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Category:MEETING MINUTES & NOTES--CORRESPONDENCE
MONTHYEARML20195D6201999-05-24024 May 1999
Summary of 990511 Meeting with New York Power Authority in Rockville,Maryland Re Licensee Plans for Insp of Reactor Vessel Welds at Ja FitzPatrick Npp.List of Meeting Attendees & Copy of Meeting Handout Encl
ML20206G2371999-05-0404 May 1999
Summary of 990414 Meeting with NYPA in Rockville,Md Re Proposed Improved TSs for Plant,Which Was Submitted on 990331.List of Attendees & Handouts Provided by NYPA Encl
ML20248L8531998-06-0404 June 1998
Summary of 980521 Meeting W/Util in Rockville,Md Re Plans for Mod of ECCS Suction Strainers.Subj Mods Respond to NRC Bulletin 96-003.List of Attendees & Handouts Encl
ML20059C7641993-05-0707 May 1993
Summary of 394th ACRS Meeting on 930211-13 in Bethesda,Md Re Key Policy Issues for Advanced Reactor Designs,Schedules for NRC Review of Proposed Reactor Designs & Reactor Operating Experience on Restart of FitzPatrick Nuclear Plant
ML20059C7181993-04-0707 April 1993
Summary of 389th ACRS Meeting on 920910-12 in Bethesda,Md Re Comments on Staff Review of Westinghouse AP600 Design,Nrr Action Re IPE for FitzPatrick Nuclear Plant & Status of Implementation of Findings of NRC Regulatory Impact Survey
ML20245H3751989-08-0808 August 1989
Summary of 890731 Meeting W/Util & Eg&G Idaho in Rockville, MD to Discuss Various Aspects of Inservice Testing Program at Facility,Per Generic Ltr 89-04.Request for Addl Info,Sent to Licensee by & List of Attendees Encl
ML20206A4591988-11-0707 November 1988
Summary of 881027 Meeting W/Util in Rockville,Md Re Various Aspects & Repair Plans Concerning IGSCC Indications.List of Attendees & Ref Matl Encl
ML20205G1391988-10-24024 October 1988
Summary of 881011 Meeting W/Util & GE in Rockville,Md Re Core Spray in-vessel Pipe Crack.List of Attendees & Ref Matls Supplied by Licensee Encl
ML20153G6331988-08-30030 August 1988
Summary of Operating Reactor Events Meeting 88-35 on 880830, Including Summary of Reactor Scrams for Wk Ending 880828. Significant Event Identified for Input to NRC Performenance Indicator Program
ML20215G0561986-10-0707 October 1986
Summary of 860911 Meeting W/Bwr Owners Group in Bethesda,Md Re Strawman Generic Requirements for Enhancing BWR Containment Performance in Severe Accident Conditions.Second Technical Exchange Meeting in mid-Nov 1986 Proposed
ML20211P1361986-07-16016 July 1986
Summary of 860707 Operating Reactor Events Meeting 86-23 W/ Div Directors & Representatives Re Events Since Last Meeting on 860630.Notification of Inability to Meet Assigned Target Completion Dates for Actions Requested.Viewgraphs Encl
ML20127D1571985-06-13013 June 1985
Summary of 850530 Operating Reactor Events Meeting to Brief Ofc Director,Div Directors & Representatives on Events Since 850515 Meeting.List of Attendees,Viewgraphs & Status of Assignments Encl
ML20128N4771985-05-22022 May 1985
Summary of Operating Reactors Events 850515 Meeting.Div Directors or Representatives Briefed on Events Occurring Since 850507 Meeting.Assignment of Followup Review Responsibilities Discussed.Attendance List Encl
ML20133K2961985-03-31031 March 1985
Summary of ACRS Class 9 Accidents Subcommittee 850314 Meeting W/Pasny & Risk Mgt Assoc in Washington,Dc Re Recent Source Term Assessment Under Severe Accident Conditions
ML20125C5621978-05-0101 May 1978
Summary of 780309-10 Meeting W/Mark I Owners Group in Bethesda,Md Re Changes in Long Term Program as Reflected in Rev 3 to Mark I Owners Group Program Action Plan
ML20127A4681978-03-0101 March 1978
Summary of 771129 Meeting W/Mark I Owners Group & GE in San Franciso,Ca Re Listed Topics,Including Results & Bases for long-term Program Decision Point 3.List of Attendees & Viewgraphs Encl
ML20141N3471977-05-20020 May 1977
Summary of 770411 Meeting W/Mark I Owners Group & GE to Discuss Structural Acceptance Criteria for Mark I Containment long-term Program.List of Attendees Encl
ML20125C5721976-09-0909 September 1976
Summary of 760819 Meeting W/Mark I Owners Group,(Ge) in Bethesda,Md Re Discussions on Mark I Containment Ltp.List of Attendees Encl
ML20125C5711976-09-0909 September 1976
Summary of 760812 Meeting W/Mark I Owners Group,Ge,Epri & Techncial Consultants Re Listed Long Term Program Tasks
ML20125D6581976-08-18018 August 1976
Summary of 760717-08 Meeting W/Representatives of Mark I Owners Group in Bethesda,Md Re Discussions on Reassessed Content of Mark I Containment LTP & Recently Submitted Responses to Questions on STP Final Rept
ML20248E4101970-01-27027 January 1970
Summary of ACRS 700123-24 Meetings Re Util Application to Construct Fitzpatrick Nuclear Power Plant.Related Info Encl
1999-05-04
[Table view]
Category:MEETING SUMMARIES-INTERNAL (NON-TRANSCRIPT)
MONTHYEARML20195D6201999-05-24024 May 1999
Summary of 990511 Meeting with New York Power Authority in Rockville,Maryland Re Licensee Plans for Insp of Reactor Vessel Welds at Ja FitzPatrick Npp.List of Meeting Attendees & Copy of Meeting Handout Encl
ML20206G2371999-05-0404 May 1999
Summary of 990414 Meeting with NYPA in Rockville,Md Re Proposed Improved TSs for Plant,Which Was Submitted on 990331.List of Attendees & Handouts Provided by NYPA Encl
ML20248L8531998-06-0404 June 1998
Summary of 980521 Meeting W/Util in Rockville,Md Re Plans for Mod of ECCS Suction Strainers.Subj Mods Respond to NRC Bulletin 96-003.List of Attendees & Handouts Encl
ML20059C7641993-05-0707 May 1993
Summary of 394th ACRS Meeting on 930211-13 in Bethesda,Md Re Key Policy Issues for Advanced Reactor Designs,Schedules for NRC Review of Proposed Reactor Designs & Reactor Operating Experience on Restart of FitzPatrick Nuclear Plant
ML20059C7181993-04-0707 April 1993
Summary of 389th ACRS Meeting on 920910-12 in Bethesda,Md Re Comments on Staff Review of Westinghouse AP600 Design,Nrr Action Re IPE for FitzPatrick Nuclear Plant & Status of Implementation of Findings of NRC Regulatory Impact Survey
ML20245H3751989-08-0808 August 1989
Summary of 890731 Meeting W/Util & Eg&G Idaho in Rockville, MD to Discuss Various Aspects of Inservice Testing Program at Facility,Per Generic Ltr 89-04.Request for Addl Info,Sent to Licensee by & List of Attendees Encl
ML20206A4591988-11-0707 November 1988
Summary of 881027 Meeting W/Util in Rockville,Md Re Various Aspects & Repair Plans Concerning IGSCC Indications.List of Attendees & Ref Matl Encl
ML20205G1391988-10-24024 October 1988
Summary of 881011 Meeting W/Util & GE in Rockville,Md Re Core Spray in-vessel Pipe Crack.List of Attendees & Ref Matls Supplied by Licensee Encl
ML20153G6331988-08-30030 August 1988
Summary of Operating Reactor Events Meeting 88-35 on 880830, Including Summary of Reactor Scrams for Wk Ending 880828. Significant Event Identified for Input to NRC Performenance Indicator Program
ML20215G0561986-10-0707 October 1986
Summary of 860911 Meeting W/Bwr Owners Group in Bethesda,Md Re Strawman Generic Requirements for Enhancing BWR Containment Performance in Severe Accident Conditions.Second Technical Exchange Meeting in mid-Nov 1986 Proposed
ML20211P1361986-07-16016 July 1986
Summary of 860707 Operating Reactor Events Meeting 86-23 W/ Div Directors & Representatives Re Events Since Last Meeting on 860630.Notification of Inability to Meet Assigned Target Completion Dates for Actions Requested.Viewgraphs Encl
ML20127D1571985-06-13013 June 1985
Summary of 850530 Operating Reactor Events Meeting to Brief Ofc Director,Div Directors & Representatives on Events Since 850515 Meeting.List of Attendees,Viewgraphs & Status of Assignments Encl
ML20128N4771985-05-22022 May 1985
Summary of Operating Reactors Events 850515 Meeting.Div Directors or Representatives Briefed on Events Occurring Since 850507 Meeting.Assignment of Followup Review Responsibilities Discussed.Attendance List Encl
ML20133K2961985-03-31031 March 1985
Summary of ACRS Class 9 Accidents Subcommittee 850314 Meeting W/Pasny & Risk Mgt Assoc in Washington,Dc Re Recent Source Term Assessment Under Severe Accident Conditions
ML20125C5621978-05-0101 May 1978
Summary of 780309-10 Meeting W/Mark I Owners Group in Bethesda,Md Re Changes in Long Term Program as Reflected in Rev 3 to Mark I Owners Group Program Action Plan
ML20127A4681978-03-0101 March 1978
Summary of 771129 Meeting W/Mark I Owners Group & GE in San Franciso,Ca Re Listed Topics,Including Results & Bases for long-term Program Decision Point 3.List of Attendees & Viewgraphs Encl
ML20141N3471977-05-20020 May 1977
Summary of 770411 Meeting W/Mark I Owners Group & GE to Discuss Structural Acceptance Criteria for Mark I Containment long-term Program.List of Attendees Encl
ML20125C5721976-09-0909 September 1976
Summary of 760819 Meeting W/Mark I Owners Group,(Ge) in Bethesda,Md Re Discussions on Mark I Containment Ltp.List of Attendees Encl
ML20125C5711976-09-0909 September 1976
Summary of 760812 Meeting W/Mark I Owners Group,Ge,Epri & Techncial Consultants Re Listed Long Term Program Tasks
ML20125D6581976-08-18018 August 1976
Summary of 760717-08 Meeting W/Representatives of Mark I Owners Group in Bethesda,Md Re Discussions on Reassessed Content of Mark I Containment LTP & Recently Submitted Responses to Questions on STP Final Rept
ML20248E4101970-01-27027 January 1970
Summary of ACRS 700123-24 Meetings Re Util Application to Construct Fitzpatrick Nuclear Power Plant.Related Info Encl
1999-05-04
[Table view] |
Text
AoRs- a 29 A PAC /6/7W
. DATE ISSUED: 3/31/85 3 M is PROPOSED MEETING
SUMMARY
/ MINUTES FOR THE ACRS CLASS 9 ACCIDENTS SUBCOMMITTEE MEETING MARCH 14, 1985 - WASHINGTON, DC Purpose The Subcommittee met with New York Power Authority (NYPA) on March 14, 1985 to discuss their recent assessment of the source term under certain severe accident conditions for Fitzpatrick. NYPA also proposed to address various Subcomittee comments and questions as a result of a similar meeting on the Indian Point-3 (IP-3) source term reassessment.
Principal Attendees:
ACRS NYPA W. Kerr, Chairman H. Specter P. Shewmon, Member R. Deem I. Catton, Consultant W. Iyer J. Lee, Consultant A. Wang, Staff, DF0 Risk Management Associates P. Bieniarz Introduction W. Kerr opened the meeting and comended NYPA on its efforts. He inquired what are NYPA's motives for performing this work. H. Specter stated NYPA proposed to address earlier Subcomittee coments on their IP-3 source tern assessment and then present some results of their current source term reassessment of Fitzpatrick. He stated that NYPA has attempted to seek coments on their work from as many different forums as possible. The final usage of this work is still being debated. For IP-3, he. hopes this work will be used in some future licensing decisions. For Fitzpatrick, the usage would be different as they have not gone through a hearing. BWR Mark I's have received some 8510210164 050331 PDR ACRS 2292 PDR g,gi- A
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i i Class 9 Accidents Minutes March 14, 1985 notoriety from some other analysis as risk outliers with regard to source terms. NYPA is hoping to learn more about Mark I's to avoid an IP-3 like hearings in the future.
Indian Point-3 P. Bienfarz stated as a result of the last Subcommittee meeting NYPA has done a parametric study for the large overpressurization accident at IP-3 for various leak rates. The leak rates were in addition to the design leak rate. Hole sizes were estimated by determining the area of a hole which at the design pressure of the containment would result in the leakage rates of interest. D. Ward asked if the study produced a maximum hole size at which point the source term release is unaffected by the hole size. P. Bieniarz stated he believes a hole size of 25 square inches is close to that point. H. Specter stated he believes their study shows as long as the containment fails late (>> 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) the calculated source term release is insensitive to the MARCH code l
calculations. 'NYPA believes one could take the entire core inventory throw it in the air of the containment, let it settle and the source term numbers would be of little changed from a MARCH calculation given that there is no early failure of containment. W. Kerr asked if this is the cese, why even do a MARCH analysis. H. Specter stated this conclusion is highly dependent on the containment type and NYPA also needed'to produce the pressure-time history for the containment.
f CRAC Code Results W. Iyer presented the CPAC code results based on the previous analysis.
W. Kerr asked what level of confidence does NYPA have in these results?
For instance would NYPA be willing to propose changes to their emergency planning based on these numbers? W. Iyer stated he believes the results would not vary by more than 50%. He stated the calculated fatal radius >
is 1.6 miles, and in his opinion could be as high as 2.4 miles, as compared to the 6 miles using WASH-1400 numbers. J. Lee asked NYPA what O
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Class 9 Accidents Minutes March 14, 1985 l
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l are the most significant fission products with respect to early fatalities.
S. Masciulli agreed to provide this information. W. Kerr asked if NYPA was prepared to re-examine their Appendix J test requirements based on the results of their work. H. Specter stated again NYPA has not decided how to apply this work but his own opinion is that the maximum allowed leak rate in Appendix J can be higher.
Fitzpatrick Analysis H. Specter noted that unlike IP-3 there is no PRA available for Fitzpatrick. Because of this NYPA was dependent on the BMI-2104 work to
. determine what sequences should be analyzed. Currently NYPA proposes to analyze four' sequences of which the AE sequence and the ATWS sequence have been completed.
R. Deem noted NYPA has made substantial changes to the MARCH 2.0 code to allow for use for BWR analysis. He stated the most important of these changes was the modelling of the individual safety relief valves.
J. Lee asked whether NYPA is performing a multi-dimensional problem.
P. Bieniarz stated while they are not solving the momentum equation, they are doing a lump parameter-type calculation for each volume.
J. Lee stated since the IP-3 results were concluded to be so insensitive to the MARCH calculations, why go through the trouble of doing a detailed MARCH analysis for Fitzpatrick, P. Bieniarz stated for the smaller volume MARK I containments the time of failure is shorter and the amount of fission product release becomes much more sensitive to the MARCH calculations. R. Deem stated they have also coupled TRAP-MELT, MERGE and CORSOR. This provides a totally coupled set of fission product migration codes that interact and run on the same time clock.
Therefore, at each timestep the program recalculates every important parameter according to the changes that have been calculated throughout all of the computer programs. They have also added models to account
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Class 9 Accidents Minutes March 14, 1985 for fi sion product heating of surfaces, energy losses through insulation, fission product behavior in the vessel after vessel failure and resuspension of deposited solid particles on sudden depressuriza-tion. J. Lee inquired, is there any new physical phenomena modelling.
I. Catton stated he interprets NYPA as saying they have produced a better coordinated, more efficient running code but there has not been a whole lot of new physics introduced. R. Deem stated the algorithms were vectorized where feasible to allow the code to run on a CYBER 205 system. This decreased the run times by approximately a factor of four.
J. Lee and I. Catton questioned why there seemed to be osciallations in the pressure plot. P. Bienairz felt these were instabilities due to the time steps used in the analysis. J. Lee and I. Catton felt more attention should be paid to what seems to be numerical instabilities in NYPA's analysis. W. Kerr asked based on NYPA's analysis is there any case where one might want to limit the amount of water on the core, contrary to current wisdom. R. Deem believes there may be cases where NYPA may someday change their procedures based on this analysis.
W. Kerr closed the meeting by stating he would not put any more effort in fine tuning the source term analysis but would rather concentrate on preventing the possibility of having a severe accident by having a good source of electric power and do everything feasilbe to eliminate the likelihood of an ATWS.
The meeting was adjourned at 6:05 p.m.
NOTE: Additional meeting details can be obtained from a transcript of this meeting available in the NRC Public Document Room, 1717 H Street, N.W., Washington, D.C., or can be purchased from ACE-Federal Reporters, 444 North Capitol Street, Washington, D.C. 20001, (202) 347-3700.
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