Similar Documents at Maine Yankee |
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Category:MEETING MINUTES & NOTES--CORRESPONDENCE
MONTHYEARML20212D1631999-09-20020 September 1999
Summary of 990908 Meeting with Myap in Rockville,Md Re Plant License Termination Plan.List of Attendees & Licensee Handouts Encl
ML20212A3101999-09-14014 September 1999
Summary of 990823 Meeting with Util in Rockville,Md to Discuss License Termination Plan.List of Attendees Encl
ML20210G2711999-07-28028 July 1999
Summary of 990707 Meeting with Util in Rockville,Md to Discuss Licensee Termination Plan.List of Attendance & Handouts Encl
ML20210B7521999-07-21021 July 1999
Summary,For Docket 7200030,of 990707 Meeting with Myap,S&W & NAC Intl Re Util Plans to Store Spent Fuel Using NAC-UMS Dry Storage Sys.Attendance List,Meeting Handouts & Util Rulemaking Handout,Encl
ML20207G2401999-06-0707 June 1999
Summary of 990525 Meeting with Util in Rockville,Md to Discuss Maine Yankee Atomic Power Station License Termination
ML20196C3251998-11-23023 November 1998
Summary of 981109 Meeting with Util & SWEC Re Decommissioning Activities & Schedule at Maine Yankee Atomic Power Station.List of Attendees Enclosed
ML20236S9811998-07-22022 July 1998
Summary of 980710 Meeting W/Util in Rockville,Md Re Plant Backfit Appeal.Appeal Submitted Per NRC Determination Re Plant Emergency Preparedness Exemption
ML20249B8251998-06-17017 June 1998
Summary of 980609 Meeting W/Util in Rockville,Md to Discuss Sf Heatup Analysis That Util Performed in Support of Exemption Requests Submitted Re Emergency Preparedness & Financial Protection
ML20202F4691997-12-0101 December 1997
Summary of 971120 Meeting W/Util in Rockville,Md to Discuss Proposed Defueled TSs for Plant.List of Attendees & Handouts Used by Licensee Encl
ML20202G8591997-12-0101 December 1997
Summary of 971125 Meeting W/Employees of Myap in Rockville, Maryland Re Proposed Defueled Emergency Plan for Myap Station.List of Attendees Encl
ML20211P3801997-10-0808 October 1997
Summary of 970911 Meeting W/Myapco Re Options Available for Storage of Spent Fuel Currently at Site.Meeting Attendee List & Meeting Handouts Encl
ML20197F7631997-08-14014 August 1997
Summary of 960429 Public Meeting in Wiscasset,Maine Re Licensee New small-break loss-of-coolant Analysis & Licensee Reanalysis of Potential Containment Pressures Under Postulated Accident Conditions
ML20140H5731997-04-0404 April 1997
Summary of 439th Meeting of ACRS on 970306-08 Re Release of AP600 Test Data from Rosa Test Facility,Rept Entitled, Recommendations to Improve Senior Mgt Meeting Process & Independent Safety Assessment of Myaps
ML20137L3531997-03-27027 March 1997
Summary of 970320 Meeting W/Util in Rockville,Md Re Outage Activities Identified in Attachment Four & Proposed TS Change 194, Reactor Coolant Flow Rate Requirements. W/List of Attendees & Viewgraphs
ML20134P0531997-02-20020 February 1997
Summary of 970212 Meeting W/Listed Attendees in Rockville,Md to Discuss Pending Mgt Svcs Agreement Between Licensee & Entergy Nuclear,Inc.Meeting Closed Due to Proprietary Nature of Info to Be Discussed
ML20129E6321996-10-0707 October 1996
Summary of 960730 Meeting W/Myap in Rockville,Md Re Lessons Learned Related to RELAP5YA.Transcript Encl
ML20127L7631993-01-21021 January 1993
Summary of 921028 Meeting to Review Licensee Proposed Fuel Pool Reracking
ML20127J6121993-01-15015 January 1993
Summary of 921217 Meeting W/Licensee to Discuss Fuel Pool Reracking
ML20198D6241992-05-12012 May 1992
Summary of 920507 Meeting W/Util in King of Prussia,Pa Re Current Status of Physical Security Program Being Implemented at Facility
ML20055E2491990-07-0505 July 1990
Summary of 900625 Meeting W/Util & C-E Re Control Element Assembly Failures & Corrective Actions.Major Topics Presented Listed,Including Visual Exam Results & Fuel Insp Activity & Results.List of Attendees & Briefing Matls Encl
ML20153C1861988-08-23023 August 1988
Summary of Operating Reactors Events Meeting 88-34 on 880823
ML20207F6541988-08-17017 August 1988
Summary of 880816 Operating Reactors Events Meeting 88-33 in Rockville,Md Re Briefing of Senior Managers from Nrr,Osp, AEOD & Regional Ofcs on Events Which Occurred Since Last Meeting on 880809.List of Attendees Encl
ML20154J8011988-05-16016 May 1988
Summary Rept of 880427 Meeting W/Util in King of Prussia,Pa Re Licensee Planning & Preparation for Upcoming Outage & Station Performance in Area of Radiological Controls
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
ML20214P6121987-05-27027 May 1987
Summary of Operating Reactors Events Meeting 87-14 on 870512 W/Nrr,Res,Aeod & Regional Ofcs Re Events Which Occurred Since 870507 Meeting.List of Attendees & Viewgraphs Encl
ML20205Q9121987-03-20020 March 1987
Summary of 870306 Meeting W/Util in Bethesda,Md Re Low Level Waste Mgt.List of Attendees,Viewgraphs & APTR-42, Maine Yankee Atomic Power Station In-Situ Decommissioning/Low Level Waste Mgt, Encl
ML20211B9491987-02-0909 February 1987
Summary of 870205 Meeting W/Util in Bethesda,Md Re RELAP5YA Computer Code & Use in Small Break LOCA Analysis Pertmi Action Plan Item II.K.3.30.List of Attendees & Presentation Matl Used by Util Encl
ML20212G4991987-01-12012 January 1987
Summary of 861216 Meeting W/Util & Intermountain Technologies,Inc in Bethesda,Md Re Large Break LOCA Analysis Axial Power Shape.List of Attendees & Presentation Outline on Steam Cooling Model Rev Encl
ML20207J7881987-01-0707 January 1987
Trip Rept of 861218-19 Visit to Framingham,Ma to Examine Plant Spent Fuel Pool Masonry Wall Failure Consequence Analysis.Conclusions Listed
ML20214P8971986-11-25025 November 1986
Summary of Operating Reactors Events Meeting 86-40 on 861117.List of Attendees,Events Discussed,Significant Events Data Sheet & Summary of Presented Events That Will Be Input to NRC Performance Indicator Program Encl
ML20213F0641986-11-10010 November 1986
Summary of Operating Reactors Events Meeting 86-36 on 861020.List of Attendees,Events Discussed,Significant Events Data Sheet,Summary of Scrams W/Complications & Status of Previous & New Assignments Encl
ML20207A7551986-11-0404 November 1986
Summary of 861022 Meeting W/Util in Bethesda,Md Re Selection of Axial Power Shape for Large Break LOCA Analysis.List of Attendees & Supporting Documentation Encl
ML20215N5521986-11-0404 November 1986
Summary of 860930 Second Peer Review Group Meeting in San Francisco,Ca Re Facility Seismic Design Margin Program
ML20210G8611986-09-22022 September 1986
Summary of 860909 Meeting W/Util in Bethesda,Md Re Util Large Break LOCA Analysis Axial Power Shape.List of Attendees & Viewgraphs Encl
ML20205E2901986-08-13013 August 1986
Summary of 860721-25 Meetings W/Util & Consultants Re Seismic Design Margin Program.Peer Review Group Meeting Scheduled for 860930.Attendee List,Agenda & Contractor Presentation Outline Encl
ML20198C6991986-05-19019 May 1986
Summary of 860507-08 Meetings W/Util & Consultants Re Seismic Design Margin Program Activities,Schedules & Manpower Requirements.Attendance List,Viewgraphs & Supporting Documentation Encl
ML20205J0421985-11-21021 November 1985
Summary of ACRS 307th Meeting on 851107-09 in Washington, DC Re Review of Application of Beaver Valley Power Station 2,EPA Stds for High Level Radwaste Repository & Investigation of Significant Incidents at Power Plants
ML20141E9501985-11-18018 November 1985
Summary of ACRS Subcommittee on Reactor Operations 851104 Meeting in Washington,Dc to Discuss Recent Plant Operating Experience.Fr Notice,Schedule of Discussion & Agenda 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
ML20128M0751985-05-21021 May 1985
Summary of 850508 Meeting W/Util in Bethesda,Md Re Testing of Offsite Power Supplies
ML20216H9751985-04-0303 April 1985
Summary of 850311 Meeting W/Util Re Alternative Approach to 10CFR50,App R,Section Iii.O Requirements.W/List of Attendees
ML20140C8561984-06-0404 June 1984
Summary of 840424 Meeting W/Utils & Eqe,Inc Re Update of Seismic Design Review Project
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
ML20148G8601976-11-15015 November 1976
Summary of 761103 Meeting W/Utils,Nus Co,C-E & Lowenstein, Newman,Reis & Axelrad Re Submission of Proposed Measures to Prevent Reactor Vessel Overpressurization in Operating C-E Facilities.Attendance List Encl
1999-09-20
[Table view]
Category:MEETING SUMMARIES-INTERNAL (NON-TRANSCRIPT)
MONTHYEARML20212D1631999-09-20020 September 1999
Summary of 990908 Meeting with Myap in Rockville,Md Re Plant License Termination Plan.List of Attendees & Licensee Handouts Encl
ML20212A3101999-09-14014 September 1999
Summary of 990823 Meeting with Util in Rockville,Md to Discuss License Termination Plan.List of Attendees Encl
ML20210G2711999-07-28028 July 1999
Summary of 990707 Meeting with Util in Rockville,Md to Discuss Licensee Termination Plan.List of Attendance & Handouts Encl
ML20210B7521999-07-21021 July 1999
Summary,For Docket 7200030,of 990707 Meeting with Myap,S&W & NAC Intl Re Util Plans to Store Spent Fuel Using NAC-UMS Dry Storage Sys.Attendance List,Meeting Handouts & Util Rulemaking Handout,Encl
ML20207G2401999-06-0707 June 1999
Summary of 990525 Meeting with Util in Rockville,Md to Discuss Maine Yankee Atomic Power Station License Termination
ML20196C3251998-11-23023 November 1998
Summary of 981109 Meeting with Util & SWEC Re Decommissioning Activities & Schedule at Maine Yankee Atomic Power Station.List of Attendees Enclosed
ML20236S9811998-07-22022 July 1998
Summary of 980710 Meeting W/Util in Rockville,Md Re Plant Backfit Appeal.Appeal Submitted Per NRC Determination Re Plant Emergency Preparedness Exemption
ML20249B8251998-06-17017 June 1998
Summary of 980609 Meeting W/Util in Rockville,Md to Discuss Sf Heatup Analysis That Util Performed in Support of Exemption Requests Submitted Re Emergency Preparedness & Financial Protection
ML20202F4691997-12-0101 December 1997
Summary of 971120 Meeting W/Util in Rockville,Md to Discuss Proposed Defueled TSs for Plant.List of Attendees & Handouts Used by Licensee Encl
ML20202G8591997-12-0101 December 1997
Summary of 971125 Meeting W/Employees of Myap in Rockville, Maryland Re Proposed Defueled Emergency Plan for Myap Station.List of Attendees Encl
ML20211P3801997-10-0808 October 1997
Summary of 970911 Meeting W/Myapco Re Options Available for Storage of Spent Fuel Currently at Site.Meeting Attendee List & Meeting Handouts Encl
ML20197F7631997-08-14014 August 1997
Summary of 960429 Public Meeting in Wiscasset,Maine Re Licensee New small-break loss-of-coolant Analysis & Licensee Reanalysis of Potential Containment Pressures Under Postulated Accident Conditions
ML20140H5731997-04-0404 April 1997
Summary of 439th Meeting of ACRS on 970306-08 Re Release of AP600 Test Data from Rosa Test Facility,Rept Entitled, Recommendations to Improve Senior Mgt Meeting Process & Independent Safety Assessment of Myaps
ML20137L3531997-03-27027 March 1997
Summary of 970320 Meeting W/Util in Rockville,Md Re Outage Activities Identified in Attachment Four & Proposed TS Change 194, Reactor Coolant Flow Rate Requirements. W/List of Attendees & Viewgraphs
ML20134P0531997-02-20020 February 1997
Summary of 970212 Meeting W/Listed Attendees in Rockville,Md to Discuss Pending Mgt Svcs Agreement Between Licensee & Entergy Nuclear,Inc.Meeting Closed Due to Proprietary Nature of Info to Be Discussed
ML20129E6321996-10-0707 October 1996
Summary of 960730 Meeting W/Myap in Rockville,Md Re Lessons Learned Related to RELAP5YA.Transcript Encl
ML20127L7631993-01-21021 January 1993
Summary of 921028 Meeting to Review Licensee Proposed Fuel Pool Reracking
ML20127J6121993-01-15015 January 1993
Summary of 921217 Meeting W/Licensee to Discuss Fuel Pool Reracking
ML20198D6241992-05-12012 May 1992
Summary of 920507 Meeting W/Util in King of Prussia,Pa Re Current Status of Physical Security Program Being Implemented at Facility
ML20055E2491990-07-0505 July 1990
Summary of 900625 Meeting W/Util & C-E Re Control Element Assembly Failures & Corrective Actions.Major Topics Presented Listed,Including Visual Exam Results & Fuel Insp Activity & Results.List of Attendees & Briefing Matls Encl
ML20153C1861988-08-23023 August 1988
Summary of Operating Reactors Events Meeting 88-34 on 880823
ML20207F6541988-08-17017 August 1988
Summary of 880816 Operating Reactors Events Meeting 88-33 in Rockville,Md Re Briefing of Senior Managers from Nrr,Osp, AEOD & Regional Ofcs on Events Which Occurred Since Last Meeting on 880809.List of Attendees Encl
ML20154J8011988-05-16016 May 1988
Summary Rept of 880427 Meeting W/Util in King of Prussia,Pa Re Licensee Planning & Preparation for Upcoming Outage & Station Performance in Area of Radiological Controls
ML20214P6121987-05-27027 May 1987
Summary of Operating Reactors Events Meeting 87-14 on 870512 W/Nrr,Res,Aeod & Regional Ofcs Re Events Which Occurred Since 870507 Meeting.List of Attendees & Viewgraphs Encl
ML20205Q9121987-03-20020 March 1987
Summary of 870306 Meeting W/Util in Bethesda,Md Re Low Level Waste Mgt.List of Attendees,Viewgraphs & APTR-42, Maine Yankee Atomic Power Station In-Situ Decommissioning/Low Level Waste Mgt, Encl
ML20211B9491987-02-0909 February 1987
Summary of 870205 Meeting W/Util in Bethesda,Md Re RELAP5YA Computer Code & Use in Small Break LOCA Analysis Pertmi Action Plan Item II.K.3.30.List of Attendees & Presentation Matl Used by Util Encl
ML20212G4991987-01-12012 January 1987
Summary of 861216 Meeting W/Util & Intermountain Technologies,Inc in Bethesda,Md Re Large Break LOCA Analysis Axial Power Shape.List of Attendees & Presentation Outline on Steam Cooling Model Rev Encl
ML20214P8971986-11-25025 November 1986
Summary of Operating Reactors Events Meeting 86-40 on 861117.List of Attendees,Events Discussed,Significant Events Data Sheet & Summary of Presented Events That Will Be Input to NRC Performance Indicator Program Encl
ML20213F0641986-11-10010 November 1986
Summary of Operating Reactors Events Meeting 86-36 on 861020.List of Attendees,Events Discussed,Significant Events Data Sheet,Summary of Scrams W/Complications & Status of Previous & New Assignments Encl
ML20207A7551986-11-0404 November 1986
Summary of 861022 Meeting W/Util in Bethesda,Md Re Selection of Axial Power Shape for Large Break LOCA Analysis.List of Attendees & Supporting Documentation Encl
ML20215N5521986-11-0404 November 1986
Summary of 860930 Second Peer Review Group Meeting in San Francisco,Ca Re Facility Seismic Design Margin Program
ML20210G8611986-09-22022 September 1986
Summary of 860909 Meeting W/Util in Bethesda,Md Re Util Large Break LOCA Analysis Axial Power Shape.List of Attendees & Viewgraphs Encl
ML20205E2901986-08-13013 August 1986
Summary of 860721-25 Meetings W/Util & Consultants Re Seismic Design Margin Program.Peer Review Group Meeting Scheduled for 860930.Attendee List,Agenda & Contractor Presentation Outline Encl
ML20198C6991986-05-19019 May 1986
Summary of 860507-08 Meetings W/Util & Consultants Re Seismic Design Margin Program Activities,Schedules & Manpower Requirements.Attendance List,Viewgraphs & Supporting Documentation Encl
ML20205J0421985-11-21021 November 1985
Summary of ACRS 307th Meeting on 851107-09 in Washington, DC Re Review of Application of Beaver Valley Power Station 2,EPA Stds for High Level Radwaste Repository & Investigation of Significant Incidents at Power Plants
ML20141E9501985-11-18018 November 1985
Summary of ACRS Subcommittee on Reactor Operations 851104 Meeting in Washington,Dc to Discuss Recent Plant Operating Experience.Fr Notice,Schedule of Discussion & Agenda 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
ML20128M0751985-05-21021 May 1985
Summary of 850508 Meeting W/Util in Bethesda,Md Re Testing of Offsite Power Supplies
ML20216H9751985-04-0303 April 1985
Summary of 850311 Meeting W/Util Re Alternative Approach to 10CFR50,App R,Section Iii.O Requirements.W/List of Attendees
ML20140C8561984-06-0404 June 1984
Summary of 840424 Meeting W/Utils & Eqe,Inc Re Update of Seismic Design Review Project
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
ML20148G8601976-11-15015 November 1976
Summary of 761103 Meeting W/Utils,Nus Co,C-E & Lowenstein, Newman,Reis & Axelrad Re Submission of Proposed Measures to Prevent Reactor Vessel Overpressurization in Operating C-E Facilities.Attendance List Encl
1999-09-20
[Table view] |
Text
. . . - - - _ _ _____ - - - . - _ - _ - - - - - - - _ - _ - - - _ _ - - - _ - - - _ _ _ - - - - - - _ _
o- N D(
JAN 121987 MEMORANDUM FOR: Ashok C. Thadani, Director PWR Project Directorate #8 Division of PWR Licensing-B FROM: Patrick M. Sears, Project Manager PWR Project Directorate #8 Division of PWR Licensing-B
SUBJECT:
SUMMARY
OF MEETING HELD ON DECEMBER 16, 1986 CONCERNING MAINE YANKEE LARGE BREAK LOCA ANALYSIS AXIAL POWER SHAPE The meeting was held in Bethesda, Maryland. Those who attended are listed in Enclosure 1.
Maine Yankee discussed the implementation of a revised steam cooling model to be used in Phase II of Cycle 10 analysis.
R. T. Jensen of Intermountain Technologies, Inc., presented a steam cooling model revision as outlined in Enclosure 2. Yankee Atomic Engineering personnel presented an outline of the use of that model.
It was agreed by the staff that a Safety Evaluation could be written concerning the proposed Phase I modification of the large Break ECCS Evaluation Model Modifications addressed in Maine Yankee submittals dated September 15, 1986 and November 10, 1986. This does include the steam cooling proposals for Phase II.
unsinal signee c3 Patrick M. Sears, Project Manager PWR Project Directorate #8 Division of PWR Licensing-B
Enclosures:
As stated cc w/ enclosures:
l See next page PBD 8 QN PBD68 PBD#8 P tzer PSears;cf AThadani 1 (/87 1/ N 87 1/0/87 8701200534 870112 PDR ADOCK 05000309 P PDR
'b MEETING SU M RY DISTRIBUTION PWR PROJECT DIRECTORATE #8 Docket File NRC PDR
, L PDR PBD#8 Rdg PKrentrfr OGV EJordan BGrimes ACRS-10 NRC Participants PSears RJones NLauben CThomas I
4 i
i
Mr. J. B. Randazza pineYankeeAtomicPowerCompany Maine Yankee Atomic Power Station cc:
Charles E. Monty, President Nr. P. L. Anderson, Project Manager Maine Yankee Atomic Power Company Yankee Atomic Electric Company 83 Edison Drive 1671 Worchester Road Augusta, Maine 04336 Framingham, Massachusetts 07101
/
Mr., Charles B. Brinkman Mr. G. D. Whittier Manager - Washington Nuclear Licensing Section Head Operations Maine Yankee Atomic Power Company Combustion Engineering, Inc. 63 Edison Drive 7910 Woodmont Avenue Augusta, Maine 04336 Bethesda, Maryland 20814 John A. Ritsher, Esquire Ropes & Gray 225 Franklin Street Boston, Massachusetts 02110 State Planning Officer Executive Department 189 State Street Augusta, Maine 04330 Mr. John H. Garrity, Plant Manager Maine Yankee Atomic Power Company
! P. O. Box 408 Wiscasset, Maine 04578 l
I Regional Administrator, Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, Pennsylvania 19406 First Selectman of Wiscasset Municipal Building U.S. Route 1 l Wiscasset, Maine 04578 Mr. Cornelius F. Holden Resident Inspector c/o U.S. Nuclear Regulatory Commission P. O. Box E l Wiscasset, Maine 04578 l
l
Z* Enclosure 1 LIST OF ATTENDEES MEETING HELD ON DECEMBER 16, 1986 NAME ,', AFFILIATION PHONE NUMBER Patrick Sears NRC/DPLB 301-492-8006 Ross T. Jerisen ITI (YAEC Consultant) 208-523-7255 Jamal Ghaus Yankee Atomic 617-872-8100 Stephen P. Schultz Yankee Atomic 617-872-8100 X2131 Peter L. Anderson Yankee Atomic 617-872-8100 G. D. Whittier Maine Yankee 207-623-3521 Robert C. Jones NRC/DPLB 301-492-8005 Norm Lauben NRC/DPLB 301-492-8997 Howard F. Jones, Jr. Maine Yankee 207-623-3521 Cecil Thomas NRC/0PLB 301-492-7974
- , , , - ,. - . , - . . . ~ -
,n- , , -- - - - - - - - - - - - - - - - --------n - - - --- -
/
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DMDHDDOWWDDU)DC9 TH@C3@[L@@D30 0 0C9%
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9
-0BJECTIVES
-ASSUMPTIONS
-NODEL DESCRIPTION
-RESULTS .
-SENSITIVITY STUDIES
-T00DEE2 RESULTS
-FURTHER JUSTIFICATION l
l
- -CONCLUSIONS l
l l
l l
l l
l
.o
, OBJECTIVES
- 1. REMOVE EXCESSIVE CONSERVATISM PRESENT IN EXISTING YAEC STEAM COOLING MODEL.
- 2. UTILIZE INFORMATION FROM FLECHT-SEASET IN DEVELOPING AND JUSTIFYING THE NEW MODEL.
- 3. SATISFY THE INTENT OF APPENDIX K BY CONSERVATIVELY COMPUTING THE EFFECT OF THE BLOCKAGE UPON THE CHANNEL FLOW AND HEAT TRANSFER.
- 4. ASSURE THAT THE STEAM COOLING MODEL IS ALWAYS CONSERVATIVE COMPARED TO THE FLECHT CORRELATION.
9
~ -
V
-COOLANT FLOW IS SATURATED STEAM
-COOLANT TEMPERATURE IS CONSTANT AT TSAT
-DOMINANT HEAT TRANSFER IS PER FLECHT CORRELATION
-EXISTING YAEC FLOW DIVERSION MODEL WILL BE UTILIZED
-CHANGE IN HEAT TRANSFER DUE TO FLOW DIVERSION WILL BE CALCULATED
-HEAT TRANSFER ENHANCEMENT DUE TO SINGLE PHASE TURBULENCE WILL BE CONSERVATIVELY CALCULATED
-HEAT TRANSFER ENHANCEMENT DUE TO DROPLET BREAKUP WILL BE NEGLECTED 1
McCEL DESCR0PTCCM
-CONSIPER! fig SINGLE PHASE STEAM FLOW
-A MODEL HAS BEEN DEVELOPED IN FLECHT SEASET FOR HEAT TRANSFER ENHANS MENT DUE BOUNDARYLAYER SEPARATION AND REATTACHMENT WITH THE MAXIMUM COEFICIENT OCCURING AT THE REATTACHMENT POINT
-FROM ABRUPT EXPANSION EXPERIMENTS, ZEMANICK AND DOUGALL FOUND NUMAX- 0.2 REDSEP '
-FROM FLECHT SEASET 161 ROD UNBLOCKED STEAM COOLING TESTS NU -0.0797 REDO '
s
-DIVIDING WMAX,0.2 REDSEP NUO 0.0797 REDO
-ASSUMING CONSTANT MASS FLOW WMAX
- 2.5 (Do/DSEP)2/3 Wo
-FLECHT SEASET DATA IS BETTER flT WITH A CONSTANT OF 1.88 RATHER THAN 2.5 l
-fCR THE YAEC MODEL, THE EFFECT OF FLOW DIVERSION MUST BE C0fiSERVITIVELY ACCOUNTED FOR. SiliCE WE KNOW G/GO, WE CAft WRITE l
WMAX
- CONS (G/G0 9/hDSEP/DoW l 50 WHERE_G
-lF THE DIAMETER USED IN THE MODEL IS DEFINED AS
- f. D = (4A/11 )1/2
/
TH MODEL CAN BE WRITEN AS WMAX
- CONS (G/Go)2/3(1.-BLK)l/3 WO WHERE BLK IS THE BLOCKAGE FRACTION.
-AS THE BOUNDARY LAYER REATTACHES AND THE FREESTPEAM TURBULENCE DECAYS, THE EllHANCEMENT DECAYS EXPONENTIALY AS WZSU0
- exp-C(Z-ZMAXII/D0 WMA>cNUo OR, NUz
- 1. + (NUMA>(NUo - 1.) exp-C(Z-2MA>lDO NUO C - 0.6 - 0 A5(DSEP/Do)
-TO GET HEAT TRANSFER COEFFICIENT Hz Z H0 NUz [D NUO 00 NU2
= hQtr51#2 - - - -
e
SUMMARY
OF EQUATE 0NS AMD ASSUMPTCOMS
= CONS (G/G O ) /3 (1.-BLK)1/3 NU O NU Z
= 1. + (NU MAX /NU n
- 1.) g-@-2MAXNO NU O C = 0.6 - 0.45(DSEP/Do)
. HZ NUz
_=
/(1. - BLK )1/2 H0 NU n l
-APPLICATION ASSUMPTIONS
-REATTACHMENT OCCURS AT RUPTURED NODE
-H RATIO = NU RATIO EXCEPT AT THE RUPTURED NODE
-G USED IN ENHANCEMENT EQUATION IS LOCAL VALUE l
-CONS = 1.1
-HZ/Hoi 1.0
.: a
/
20% BLOCKAGE CONS = 1.1 1.0000 +++,,,,. ..
0.9800 [c._+-+--+-+
0.9600 0.9400 NUZ/NUMAX 0.9200 0.9000 l 0.0000 0.8600
- 0.000 0.500 1.000 1.500 2.000 2.500 DISTANCE ADOVE BLOCKAGE, FEET l
.?b
, /
/--
i 20% BLOCKAGE CONS =l .1 1.0000 - y ,_,_,_,_,_,_,_,_,_,_,_, ,_, ,
0.9900 -
0.9800 -
0.9700
0.9500 -
i 0.9400 -
0.9300 0.000 0.500 1.000 1.500 2.000 2.500 DISTANCE ABOVE BLOCKAGE, FEET i
4 m
w -,rw.,, -sy ,w ny--,- ,ww,wy.wwr-www w w ,rw-, , - m--4 w -mw-mwwvwww-y-wgww.-my%--e,gw,---#,-r-m --
~
30% BLOCKAGE CONS =1.1 1.0000 - y +-+-+-+-+-+-+-+-+-+-+-+ +-4 0.9500 -
[
?
0.9000-NUZ/NUMAX 0.6500- -
l l 0.8000 -
l 0.7500
- l 0.000 0.500 1.000 1.500 2.000 2.500 l DISTANCE ABOVE BLOCKAGE. FEET l
l l
l
, e
- - - - - --,--,r +.--y.w ..,,e~, ----.w-.- f- .m- - - , , - ,,,----,.,..-.-.,o e , ---- . . , . - , - - , - - . , - - - - , , ~ , . - - - - - ...w, , . . .---,.%.w. ..+ --- -
9
.' a a'
/
/
30% BLOCKAGE CONS-1.I 1.0000 - e_e-e-+-+-+-+-+-+-+-+-e +-+
0.9800 -
0.9600 -
0.9400 -
HZ/Ht1AX 0.9200 -
0.9000 -
l l 0.8800 -
+
0.8600 0.000 0.500 1.000 1.500 2.000 2.500 DISTANCE ABOVE BLOCKAGE, FEET l
i l
(
.b
/
,. ~
60% BLOCKAGE CONS =1.1 1.0000 -
j_e-e-+--+-+--+--+-+-+-+-+-+ 0-+
0.9500 -
0.9000 --
0.6500 --
0.8000 --
NUZ/l!UMAX 0.7500 -
0.7000 +
0.6500 -
0.6000 -
e 0.5500 0.000 0.500 I.000 1.500 2.000 2.500 DISTANCE ABOVE BLOCKAGE, FEET l
I %
4
.Ib '
/
60% BLOCKAGE CONS-1.1 1.2000 "
1.1000
- 1.0000- y o -e-e-e-e-e-e-e-e-+-+-+-+ -e
, 0.9000 '-
HZ/Ht1AX l 0.8000 -
0.7000--
0.6000 -
0.5000 .
0.000 0.500 1.000 1.500 2.000 2.500 DISTANCE ABCVE BLOCKAGE. FEET t
,y 4- -- - -n , - - ,-- .,,-n--- ,,,-,--rr, - , .
-,,,w,----+,
" ~
T0@DEE2 RESULTS ELEVATION OLD MODEL FLECHT NEW MODEL 9.96 ,- 1639. 1639. 1639.
Id[21 2019. 1858. 1858.
10.51 1822. 1817. 1817.
11.04 1552. 1552. 1552.
NOTE: FLECHT AND NEW MODEL PCT'S OCCURED PRIOR TO STEAM COOLING PERIOD.
6 I
l i
MODOFDED T00DEE2 M@ DEL RESULTS 1
/
ELEVATION OLD MODEL FLECHT NEW MODEL 9.96 1921. 1921. 1921.
10.21 2291. 2017. 2029.
10.51 1955. 1946. 1947.
11.04 1620. 1619. 1619.
l
l FURT[MR MGBR JOIST 0F(CAT 0016
-FURTHER, SENSITIVITY STUDIES USING T00DEE2 ARE NEEDED TO ASSURE THA.T-THE N0 DEL IS CONSERVATIVE FOR ALL BLOCKAGES
-FURTHER COMPILATION OF RELATIVE EXPERIMENTAL DATA IS NEEDED
C@BCCLUSCMS
-FLECHT SEASET, FEBA, AND OTHER TESTS HAVE SHOWN BLOCKAGE TO ENH@C[ HEAT TRANSFER
-ENHANCEMb 4T IS DUE TO STEAM TURBULENCE AND DROPLET BREAKUP
-CONSIDERING ONLY STEAM TURBULENCE IS CONSERVATIVE AND CONSISTENT WITH APPENDIX K
-PROPOSED MODEL REMOVES EXCESS CONSERVATISM IN OLD MODEL
-PROPOSED MODEL IS CONSERVATELY ACCOUNTS FOR BLOCKAGE EFFECTS AND SATISFIES THE INTENT OF APPENDIX K i
- ,. .~,- - -- - -- - . - - -
,--