 1988 Summary of 880330 Meeting W/Util to Discuss Justification for Continued Operation at Reduced Power Levels Due to Calculated Reduced ECCS Flowrate During Large Break Loca. Agenda Viewgraphs Encl ML20153F0931988-04-28028 April 1988 Summary of 880407 Meeting W/Util & Applied Research Assoc Re SEP Topics III-2, Wind & Tornado Loadings & III-4.A, Tornado Missiles. List of Attendees & Viewgraphs Encl ML20153G8991988-04-28028 April 1988 Summary of 880406 Meeting W/Util Re Addl Info Concerning SEP Topic III-6, Seismic Reevaluation. Util Will Provide Listed Info in Response.Util Handout & List of Attendees Encl ML20196J2331988-03-0707 March 1988 Summary of 880208 Meeting W/Util Re NRC 870930 Request for Addl Info Concerning Facility Fire Protection of Safe Shutdown Capability ML20147G7621988-03-0101 March 1988 Summary of 880210 Meeting W/Util & NUS Co Re Reply to 880205 Request for Addl Info Re Modernization of Reactor Protection Sys.Addl Questions Resulting from Meeting & List of Attendees Encl ML20196B2671988-02-0505 February 1988 Summary of 880127 Meeting W/Util Re Use of Dual Role Senior Reactor Operator/Shift Technical Advisor.List of Attendees & Viewgraphs Encl ML20147C3461988-01-0606 January 1988 Summary of 871210 Meeting W/Util in Bethesda,Md Re Full 40-yr OL & Status of Worker ALARA Programs at Plants.List of Attendees & Viewgraphs Encl ML20237D1561987-12-15015 December 1987 Summary of 871201 Meeting W/Util Re Status of Thermal Shield Repair at Plant.Util Handout & Attendance List Encl ML20237D2581987-12-14014 December 1987 Summary of 871119 Meeting W/Util Re New Failure Mode for Steam Generator Tube Ruptures.Westinghouse Determined That Plant May Be Susceptible to Steam Generator Tube Rupture Similar to Rupture at North Anna.Meeting Handouts Encl ML20212F8491987-03-0202 March 1987 Summary of 870218 Meeting W/Util Re Licensee Proposed Plant Mods for Resolution of Recently Identified Small Break LOCA Concerns & Schedule of Completion.Viewgraphs Encl ML20212F2921986-12-30030 December 1986 Summary of Operating Reactors Events Meeting 86-45 on 861222 Re Events Which Occurred Since Last Meeting on 861215.List of Attendees & Significant Elements of Events Discussed Encl ML20215F0151986-12-16016 December 1986 Summary of Operating Reactor Events Meeting 86-43 on 861208. List of Attendees,Events Discussed & Significant Elements of Events 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 ML20207A7781986-11-0505 November 1986 Summary of 861023 Meeting W/Util in Bethesda,Md Re Fire protection-related Issues,Including Separation of Redundant Shutdown Sys in Drywell Expansion Gap ML20215G6351986-09-25025 September 1986 Handwritten Summary of 860925 Meeting W/Util Re Engineering Expertise on Shift.Viewgraphs Encl ML20206M0371986-08-0808 August 1986 Summary of 860508 Meeting W/Util in Region I Ofc Re Questions Resulting from Review of Plant Pump & Valve Inservice Testing Program & Licensee Responses.List of Attendees & Questions Encl 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 ML20211E1981986-06-10010 June 1986 Summary of 860519 Meeting W/Util Re Proposed Changes in Administrative & Reporting Requirements Tech Specs Contained in 820723,830502,850709 & 0813 applications.Marked-up Rev to Tech Specs for Fire Protection Sys Encl ML20210U2221986-05-28028 May 1986 Summary of 860514 Meeting W/Util in Bethesda,Md Re Status of Outstanding Fire Protection Review Issues,Including Util Rept Addressing Generic Ltr 81-12.List of Attendees 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 ML20197F1691986-05-0808 May 1986 Summary of Operating Reactors Events 860428 Meeting W/Listed Divs Re Chernobyl Nuclear Accident & Events at Us Reactors ML20155G9461986-05-0101 May 1986 Summary of 860423 Meeting W/Util Re Request for Exemption from GDC 35 & Results of Small Range of Break Sizes in Loop of RCS Analysis ML20203C0081986-04-15015 April 1986 Summary of 860404 Meeting W/Util & B&W Re Revised Core Loading Pattern.Dnbr & Peak Fuel Centerline Temp Increased But within Design Values for Plant ML20155D9231986-04-11011 April 1986 Summary of 860401 Meeting W/Util Re Requested Schedular Exemption from Fire Protection Mods to Switchgear Room. Discussion Items from Meeting Listed ML20141F4091986-04-10010 April 1986 Summary of Operating Reactors Events Meeting 86-10 W/Ofc Director,Div Directors & Representatives Re Events Since 860324.Viewgraphs & Supporting Documentation Encl ML20141D5941986-03-31031 March 1986 Summary of 860320 Meeting W/Util Re in-house Reload Analysis Capability,Per Generic Ltr 83-11.Viewgraphs Encl ML20154P0071986-03-12012 March 1986 Summary of Operating Reactor Events 860303 Meeting 86-06 W/Ornl Re Events Occurring Since 860224 Meeting.Followup Review Assignments,Status of Previous Assignments,List of Attendees & Viewgraphs Encl ML20154J2871986-03-0303 March 1986 Summary of 860123 Meeting W/Licensee & B&W Re NRC Concerns W/Pending Cycle 14 Reload Application,Methodology for Calculating Reduction in Engineering Hot Channel Factor & Tech Specs Changes ML20138M9761985-12-18018 December 1985 Summary of 851210 Meeting W/Util at Plant Re Pending Requests for Exemptions from Section III.G.2 of App R to 10CFR50 & Request for Addl Info ML20138N3501985-12-17017 December 1985 Summary of 851126 Meeting W/Util Re Proposed Design of Permanent Reactor Cavity Pool Seal & Util Position on Use of leak-before-break.List of Attendees & Viewgraphs Encl ML20210A5011985-11-14014 November 1985 Summary of 851028-30 Meetings W/Utils Re Plant Mods in Response to IE Bulletin 80-11 Masonry Wall Design ML20133C4951985-10-0404 October 1985 Summary of 851002 Meeting W/Util Re Use of Feed & Bleed Core Cooling in Lieu of Qualifying Equipment Outside Containment.Suppl to Safety Evaluation & Schwencer Forwarding Amend 16 to License DPR-61 Encl ML20133E4631985-10-0101 October 1985 Summary of Operating Reactors Events Meeting 85-17 on 850923.List of Attendees & Viewgraphs Encl 1999-09-24
[Table view] Category:MEETING SUMMARIES-INTERNAL (NON-TRANSCRIPT)
MONTHYEARML20216H8631999-09-24024 September 1999 Summary of 990714 Meeting with Cyap & Bpc Re Hazards Analysis of Proposed Installation of Natural gas-fired, Turbine Driven Electric Generation Facility on Site of Haddam Neck Plant.List of Attendees & Meeting Notes Encl ML20212H1911999-09-24024 September 1999 Summary of 990819 Meeting with Util & DOT to Discuss Packaging & Applicable Regulations for Haddam Neck Rv Shipment Scheduled for September 2000 ML20212J5991999-06-28028 June 1999 Summary of 990602 Meeting with Licensees to Discuss Safety & Licensing Requirements Applicable to Installation of Natural gas-fired,turbine-driven Electric Generation Facility on Site at Haddam Neck Plant ML20151W9361998-09-10010 September 1998 Summary of 980902 Meeting W/Duke Engineering & Services in Rockville,Md Re Plans to Transport Haddam Neck Reactor Vessel to Disposal Site in Barnwell,Sc.List of Meeting Attendees & Agenda,Encl ML20137Y9151997-04-21021 April 1997 Summary of 970410 Meeting W/Util in Rockville,Md Re Defueled Safeguards Plan.Portion of Meeting Concerned Proprietary Safeguards Info & Closed to Public.List of Attendees & Meeting Agenda Encl ML20129G7911996-10-23023 October 1996 Summary of 960904 Meeting W/Cyap in Rockville,Md Re Licensee Evaluation That Concluded That Loads on SW Sys Would Be Unacceptable Following LOCA or MSLB Accident W/Concurrent LNP Event.List of Attendees Encl ML20056H0291993-07-15015 July 1993 Summary of Operating Reactors Events Meeting 93-25 on 930707.Attendance List,Significant Elements of Discussed Events & Reactor Scram Statistics for Wk Ending 930704 Encl ML20062C8111990-10-16016 October 1990 Summary of Operating Reactors Events Meeting 90-25 on 901010.List of Attendees,Reactor Scram Statistics & Tabulation of Events Encl ML20059B7331990-08-23023 August 1990 Summary of Operating Reactors Events Meeting 90-21 on 900822.Reactor Scram Statistics Encl ML20058L5721990-08-0101 August 1990 Summary of 900628 Meeting W/Util in Berlin,Ct Re Licensing Issues Associated W/Facilities,Including Generic Ltrs ML20058K4531990-06-28028 June 1990 Summary of 900613 Meeting W/Util Re Status of Crdr at Facilities.Util Agreed to Provide Isap Ranking of All Human Engineering Discrepancies Identified at Plants by 900830. Meeting Handout Encl ML20247B9101989-03-20020 March 1989 Summary of 890228 Meeting W/Util in Rockville,Md to Discuss New Switchgear Bldg Compliance W/App R.Handouts,Plant Design Change Requests,Attendance List & Agenda Encl ML20236A0601989-03-0808 March 1989 Summary of 890214-17 Meetings W/Util & Foxboro Co Re Review of Reactor Protection Sys Upgrade Implemented During 1987 Outage ML20207K9461988-10-0404 October 1988 Summary of 880830 Meeting W/Util in Rockville,Md Re Fire protection-related Issues.Draft Fire Protection Engineering Evaluation, Cables on Svc Bldg Outside Wall & List of Attendees Encl ML20154N5221988-05-24024 May 1988 Summary of 880510 Meeting W/Util Re Single Failure Problem W/Charging Pumps Sys.List of Attendees Encl ML20154N4501988-05-24024 May 1988 Summary of 880510 Meeting W/Connecticut Yankee Atomic Power Co & Northeast Utilities to Discuss Plans to Convert from Stainless Steel to Zircaloy Core.List of Attendees & Handout Encl ML20153F0081988-05-0202 May 1988 Summary of 880330 Meeting W/Util to Discuss Justification for Continued Operation at Reduced Power Levels Due to Calculated Reduced ECCS Flowrate During Large Break Loca. Agenda Viewgraphs Encl ML20153G8991988-04-28028 April 1988 Summary of 880406 Meeting W/Util Re Addl Info Concerning SEP Topic III-6, Seismic Reevaluation. Util Will Provide Listed Info in Response.Util Handout & List of Attendees Encl ML20153F0931988-04-28028 April 1988 Summary of 880407 Meeting W/Util & Applied Research Assoc Re SEP Topics III-2, Wind & Tornado Loadings & III-4.A, Tornado Missiles. List of Attendees & Viewgraphs Encl ML20196J2331988-03-0707 March 1988 Summary of 880208 Meeting W/Util Re NRC 870930 Request for Addl Info Concerning Facility Fire Protection of Safe Shutdown Capability ML20147G7621988-03-0101 March 1988 Summary of 880210 Meeting W/Util & NUS Co Re Reply to 880205 Request for Addl Info Re Modernization of Reactor Protection Sys.Addl Questions Resulting from Meeting & List of Attendees Encl ML20196B2671988-02-0505 February 1988 Summary of 880127 Meeting W/Util Re Use of Dual Role Senior Reactor Operator/Shift Technical Advisor.List of Attendees & Viewgraphs Encl ML20147C3461988-01-0606 January 1988 Summary of 871210 Meeting W/Util in Bethesda,Md Re Full 40-yr OL & Status of Worker ALARA Programs at Plants.List of Attendees & Viewgraphs Encl ML20237D1561987-12-15015 December 1987 Summary of 871201 Meeting W/Util Re Status of Thermal Shield Repair at Plant.Util Handout & Attendance List Encl ML20237D2581987-12-14014 December 1987 Summary of 871119 Meeting W/Util Re New Failure Mode for Steam Generator Tube Ruptures.Westinghouse Determined That Plant May Be Susceptible to Steam Generator Tube Rupture Similar to Rupture at North Anna.Meeting Handouts Encl ML20212F8491987-03-0202 March 1987 Summary of 870218 Meeting W/Util Re Licensee Proposed Plant Mods for Resolution of Recently Identified Small Break LOCA Concerns & Schedule of Completion.Viewgraphs Encl ML20212F2921986-12-30030 December 1986 Summary of Operating Reactors Events Meeting 86-45 on 861222 Re Events Which Occurred Since Last Meeting on 861215.List of Attendees & Significant Elements of Events Discussed Encl ML20215F0151986-12-16016 December 1986 Summary of Operating Reactor Events Meeting 86-43 on 861208. List of Attendees,Events Discussed & Significant Elements of Events 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 ML20207A7781986-11-0505 November 1986 Summary of 861023 Meeting W/Util in Bethesda,Md Re Fire protection-related Issues,Including Separation of Redundant Shutdown Sys in Drywell Expansion Gap ML20215G6351986-09-25025 September 1986 Handwritten Summary of 860925 Meeting W/Util Re Engineering Expertise on Shift.Viewgraphs Encl ML20206M0371986-08-0808 August 1986 Summary of 860508 Meeting W/Util in Region I Ofc Re Questions Resulting from Review of Plant Pump & Valve Inservice Testing Program & Licensee Responses.List of Attendees & Questions Encl 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 ML20211E1981986-06-10010 June 1986 Summary of 860519 Meeting W/Util Re Proposed Changes in Administrative & Reporting Requirements Tech Specs Contained in 820723,830502,850709 & 0813 applications.Marked-up Rev to Tech Specs for Fire Protection Sys Encl ML20210U2221986-05-28028 May 1986 Summary of 860514 Meeting W/Util in Bethesda,Md Re Status of Outstanding Fire Protection Review Issues,Including Util Rept Addressing Generic Ltr 81-12.List of Attendees Encl ML20197F1691986-05-0808 May 1986 Summary of Operating Reactors Events 860428 Meeting W/Listed Divs Re Chernobyl Nuclear Accident & Events at Us Reactors 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 ML20155G9461986-05-0101 May 1986 Summary of 860423 Meeting W/Util Re Request for Exemption from GDC 35 & Results of Small Range of Break Sizes in Loop of RCS Analysis ML20203C0081986-04-15015 April 1986 Summary of 860404 Meeting W/Util & B&W Re Revised Core Loading Pattern.Dnbr & Peak Fuel Centerline Temp Increased But within Design Values for Plant ML20155D9231986-04-11011 April 1986 Summary of 860401 Meeting W/Util Re Requested Schedular Exemption from Fire Protection Mods to Switchgear Room. Discussion Items from Meeting Listed ML20141F4091986-04-10010 April 1986 Summary of Operating Reactors Events Meeting 86-10 W/Ofc Director,Div Directors & Representatives Re Events Since 860324.Viewgraphs & Supporting Documentation Encl ML20141D5941986-03-31031 March 1986 Summary of 860320 Meeting W/Util Re in-house Reload Analysis Capability,Per Generic Ltr 83-11.Viewgraphs Encl ML20154P0071986-03-12012 March 1986 Summary of Operating Reactor Events 860303 Meeting 86-06 W/Ornl Re Events Occurring Since 860224 Meeting.Followup Review Assignments,Status of Previous Assignments,List of Attendees & Viewgraphs Encl ML20154J2871986-03-0303 March 1986 Summary of 860123 Meeting W/Licensee & B&W Re NRC Concerns W/Pending Cycle 14 Reload Application,Methodology for Calculating Reduction in Engineering Hot Channel Factor & Tech Specs Changes ML20138M9761985-12-18018 December 1985 Summary of 851210 Meeting W/Util at Plant Re Pending Requests for Exemptions from Section III.G.2 of App R to 10CFR50 & Request for Addl Info ML20138N3501985-12-17017 December 1985 Summary of 851126 Meeting W/Util Re Proposed Design of Permanent Reactor Cavity Pool Seal & Util Position on Use of leak-before-break.List of Attendees & Viewgraphs Encl ML20210A5011985-11-14014 November 1985 Summary of 851028-30 Meetings W/Utils Re Plant Mods in Response to IE Bulletin 80-11 Masonry Wall Design ML20133C4951985-10-0404 October 1985 Summary of 851002 Meeting W/Util Re Use of Feed & Bleed Core Cooling in Lieu of Qualifying Equipment Outside Containment.Suppl to Safety Evaluation & Schwencer Forwarding Amend 16 to License DPR-61 Encl ML20133E4631985-10-0101 October 1985 Summary of Operating Reactors Events Meeting 85-17 on 850923.List of Attendees & Viewgraphs Encl ML20127K0201985-05-17017 May 1985 Summary of 850430 & 0501 Meetings W/Util in Berlin,Ct Re Status of Licensing Actions & Integrated Safety Assessment Program.Purchase of Spare Main Transformer & Improvements to Secondary Water Chemistry Program Discussed 1999-09-24
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r ,
pm g i UNITED STATES
,g } NUCLEAR REGULATORY COMMISSION g WASHINGTON, D.C. 3066H001
%,....+f September 24, 1999 LICENSEE: Connecticut Yankee Atomic Power Company FACILITY: Haddam Neck Plant
SUBJECT:
SUMMARY
OF PUBLIC MEETING DISCUSSING NATURAL GAS HAZARDS OF A PROPOSED INSTALLATION AT HADDAM NECK (TAC NO. MA5757)
On July 14,1999, the NRC staff met with representatives of Connecticut Yankee Atomic Power Company (CY, or the licensee) and Bechtel Power Corporation (Bechtel) to discuss the hazards analysis of a proposed installation of a natural gas fired, turbine driven electric generation facility on the site of the Haddam Neck Plant in Connecticut. The meeting was open to the public. A list of the attendees is included as Enclosure 1.
Bechtel prevented the results of three natural gas hazard scenarios for the installation, as outlined in the enclosed meeting notes (Enclosure 2). In order to present an explosion hazard, natural gas must accumulate in an enclosed space, such as a building. Bechtel summarized the results of two scenarios that examined the building explosion hazards. The third scenario considered the formation of a free gas cloud, followed by ignition and explosion. Bechtel noted that experiments conducted in Germany and England found that methane / air gas clouds were non-detonable. However, Bechtelincluded analysis of the overpressure from an unconstrained cloud of gas under the assumption that ignition was possible.
Bechtel's preliminary conclusion was that the calculated overpressures from an explosion were acceptable for the spent fuel building or an independent spent fuel storage facility.
A summary was presented of the results of an analysis of building fragment missiles, generated by an explosion, striking the spent fuel building and dry storage casks. The mass and velocity of the fragments are within the boundaries of a tornado missile evaluation done for the systematic evaluation program.
The NRC staff suggested the final analysis should consider the following items:
(1) the effect on spent fuel storage safety if the control room is unavailable for use; (2) overpressure peak reflection effects on buildings; (3) natural gas accumulation in the cooling discharge tunnel; (4) when the property underlying the installation should be released for unrestricted use;
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W FRF R&NTEC COPY 9910040077 990924 PDR ADOCK 05000213 P PDR
(5) fragment missiles from buildings evaluated in Case 3 (of Bechtel's meeting notes); and (6) risk perspective and the probability of occurrence of an explosion.
/ M -
Thomas L. Fredrichs, Project Manager Decommissioning Section Project Directorate IV & Decommissioning Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-213
Enclosures:
- 1. List of Attendees
- 2. Meeting Notes cc w/enci 1: See next page i
l
Haddam Neck Plant cc:
Mr. Allan Johanson, Assistant Director Ms. Deborah B. Katz, President Office of Policy and Management Citizens Awareness Network Policy Development and Planning Division P. O. Box 83 450 Capitol Avenue - MS# 52ERN Shelburne Falls, MA 01370-0083 P. O. Bo 341441 Hartford, CT 06134-1441 Mr. G. P. van Noordonnen Manager- Nuclear Licensing Regional Administrator Northeast Utilities Service Company Region 1 362 Injun Hollow road U.S. Nuclear Regulatory Commission East Hampton, CT 06424-3099 475 Allendale Road .
j King of Prussia, PA 19406 Mr. D. K. Davis Chairman, President and Chief Board of Selectmen Executive Officer Town Office Building Connecticut Yankee Atomic Power Co.
Haddam, CT 06438 580 Main Street Bolton, MA 01740 Mr. James S. Robinson Manager, Nuclear Investments Mr. T. W. Bennet and Administration Vice President and Chief Financial officer New England Power Company Connecticut Yankee Atomic Power Co.
, 25 Research Drive 580 Main Street Westborough, MA 01582 Bolton, MA 01740 Mr. Russell A. Mellor Director Vice President - Operations and Monitoring and Radiation Division !
Decommissioning Department of Environmental Protection Connecticut Yankee Atomic Power Co. 79 Elm Street 362 Injun Hollow Road Hartford, CT 06106-5127
! East Hampton, CT 06424-3099 l Mr. G. H. Bouchard, Unit Director i Mr. J. A. Ritsher Connecticut Yankee Atomic Power Co.
Connecticut Yankee Atomic Power Co. 362 injun Hollow Road i Ropes & Gray East Hampton, CT 06424-3099 1 One International Place Boston, MA 02110-2624 Mr. J. D. Haseltine Strategic Planning Director Mr. K. J. Heider, Decommissioning Director Connecticut Yankee Atomic Power Co.
Connecticut Yankee Atomic Power Co. 362 Injun Hollow road 362 Injun Hollow Road East Hampton, CT 06424-3099 East Hampton, CT 06424-3099 ,
Mr. Russell A. Mellor l Mr. M. D. Cavanaugh Vice President- Operatiens and Communications Manager Decommissioning Connecticut Yankee Atomic Power Co. Connecticut Yankee Atomic Power 362 Injun Hallow Road Company East Hampton, CT 06424-3099 362 Injun Hollow Road East Hampton, Connecticut 06424-3099
l ATTENDEES l Connecticut Yankee Public Meeting Natural Gas Hazards of a Proposed installation at Haddam Neck July 14,1999 NAME ORGANIZATION l Tom Fredrichs NRC
' Ann Hodgdon NRC 1
Michael T. Masnik NRC Sam Nalluswami NRC Steven West NRC K. M. Campe NRC John Hasettine CY Gerry van Nordennen CY Keith Sickles CY Steve Routh Bechtel Allen Viera Bechtel
( Yijen Ling Bechtel Jim Ray Bechtel Ron Fischer Bechtel Ping Wan Bechtel I David Lochbaum . Union of Concerned Scientists Steve Shulin The IBEX Group l l l )
l 0
Enclosure 1 l
u_ _ __ .. _
4 NRC/CYAPCO Meeting Haddam Neck Repowering Hazards Analyses July 14,1999 Purpose of Meetine e Technical working meeting with NRC Staff to address details of planned technical evaluation of Natural Gas (NG) hazards e To present approach to assessing effects of NG hazards e To obtain NRC input
. To result in subsequent complete submittal that will be acceptable to NRC Staff DescrIDilon of NG Facility e Separate facility, developed and operated by an independent developer / owner e Constmeted and placed into operation while spent fuel is stored in Spent Fuel Building (SFB) and decommissioning activities are underway
. Will be in operation during long term storage of spent fuel in the onsite Independent Spent Fuel Storage Installation (ISFSI)
. Specifics and General Arrangement DescriDtion of Natural Gas Hazard Scenarios e Case 1 - Explosion Inside the Combustion Turbine Generator (CTG) Building
. Evaluate NG and Hydrogen (used for cooling) e Evaluate effect of missile fragments as result of explosion e Case 2 - Flammable Clouds in Free Field Traveling Toward SFB and ISFSI e Case 3 - Explosion Inside Buildings Within Flammable Cloud Range I
Assumptions e NG Explosion in CTG Bldg - Case 1
. Entire CTG Building fills up with NG e Flammable limits of NG similar to methane (LFL=5%; UFL=15%)
- Amount of NG available for explosion conservatively assumed to be 15% of free volume
- Assume building does not impede explosion effects l
i e NG Cloud in Free Field - Case 2
+ Look at both 10" and 16" lines
. Upon assumed pipe break, assume horizontaljet toward SFB and ISFSI e Release is continuous at constant rate l
ENCLOSURE 2 L
- Release is simulated by considering a series of continuous puffs (Regulatory Guide 1.78) e Flammable mass integrated along paths of the puffs to simulate continuous release
. Conservatively assume CTG Building has no effect in diluting initial release (Building effects not considered) e F (stable) stability assumed to minimize atmospheric dispersion. (Centerline concentrations for unstable and neutral conditions also estimated and found to be lower)
- No plume rise, for conservatism
. Experiments in Germany and UK indicate methane / air mixtures non-detonable.
However, overpressures estimated assuming detonation is possible e To estimate overpressure, assume explosion occurs at location of maximum flammable mass.
. NG Explosion in Other Buildings Within Flammable Cloud Range - Case 3
- No NG sources in other buildings
- NG accumulation in buildings unlikely
- CTO Building wake would impede cloud from reaching intermediate buildings.
. Conservatively assume NG cloud would leak into buildings e Evaluate explosions originating in buildings in which passing cloud is within NG flammability limits e Evaluate Office Building #3 and Warehouse #141 e Amount of NG available for explosion conservatively assumed to be 15% of free volume e Building does not impede explosion effects e Fragment Missile Evaluation from CTG Building Explosion e Comparisons made to study done for NRC on Fort St. Vrain docket
- CTG Building valume is same as that modeled in Fort St. Vrain study Methodolorv e Pipe frictional loss considered in estimating release rates through constant area pipe e Two pipe break locations evaluated:
e 16" pipe at metering station - Assume 500 psi,82.55 kg/sec release (Main line expected to be at 350 psi) e 10" pipe supplying eastemmost CTG (closest to SFB)- Assume 450 psi,68.56 kg/sec release (Main line expected to be at 350 psi) e Safe distance calculated as per Regulatory Guide 1.91
u ._ . . . _ ._ . ~ . _ . _ _ _ - - . _ _ _ . . . . _ . .. - . . - -
, .~
r .
- Flammable mass calculated using volume integration of puff between outer (lean flammable limit) and inner (rich flammable limit) ellipsoids (relationship between off-centerline concentration and centerline concentration of a puff is in form of an ellipse) e To accurately calculate flammaable mass:
. Calculate lean and rich flammable limits of plume at every 25 m distance e Estimate average concentrations e Flammable mass converted to TNT equivalent energy to calculate overpressure e Calculate mass of equivalent TNT energy for unconfined vapor cloud using empirical formula in loss Prevention data (1994), with approximate energy of decomposition forTNTof 2000 Btu /lb e Used conservative effective yield of 20% (Zalosh,1995) based on turbulent jet-like release e For confined explosion, estimate mass of equivalent TNT energy using method in Regulatory Guide 1.91 (240%)
l Preliminary Results 1
e Flammable clouds do not exist beyond 200 m for 16" pipe break and beyond 175 m for 10" pipe break e This is conservative, based on Computational Fluid Dynamics study done for l
comparative purposes e Worst case effect is due to explosion in CTG Building e Results in 1.66 psi overpressure at SFB l
e Results in 0.60 psi overpressure at ISFSI l
e Effect on the SFB is expected to be acceptable l
l e Peak overpressures are less than the design capacity of the NAC cask e ISFSI will be located a sufficient distance from the NG facility to ensure any postulated missiles are less than previously evaluated for the NAC cask ;
- SFB location of 720' from epicenter af assumed CTG explosion would result in steel missiles reaching SFB that are no greater than 1/8" thick, with velocities no greater than 193 ft/sec This is enveloped by the tomado missile evaluation performed for the SEP.
i i
September 24, 1999 (5) fragment missiles from buildings evaluated in Case 3 (of Bechtel's meeting notes); and (6) risk perspective and the probability of occurrence of an explosion.
ORIG. SIGNED BY Thomas L. Fredrichs, Project Manager Decommissioning Section Project Directorate IV & Decommissioning i Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-213
Enclosures:
- 1. List of Attendees
- 2. Meeting Notes cc w/ encl 1: See next page DISTRIBUTION:
E-Mall HARD COPY JZwolinski/SBlack SWest MFairtile Docket File 50-213 GRichards DWheeler DLange PUBLIC GPangburn, RI Pray OGC LPittiglio _ MWebb PDIV-D r/f WHuffman JMinns RDudley AHodgdon RBellamy,RI ACRS/ACNW KCampe JHickey To receive a copy of this document, indicate "C" in the box OFFICE PDIVD/PM C PDIV-1/L4 0 N PDIV-2/SC C NAME TFredrichs $ fLBerry h MMasnik fY DATE 9 /d /99 9 /$[/99 9 / gj/99 DOCUMENT NAME: G:\PDIV-3\Haddam\ summary.wpd OFFICIAL RECORD COPY i