|
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Category:MEETING MINUTES & NOTES--CORRESPONDENCE
MONTHYEARML17313A3661998-05-0707 May 1998 Summary of 980408 Meeting W/Arizona Public Svc (APS) in Rockville,Maryland Re Future Activities Planned by APS for Acquiring Addl on-site Capabilities for Conducting Fuel Reload Analyses & Dry Cask Storage of Spent Fuel ML17312B7121997-10-0808 October 1997 Summary of 970916 Meeting W/Aps to Discuss Proposed TS Amend to Provide Method to Respond to Sustained, & Degraded Switchyard Voltage.List of Attendees & Handouts Encl ML17312B6991997-09-29029 September 1997 Summary of 970916 Meeting W/Aps at NRC Re Staff Revised Schedule for Review of Improved Std TS Submittal for Pvngs. List of Meeting Attendees Encl ML17312B3351997-03-25025 March 1997 Summary of 970220 Meeting W/Aps to Discuss Results of SG Tube Current Insp Particularly as They Relate to Issue of Appropriate Cycle Length for Plant,Unit 2 ML20137F2351997-03-24024 March 1997 Summary of 970207 Meeting W/Listed Attendees in Rockville,Md to Discuss Nuclear Energy Inst Concerns Re Graded Quality Assurance Activities W/Volunteer Plants ML17312B1921997-01-23023 January 1997 Summary of 961216 Meeting W/Aps in Rockville,Md to Discuss Improved Tech Spec Submitted on 961004.List of Attendees Encl ML17312B0371996-11-13013 November 1996 Summary of 9609018 Meeting W/Util in Rockville,Md Re Issues Concerning Degraded Grid Voltage Concerns & Grid Stability at Plant.List of Attendees & Licensee Handout Encl ML20140H5981996-11-11011 November 1996 Summary of 435th Meeting of ACRS on 961009-12 Re Capability of NRC SCDAP/RELAP5 Code to Predict Temps & Flows in SGs Under severe-accident Conditions ML20148B5761996-10-0404 October 1996 Summary of 434th Meeting of ACRS on 960912-13 Re Capability of SCAP/RELAP5 Code to Predict SG Temps During Severe Accidents ML17312A9501996-09-0909 September 1996 Summary of 960711 Meeting in Rockville,Md W/Aps to Discuss Double Sequencing of Safety Loads Under Degraded Grid Voltage Conditions.List of Attendees & Viewgraphs Encl ML17312A9141996-08-12012 August 1996 Summary of 960801 Predecisional Enforcement Conference W/ Arizona Public Svc Co in Arlington,Tx to Discuss Apparent Violations Identified in Insp Repts 50-528/96-10, 50-529/96-10 & 50-530/96-10.List of Attendees Encl ML17312A7551996-05-0909 May 1996 Summary of 960418 Meeting W/Licensees to Discuss Use of At&T Round Cell Batteries.Meeting Attendees Listed in Encl 1 ML17311B3071995-10-27027 October 1995 Trip Rept of 950906-07 Assessment of Plant Graded QA Program for Commercial Grade Item Dedication.Detail Discussion Encl ML17311A9741995-06-13013 June 1995 Summary of 950523 Meeting W/Util at Plant Re Graded QA Initiatives ML17311A7211995-03-15015 March 1995 Summary of 950209 Meeting W/Util to Discuss 125 Vdc Battery Testing & Operability Issues.Forwards non-proprietary APS-PVNGS Crdr 240348, Equipment Root Cause of Failure Analysis At&T Lineage 2000 Round Cells in Unit 2 ML17311A6331995-02-14014 February 1995 Summary of 950125-26 Meeting W/Util Re Plant Licensing Issues.Grid Disturbance Info & Root Cause Analysis Rept Encl ML16342C7511994-11-22022 November 1994 Summary of 941110 Meeting W/Utils Re Training & Operator Licensing Issues.List of Attendees,Meeting Agenda & Handouts Encl ML17311A3651994-10-19019 October 1994 Summary of 940822 Meeting W/Util Re SG ECT Results & Analyses at Plant.List of Attendees & Agenda Encl ML17311A2851994-09-20020 September 1994 Summary of 940815 Meeting W/Util in Arlington,Tx to Discuss Changes to Engineering & Maint Programs at Plant Which Resulted from Licensee Reengineering Efforts.List of Attendees Encl ML20029C7961994-04-0404 April 1994 Summary of Operating Reactors Events Meeting 94-11 on 940323 ML17310B0761994-02-25025 February 1994 Summary of 940225 Meeting W/Util Re Reactor Coolant Sys Hot Leg Temp Reduction.List of Attendees Encl & Viewgraphs Encl ML17310A8761993-12-29029 December 1993 Summary of 931109 Meeting W/Util to Discuss Results & Conclusions from Recently Completed Unit 1 Steam Generator Eddy Current Testing ML20058N7741993-12-0303 December 1993 Summary of Operating Reactors Events Meeting 93-45 on 931201 ML17310B1421993-12-0202 December 1993 Summary of 402nd ACRS Meeting on 931007-08 in Bethesda,Md Re EPRI Passive LWR Requirements Document,Proposed Resolution of GI-23, RCP Seal Failure, Severe Accident/Pra Issues for ABWR Design & SG Tube Rupture Event at Pvngs,Unit 2 IR 05000528/19930031993-11-30030 November 1993 Summary of 931019 Meeting W/Util Re Licensee Method of Calibr for Containment high-range Radiation Monitors,Per Deviation in Insp Rept 50-528/93-03.List of Attendees Encl. W/O Viewgraphs ML17310A7741993-11-0909 November 1993 Summary of 931006 Meeting W/Util & C-E Re Discussion on Statistical Treatment of Core Inlet Flow Uncertainties.List of Attendees & Viewgraphs Encl ML20057A5221993-07-28028 July 1993 Summary of Operating Reactors Events Meeting 93-27 on 930721 ML17310A4301993-07-0707 July 1993 Summary of 930630 Meeting W/Util Re Steam Generator Tube Rupture Root Cause Investigation & Tube Insp Results ML20056E2031993-06-15015 June 1993 Summary of Operating Reactors Events Meeting 93-20 on 930602 ML20035B4531993-03-18018 March 1993 Summary of Operator Reactors Events Briefing 93-10 on 930317.List of Attendees Encl ML20128P8491993-02-18018 February 1993 Summary of Operating Reactors Events Briefing 93-05 on 930210 ML17306B0781992-10-27027 October 1992 Notification of 921110 Meeting W/Util in Rockville,Md to Discuss Improvements in Fire Protection Program at Palo Verde Nuclear Generation Station W/Nrc Staff.Meeting Agenda Encl ML17306A4671992-02-11011 February 1992 Summary of 920205 Meeting W/Util Re 5 Yr Fuel Enhancement Program & Other Fuel Related Issues.W/Attendance List & Handout ML20217C5121991-07-0303 July 1991 Summary of Operating Reactors Events Meeting 91-12 on 910626 ML20058B7431990-10-19019 October 1990 Summary of 901010 Meeting W/Util & Consultants in Rockville, MD Re Licensee Plan to Pursue Reload Technology.List of Attendees Also Encl ML18057A3271990-07-0909 July 1990 Summary of 900625 Meeting w/C-E Regulatory Response Group in Rockville,Md Re Control Element Assembly Failure Mechanisms. List of Attendees & C-E Presentation Handout Encl ML20127J2961990-04-0606 April 1990 Trip Rept of Commissioner Curtiss 900201 Site Visit.Facility Has Undergone Radical Change in Mgt Personnel & Experiencing Problems W/High Attrition of Licensed Operators ML20247R0161989-09-21021 September 1989 Summary of Operating Reactors Events Meeting 89-34 on 890920 to Brief Senior Managers & Regional Offices on Selected Events That Occured Since Last Meeting ML13322A3371989-08-15015 August 1989 Summary of 890712 Meeting w/C-E Owners Group in Bethesda,Md Re Diverse Emergency Feedwater Actuation Sys Design Features to Be Installed Per 10CFR50.62 (ATWS Rule) ML20245G5421989-08-0303 August 1989 Summary of Operating Reactors Events Meeting 89-28 on 890802.List of Attendees,Events Discussed & Significant Elements of Events & Summaries of Reactor Scrams for Wks Ending 890723 & 30 Encl ML20245D3881989-04-21021 April 1989 Summary of 890413 Meeting W/Control Components,Inc in Rockville,Md Re Operation of Atmospheric Dump Valves.Agenda, Slides Used During Meeting for Valve Description & Worst Case Model Assumptions Encl ML20248K3761989-04-10010 April 1989 Summary of Operating Reactors Events Meeting 89-014 on 890405.List of Attendees,Events Discussed & Significant Elements of Events & Summary of Reactor Scrams for Wk Ending 890402 Encl ML20247F1991989-03-24024 March 1989 Summary of Operating Reactors Events Meeting 89-12 on 890322.List of Attendees,Events Discussed & Significant Elements,Summary of Reactor Scrams & Comparison of Weekly Statistics W/Industry Averages for Wk Ending 890319 Encl ML20247A8971989-03-16016 March 1989 Summary of Operating Reactors Events Meeting 89-11 on 890315.List of Attendees,Events Discussed & Significant Elements of Events & Four Events Identified for Input to NRC Performance Indicator Program & Summary of Scrams Encl ML20246N9201989-03-16016 March 1989 Summary of Operating Reactors Events Meeting 89-010 on 890308.List of Attendees,Significant Events Identified for Input to NRC Performance Indicator Program & Summary of Reactor Scrams for Wk Ending 890305 Encl ML20207G3861988-08-12012 August 1988 Summary of 880803 Meeting W/Util in Rockville,Md Re Facility Auxiliary Transformer Fire & Reactor Trip Event Initiated by Combination of Cracked Insulating Matl & Dirt Accumulation.Briefing Slides Encl ML20151K6901988-07-18018 July 1988 Summary of Operating Reactors Events Meeting 88-28 on 880712.Viewgraphs & List of Attendees Encl ML18053A4611988-07-15015 July 1988 Summary of 880708 Meeting w/C-E Owmers Group Re Generic Ltr 87-12, Loss of RHR While RCS Partially Filled ML20196B6471988-06-17017 June 1988 Summary of 880531 Meeting W/Licensee in Rockville,Md Re Auxiliary Feedwater Pump Degradation Events.Viewgraphs Encl ML20154M8471988-05-17017 May 1988 Summary of 880414 Meeting W/Util & BNL in Rockville,Md Re Monitoring Program for Reactor Coolant Pump Shafts.List of Attendees & Related Documents Encl 1998-05-07
[Table view] Category:MEETING SUMMARIES-INTERNAL (NON-TRANSCRIPT)
MONTHYEARML17313A3661998-05-0707 May 1998 Summary of 980408 Meeting W/Arizona Public Svc (APS) in Rockville,Maryland Re Future Activities Planned by APS for Acquiring Addl on-site Capabilities for Conducting Fuel Reload Analyses & Dry Cask Storage of Spent Fuel ML17312B7121997-10-0808 October 1997 Summary of 970916 Meeting W/Aps to Discuss Proposed TS Amend to Provide Method to Respond to Sustained, & Degraded Switchyard Voltage.List of Attendees & Handouts Encl ML17312B6991997-09-29029 September 1997 Summary of 970916 Meeting W/Aps at NRC Re Staff Revised Schedule for Review of Improved Std TS Submittal for Pvngs. List of Meeting Attendees Encl ML17312B3351997-03-25025 March 1997 Summary of 970220 Meeting W/Aps to Discuss Results of SG Tube Current Insp Particularly as They Relate to Issue of Appropriate Cycle Length for Plant,Unit 2 ML20137F2351997-03-24024 March 1997 Summary of 970207 Meeting W/Listed Attendees in Rockville,Md to Discuss Nuclear Energy Inst Concerns Re Graded Quality Assurance Activities W/Volunteer Plants ML17312B1921997-01-23023 January 1997 Summary of 961216 Meeting W/Aps in Rockville,Md to Discuss Improved Tech Spec Submitted on 961004.List of Attendees Encl ML17312B0371996-11-13013 November 1996 Summary of 9609018 Meeting W/Util in Rockville,Md Re Issues Concerning Degraded Grid Voltage Concerns & Grid Stability at Plant.List of Attendees & Licensee Handout Encl ML20140H5981996-11-11011 November 1996 Summary of 435th Meeting of ACRS on 961009-12 Re Capability of NRC SCDAP/RELAP5 Code to Predict Temps & Flows in SGs Under severe-accident Conditions ML20148B5761996-10-0404 October 1996 Summary of 434th Meeting of ACRS on 960912-13 Re Capability of SCAP/RELAP5 Code to Predict SG Temps During Severe Accidents ML17312A9501996-09-0909 September 1996 Summary of 960711 Meeting in Rockville,Md W/Aps to Discuss Double Sequencing of Safety Loads Under Degraded Grid Voltage Conditions.List of Attendees & Viewgraphs Encl ML17312A9141996-08-12012 August 1996 Summary of 960801 Predecisional Enforcement Conference W/ Arizona Public Svc Co in Arlington,Tx to Discuss Apparent Violations Identified in Insp Repts 50-528/96-10, 50-529/96-10 & 50-530/96-10.List of Attendees Encl ML17312A7551996-05-0909 May 1996 Summary of 960418 Meeting W/Licensees to Discuss Use of At&T Round Cell Batteries.Meeting Attendees Listed in Encl 1 ML17311A9741995-06-13013 June 1995 Summary of 950523 Meeting W/Util at Plant Re Graded QA Initiatives ML17311A7211995-03-15015 March 1995 Summary of 950209 Meeting W/Util to Discuss 125 Vdc Battery Testing & Operability Issues.Forwards non-proprietary APS-PVNGS Crdr 240348, Equipment Root Cause of Failure Analysis At&T Lineage 2000 Round Cells in Unit 2 ML17311A6331995-02-14014 February 1995 Summary of 950125-26 Meeting W/Util Re Plant Licensing Issues.Grid Disturbance Info & Root Cause Analysis Rept Encl ML16342C7511994-11-22022 November 1994 Summary of 941110 Meeting W/Utils Re Training & Operator Licensing Issues.List of Attendees,Meeting Agenda & Handouts Encl ML17311A3651994-10-19019 October 1994 Summary of 940822 Meeting W/Util Re SG ECT Results & Analyses at Plant.List of Attendees & Agenda Encl ML17311A2851994-09-20020 September 1994 Summary of 940815 Meeting W/Util in Arlington,Tx to Discuss Changes to Engineering & Maint Programs at Plant Which Resulted from Licensee Reengineering Efforts.List of Attendees Encl ML20029C7961994-04-0404 April 1994 Summary of Operating Reactors Events Meeting 94-11 on 940323 ML17310B0761994-02-25025 February 1994 Summary of 940225 Meeting W/Util Re Reactor Coolant Sys Hot Leg Temp Reduction.List of Attendees Encl & Viewgraphs Encl ML17310A8761993-12-29029 December 1993 Summary of 931109 Meeting W/Util to Discuss Results & Conclusions from Recently Completed Unit 1 Steam Generator Eddy Current Testing ML20058N7741993-12-0303 December 1993 Summary of Operating Reactors Events Meeting 93-45 on 931201 ML17310B1421993-12-0202 December 1993 Summary of 402nd ACRS Meeting on 931007-08 in Bethesda,Md Re EPRI Passive LWR Requirements Document,Proposed Resolution of GI-23, RCP Seal Failure, Severe Accident/Pra Issues for ABWR Design & SG Tube Rupture Event at Pvngs,Unit 2 IR 05000528/19930031993-11-30030 November 1993 Summary of 931019 Meeting W/Util Re Licensee Method of Calibr for Containment high-range Radiation Monitors,Per Deviation in Insp Rept 50-528/93-03.List of Attendees Encl. W/O Viewgraphs ML17310A7741993-11-0909 November 1993 Summary of 931006 Meeting W/Util & C-E Re Discussion on Statistical Treatment of Core Inlet Flow Uncertainties.List of Attendees & Viewgraphs Encl ML20057A5221993-07-28028 July 1993 Summary of Operating Reactors Events Meeting 93-27 on 930721 ML17310A4301993-07-0707 July 1993 Summary of 930630 Meeting W/Util Re Steam Generator Tube Rupture Root Cause Investigation & Tube Insp Results ML20056E2031993-06-15015 June 1993 Summary of Operating Reactors Events Meeting 93-20 on 930602 ML20035B4531993-03-18018 March 1993 Summary of Operator Reactors Events Briefing 93-10 on 930317.List of Attendees Encl ML20128P8491993-02-18018 February 1993 Summary of Operating Reactors Events Briefing 93-05 on 930210 ML17306B0781992-10-27027 October 1992 Notification of 921110 Meeting W/Util in Rockville,Md to Discuss Improvements in Fire Protection Program at Palo Verde Nuclear Generation Station W/Nrc Staff.Meeting Agenda Encl ML17306A4671992-02-11011 February 1992 Summary of 920205 Meeting W/Util Re 5 Yr Fuel Enhancement Program & Other Fuel Related Issues.W/Attendance List & Handout ML20217C5121991-07-0303 July 1991 Summary of Operating Reactors Events Meeting 91-12 on 910626 ML20058B7431990-10-19019 October 1990 Summary of 901010 Meeting W/Util & Consultants in Rockville, MD Re Licensee Plan to Pursue Reload Technology.List of Attendees Also Encl ML18057A3271990-07-0909 July 1990 Summary of 900625 Meeting w/C-E Regulatory Response Group in Rockville,Md Re Control Element Assembly Failure Mechanisms. List of Attendees & C-E Presentation Handout Encl ML20247R0161989-09-21021 September 1989 Summary of Operating Reactors Events Meeting 89-34 on 890920 to Brief Senior Managers & Regional Offices on Selected Events That Occured Since Last Meeting ML13322A3371989-08-15015 August 1989 Summary of 890712 Meeting w/C-E Owners Group in Bethesda,Md Re Diverse Emergency Feedwater Actuation Sys Design Features to Be Installed Per 10CFR50.62 (ATWS Rule) ML20245G5421989-08-0303 August 1989 Summary of Operating Reactors Events Meeting 89-28 on 890802.List of Attendees,Events Discussed & Significant Elements of Events & Summaries of Reactor Scrams for Wks Ending 890723 & 30 Encl ML20245D3881989-04-21021 April 1989 Summary of 890413 Meeting W/Control Components,Inc in Rockville,Md Re Operation of Atmospheric Dump Valves.Agenda, Slides Used During Meeting for Valve Description & Worst Case Model Assumptions Encl ML20248K3761989-04-10010 April 1989 Summary of Operating Reactors Events Meeting 89-014 on 890405.List of Attendees,Events Discussed & Significant Elements of Events & Summary of Reactor Scrams for Wk Ending 890402 Encl ML20247F1991989-03-24024 March 1989 Summary of Operating Reactors Events Meeting 89-12 on 890322.List of Attendees,Events Discussed & Significant Elements,Summary of Reactor Scrams & Comparison of Weekly Statistics W/Industry Averages for Wk Ending 890319 Encl ML20247A8971989-03-16016 March 1989 Summary of Operating Reactors Events Meeting 89-11 on 890315.List of Attendees,Events Discussed & Significant Elements of Events & Four Events Identified for Input to NRC Performance Indicator Program & Summary of Scrams Encl ML20246N9201989-03-16016 March 1989 Summary of Operating Reactors Events Meeting 89-010 on 890308.List of Attendees,Significant Events Identified for Input to NRC Performance Indicator Program & Summary of Reactor Scrams for Wk Ending 890305 Encl ML20207G3861988-08-12012 August 1988 Summary of 880803 Meeting W/Util in Rockville,Md Re Facility Auxiliary Transformer Fire & Reactor Trip Event Initiated by Combination of Cracked Insulating Matl & Dirt Accumulation.Briefing Slides Encl ML20151K6901988-07-18018 July 1988 Summary of Operating Reactors Events Meeting 88-28 on 880712.Viewgraphs & List of Attendees Encl ML18053A4611988-07-15015 July 1988 Summary of 880708 Meeting w/C-E Owmers Group Re Generic Ltr 87-12, Loss of RHR While RCS Partially Filled ML20196B6471988-06-17017 June 1988 Summary of 880531 Meeting W/Licensee in Rockville,Md Re Auxiliary Feedwater Pump Degradation Events.Viewgraphs Encl ML20154M8471988-05-17017 May 1988 Summary of 880414 Meeting W/Util & BNL in Rockville,Md Re Monitoring Program for Reactor Coolant Pump Shafts.List of Attendees & Related Documents Encl ML20236W3951987-11-25025 November 1987 Summary of 870909 Meeting W/Util in Bethesda,Md Re Proposed Changes to Organizational Structure for Plant Submitted by & Selected Issues Listed on Meeting Agenda.List of Attendees,Agenda & Licensee Viewgraphs Encl ML20237G3891987-08-27027 August 1987 Summary of Operating Reactors Events Meeting 87-25 on 870804 Re Events That Occurred Since 870728 Meeting.List of Attendees,Viewgraphs & Summary of Reactor Scrams Encl 1998-05-07
[Table view] |
Text
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UNITED STATES g( l',;s NUCLEAR REGULATORY COMMISSION y
WASHINGTON, D. C. 20555 2
%,.*...+/
OCT 6 1986 Docket Nos.:
50-528, 50-529 and 50-530 LICENSEE:
Arizona Public Service Company FACILITY:
Palo Verde, Units 1, 2 and 3
SUBJECT:
SUMMARY
OF MEETING REGARDING ADEQUACY OF MASONRY WALLS A meeting was held on August 20, 1986 in Bethesda, Maryland with representatives of the licensee and the staff to discuss the licensee's June 19, 1986 submittal regarding the adequacy of masonry walls at Palo Verde, Units 1, 2 and 3.
The attendees for the meeting are listed on Enclosure 1 and the meeting is summarized as follows:
Summary The licensee made a presentation in support of its June 19, 1986 submittal. The viewgraphs used during the presentation are included as Enclosure 2.
Since the viewgraphs contained additional clarifying information for the June 19, 1986 submittal, the licensee indicated that the staff's review should consider both packages.
Following the presentation, the staff provided the following comments based on its review to date of the June 1986 submittal and its understanding of the material presented at the meeting.
(1) For one of the two groups of mascnry walls in question, i.e., the walls at elavation 100 feet, the staff will be able to conclude that the information presented by the licensee demonstrates that the walls, as constructed, are adequate to meet NRC seismic requirements.
(2) For the walls at elevation 74 feet, the staff cannot find that the licensee's submittal demonstrates that the as-built walls meet accepted industry standards and NRC requirements.
(3)
In addition, the staff stated the following with regard to the licensee's methodology; (a) the assumption of using a 3-stage moment of inertia for estimating wall stiffness is not supported by test data, and (b) the sensitivity of stress change in response to wall frequency shift has not been considered.
The staff stated that it will complete its review of the masonry walls submittal and the results of the evaluation will be provided to the licensee.
8610140008 861006 PDR ADOCK 05000528 P
- PDR, J
O.
In response to the licensee's request, the staff agreed to schedule a follow-up meeting to permit the licensee to provide any further information relating to masonry walls. The licensee informed the staff that in addition to its evaluations of the masonry walls, it has been considering ways of strengthening the walls as an alternative to resolving the issue. However, no decisions have been made regarding a final resolution..
45/
E. A. Licitra, Project Manager PWR Project Directorate No. 7 Division of PWR Licensing-B
Enclosures:
1.,
Meeting Attendees 2.
Viewgraphs cc: See next page l
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PD7 EAlicitra/yt hton 10/[/86 1 6/86
Mr. E. E. Van Brunt, Jr.
Arizona Nuclear Power Project Palo Verde cc:
Arthur C. Gehr, Esq.
Kenneth Berlin, Esq.
Snell & Wilmer Winston & Strawn 3100 Valley Center Suite 500 Phoenix, Arizona 85073 2550 M Street, NW Washington, DC 20037 Mr. James M. Flenner, Chief Counsel Arizona Corporation Commission Ms. Lynne Bernabei 1200 West Washington Government Accountability Project Phoenix, Arizona 85007 of the Institute for Policy Studies 1901 Que Street, NW Charles R. Kocher, Esq. Assistant Washington, DC 20009 Council James A. Boeletto, Esq.
Southern California Edison Company Ms. Jill Morrison P. O. Box 800 522 E. Colgate Rosemead, California 91770 Tempi, Arizona 85238 Mr. Mark Ginsberg Mr. Charles B. Brinkman, Manager Energy Director Washington Nuclear Operations Office of Economic Planning Combustion Engineering, Inc.
and Development 7910 Woodmont Avenue Suite 1310 1700 West Washington - 5th Floor Bethesda, Maryland 20814 Phoenix, Arizona 8E007 Mr. Wayne Shirley-Mr. Ron Rayner Assistant Attorney General P. O. Box 1509 Bataan Memorial Building Goodyear, AZ 85338 Santa Fe, New Mexico 87503 Mr. Roy Zimmerman U.S. Nuclear Regulatory Commission P. O. Box 239 Arlington, Arizona 85322 Ms. Patricia Lee Hourihan 6413 S. 26th Street Phoenix, Arizona 85040 Regional Administrator, Region V U. S. Nuclear Fegulatory Commission 1450 Maria Lane Suite 210 Walnut Creek, California 94596
s OCT 6 1986 MEETING
SUMMARY
DISTRIBUTION t No(s): 50-528/529 @
Local PDR PBD-7 Reading JPartlow BGrimes ACRS(10)
EJordan Attorney, OELD GWKnighton E. A. Licitra Project Manager JLee NRC PARTICIPANTS E. A. Licitra J. Ma P. T. Kuo D. Crutchfield L. B. Marsh M. J. Davis H. Rood i
l bec: Applicant & Service List l
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Attendees for Palo Verde Masonry Walls Meeting August 20, 1986 Name Affiliation Manny Licitra
~
NRC/NRR/PBD7 John Ma NRC/NRR/EB Ahmad Hamid Drexel University Stephen Triolo Franklin Research Center Bill Quinn Manager of Licensing /ANPP Orhan Gurbuz Bechtel Ken Schechter Bechtel/ Civil Engr. Gr. Superv.
Steven Shapiro Bechtel/Nuc./Lic. Supr.
Lucien Hersh Bechtel/ Chief Civil /Struc. Engr.
Wm. Bingham Bechtel/Proj. Engr. Mgr.
P. T. Kuo NRC/NRR/PWR-B/EB Dennis Crutchfield NRC/NRR/PWR-B L. B. Marsh NRC/NRR/PWR-B/EB Michael J. Davis NRC/NRR/PBD7 Harry Rood NRC/NRR/PBD7 R. M. Butler Director Technical Services - ANPP l
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AususT 20, 1986 AGENDA I.
CONCERN II.
DESCRIPTION OF EVALUATION III.
JUSTIFICATION OF ASSUMPTIONS IV.
RESULTS V.
CONFIRMATORY ANALYSIS VI.
MAR 0 INS OF SAFETY VII.
CONCLUSIONS VIII.
RESPONSE TO NRC QUESTIONS I
6 4
0 4
PRESENTATION ON MASONRY WALLS FOR THE PALO VERDE NUCLEAR GENERATING STATION UNITS 1, 2. AND 3 AUGUST 20 1986 J
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AUGUST 20, 1986 II.
DESCRIPTION OF EVALUATION (1)
A.
TIME-HISTORY (T-H) ANALYSIS ASSUMPTIONS:
- COUPLED ANALYSIS WITH S0IL STRUCTURE INTERACTION (SSI)
- SINGLE DIRECTION TIME-HISTORY
- STRIP IDEALIZATION OF WALL B.
REALISTIC MATERIAL PROPERTIES AND METHODOLOGY
- WALL MODULUS OF ELASTICITY FOR STIFFNESS
- AVERAGE REBAR LOCATION ("d")
- GROUT STRENGTH BASED ON TEST
- 3-STAGE MOMENT OF INTERTIA - UNCRACKED PARTIALLY CRACKED, AND FULLY CRACKED i
(1)
JUNE 19, 1986-SUBMITTAL i
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AUGUST 20, 1986 III.
JUSTIFICATION OF ASSUMPTIONS A.
TIME-HISTORY ANALYSIS
- COUPLED ANALYSIS WITH SSI PER FSAR PER NRC APPROVED BC-TOP-4A ACCEPTED INDUSTRY PRACTICE
- SINGLE TIME-HISTORY RECORD ENVELOPES RG-1.60 SPECTRA PER NRC APPROVED BC-TOP-4A VALID FOR LINEAR-ELASTIC ANALYSIS
- SINGLE DIRECTION TIME-HISTORY (REALISTIC APPLICATION)
TORSIONAL EFFECTS ARE MINIMAL OUT-0F-PLANE (FLEXURAL) RESPONSE DOMINATES
- STRIP IDEALIZATION OF WALL ONE WAY ACTION - CONSERVATIVE APPLICATION RUNNING BOND CONFIGURATION ENSURES UNIFORM RESPONSE PENETRATIONS AND OPENINGS ARE LOCALLY REINFORCED
($)
AUGUST 20, 1986 III.
JUSTIFICATION OF ASSUMPTIONS (CONTINUED)
B.
REALISTIC MATERIAL PROPERTIES AND METHODOLOGY
- WALL MODULUS OF ELASTICITY (Ew)
- Ew - 1.5 x 106 2.0 x 106 BASED ON CODE MINIMUM AND REALISTIC EXPECTED VALUES OF f'm
- AVERAGE REBAR LOCATION ("d")
- WALL ACTS AS A CONTINUUM
- NRC CONCURRED
- GROUT COMPRESSIVE STRENGTH USED LESS THAN TEST DATA (2300 PSI VERSUS 2600+ PSI)
- 3-STAGE M0 MENT OF INERTIA - BASED ON SOUND ENGINEERING PRINCIPLES
- FULLY GROUTED CELLS AT PVNGS
- THEORY OF ELASTICITY (SRP 3.8.4 APPENDIX A) 1)
PLANE SECTIONS REMAIN PLANE 2)
SECTIONS REMAIN UNCRACKED UNTIL (fc).
IS EXCEEDED 3)
SECTION REMAINS PARTIALLY CRACKED UNTIL (9, IS EXCEEDED
- REFINED GRID SIZE TO INCREASE ACCURACY OF ANALYSIS
- SMALL BLOCK HEIGHT LIMITS STRESS CONCENTRATION
- WALL MODELING - VERIFIED BY INSPECTION
- PINNED-PINNED END CONDITION
- MASS INCLUDES ATTACHMENTS
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AususT 20, 1986 PRELIMINARY IV.
RESULTS TIME-HISTORY ANALYSES FREQUENCIES AND M0MENTS - ELEV. 74 ANALYSIS SSE C0.2G)
GBE CO.1G)
PARAMETERS FINAL MA FINA_
MA FREQUENCY FT-K/FT FREQUENCY FT-K/FT Ew-1.5x106
- 4. 9 2.7(1) 6.8 1.8(1)
E's-0.67Es Ew=1.5x106 N/A(2)
N/A(2) 6.8 1.7(1)
E's=1.0Es Ew-1.5x106 5.5 2.9 6.8 1.6(1)
E's=1.5Es Ew=2.0x106 6.3 2.9 7.8 2.0(1)
E's-1.0Es (1)
REPORTED IN JUNE 19, 1986 SUBMITTAL (2)
DATA NOT AVAILABLE
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AUGUST 20, 1986
- PRELIMINARY IV.
RESULTS CONTINUED TIME-HISTORY ANALYSES MAXIMUM STRESSES (PSI) - ELEV. 74 ITEM SSE C0.2G)
OBE f0.iG) i CALCULATED (1)
ALLOWABLE CALCULATED ALLOWABLE MASONRY 420 833 290(2) 333 REBAR-13500 48000 9130(2) 24000 BOND-118 180 80(2) 120 (i)
CALCULATED STRESSES BASED ON UPDATED MAXIMUM M0 MENT (2)
REPORTED IN JUNE 19, 1986 SUBMITTAL I
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(TIME HISTORY ANALYSIS)
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El. 140 P
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@ 0.2g SSE CONTROL BUILDING ELEVATION VIEW 4
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AUGUST 20, 1986 V.
CONFIRMATORY ANALYSIS A.
PURPOSE
- SUBSTANTIATE T-H ANALYSIS
- ADDRESS " DIP" IN T-H ANALYSIS
- ESTABLISH UPPER B0UNDS B.
METHODOLOGY
- ENVELOPED SPECTRA / PEAK BROADENED SPECTRA
e
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i AVERAGE BETWEEN ELEVATIONS 74 &
100 COMPARISON OF PUBLISHED AND ENVELOPED WALL SPECIFIC SPECTRA 7% DAMPING g
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AususT 20, 1986 PRELIMINARY V.
CONFIRMATORY ANALYSIS (CONTINUED)
C.
RESULTS RSA FREQUENCIES AND M0MENTS - ELEV. 74 PARAMETERS SSE (0.2s)
OBE (0.1G)
TYPE OF
_EW(PSI)
SPECTRA FRE0.
MA FRE0.
MA
- 1. 5x iO6 ENVELOPED 5.4 3.6
- 5. 6 2.8
- 2. 0x iO6 ENVELOPED 6.2
- 3. 5 6.7 2.3 15%
1.5x106 BROADENED
- 5. 4 4.5 6.8
- 2. 0 15%
2.0x106 BROADENED
- 6. 2 3.5
- 7. 8 2.0 2.0x 106 ENVELOPED (1) 6.1 3.5 6.1
- 2. 3 RSA MAXIMUM STRESSES (PSI) - ELEV. 74 ITEM SSE C0.2s) 03E (0.is)
CALCULATED ALLOWABLE CALCULATE )
ALLOWABLE MASONRY 650 833 400 333 REBAR 21.000 48.000 12.800 24.000 BOND 180 180 110 120 (1)
BASED ON GROUT MOMENT OF INERTIA ONLY l
.AususT 20, 1986 V.
CONFIRMATORY ANALYSIS (CONTINUED 1 D.
CONCLUSIONS
- RSARESULTSMORECONSERVATIVETHANT-HANAL'7,ISRESULTS
- RSA ELIMINATES T-H " DIP"
- RSA CONFIRMS T-H ANALYSIS
- ALL SSE STRESSES ARE WITHIN PRESCRIBE 0 ALLOWABLES
- OBE BOND AND REBAR STRESSES ARE WITHIN PRESCRIBED-ALLOWABLES
- OBE MASONRY STRESS EXCEEDS THE REDUCED ALLOWABLES BY ONLY 20%
- WALLS ARE ADEQUATE AS-BUILT
. - ~
~
32[ MARG /N O F 8AFETY P/C TOM /A L REPREN7A' T/ON OF MARG /NS OF SAFETY FOR BOND STRESS El EV 74 ' O, SSE = O 2g
-UL T/ MATE
$83 ACZ-3/8. G S
/?EdlIB7'/C AUOWABL5 300 ACI B/8-/ 7-fg MAlial/l.
/N
>BE5/6#
i MAR 6/Al ERESCR/8ED
.0 F All0WABLs l SAFETY 180 MI
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8ACADENED ~:-
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MARG lH srscTRA
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ANALYSI6 fo,, $m, 2 6.~l60) l 0TNGR
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CON. SERVAT /sM -
NOTE' 0/5 E /5 O A/D 6 7 M'ESS&5 ARENo7' PRG6ENTED S/NCE TNGY,4RS L555 cR/7~/CA/
i
AUGUST 20, 1986 VII.
CONCLUSIONS T-H ANALYSIS IS REALISTIC AND COMPLIES WITH SRP 3.8.4, APPENDIX A
- ESTABLISHED PRINCIPLES OF ENGINEERING MECHANICS
- SOUND ENGINEERING PRACTICES
- PROPER CONSIDERATION TO CRACKING 0F SECTIONS AND BOUNDARY CONDITIONS
- RSA CONFIRMS MARGIN OF SAFETY WALLS AS CONSTRUCTED HAVE ADEQUATE MARGINS OF SAFETY FOR SSE AND OBE i
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