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Category:MEETING MINUTES & NOTES--CORRESPONDENCE
MONTHYEARML20129J5741996-11-0505 November 1996
Trip Rept of 961001-03 Visit to Omega Point Labs in San Antonio,Tx to Witness Three Fire Endurance Tests Conducted for PG&E
ML20245F9261989-08-0707 August 1989
Summary of 890613-15 Meetings W/Util in San Francisco,Ca Re PRA long-term Seismic Program.List of Attendees & Agenda Encl
ML20247K0901989-05-23023 May 1989
Summary of 890517 Meeting W/Inpo Re Similarities & Differences Between Performance Indicator Programs.Detailed Discussion Encl
ML20247K1011989-05-16016 May 1989
Summary of 890517 Meeting W/Inpo in Bethesda,Md Re Similarities & Differences Between INPO & NRC Performance Indicators
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
ML20205H7521988-10-18018 October 1988
Summary of Operating Reactors Events Meeting 88-41 on 881018.No Significant Events Identified for Input to NRC Performance Indicator Program
ML20151D3481988-04-0707 April 1988
Summary of ACRS Subcommittee on Diablo Canyon Meeting on 880223-24 in Burlingame,Ca Re Review of Diablo Canyon Long Term Seismic Program
ML20148H6621988-01-15015 January 1988
Summary of Operating Reactors Events Meeting 88-02 on 880112 Re Events Which Occurred Since Last Meeting on 880105.List of Attendees,Significant Elements of Events & Tabulation of long-term Followup Assignments to Be Completed Encl
ML20148H6031987-12-15015 December 1987
Summary of ACRS DHR Sys Subcommittee 871117 Meeting in Washington,Dc Re Util Decision Not to Install Dedicated Blowdown Sys at Davis Besse & Implications of Diablo Canyon Loss of Shutdown Cooling Event.Viewgraphs Encl
ML20195G3651987-08-0707 August 1987
Summary of CRGR Meeting 116 on 870610 Re Final Rule Amends to 10CFR30,40,50,51,70 & 72 Concerning Requirements for Decommissioning Facility.List of Attendees Encl
ML20245C2601987-08-0707 August 1987
Summary of CRGR Meeting 116 on 870610 Re Final Rule Amends to 10CFR30,40,50,51,70 & 72 Concerning Requirements for Decommissioning Facility.List of Attendees Encl
ML20215C8721987-06-0808 June 1987
Summary of Operating Reactors Events Meeting 87-10 on 870406 Re Events Which Occurred Since 870330 Meeting.List of Attendees,Events Discussed & Significant Elements of Events & Summary of Reactor Scrams & Significant Events Encl
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
ML20215L3281987-05-0505 May 1987
Summary of Operating Reactors Events Meeting 87-11 on 870420.List of Attendees,Viewgraphs & Input to NRC Performance Indicator Program Encl
ML20210T4031987-01-28028 January 1987
Summary of Operating Reactors Events Meeting 87-02 on 870112 of Events Which Occurred Since 870105.List of Attendees,Events Discussed & Summary of Events Encl
ML20210T3641987-01-16016 January 1987
Summary of Operating Reactors Events Meeting 87-02 on 870112 Re Events Which Occurred Since 870105.List of Attendees,Events Discussed & Summary of Events Encl
ML20205K7591986-12-31031 December 1986
Summary of ACRS 320th Meeting on 861211-13 in Washington,Dc Re New Requirements for BWR Mark I Containments in Regard to Severe Accidents & Proposal for Commission Policy Statement on Deferred Plants (SECY-86-359)
ML20211Q6161986-07-23023 July 1986
Summary of Operating Reactor Events Meeting 86-25 on 860721 Re Events Since 860714 Meeting.List of Attendees,Discussion of Events & Status of Assignments Encl.Response Requested for Incomplete Assignments
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
ML20206J6561986-06-23023 June 1986
Trip Rept of 860612 Training Session in Lacey,Wa Re Federal Radiological Emergency Response Plans & Meeting W/Utils & State of Wa Concerning Potential Emergency Preparedness Issues.Attendees Listed & Training Agenda Encl
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
ML20210J0261986-03-24024 March 1986
Summary of Operating Reactor Events Meeting 86-08 on 860317 to Discuss Events Occurring Since Last Meeting on 860310
ML20214E6961986-03-14014 March 1986
Summary of Allegation Review Board 860313 Meeting Re Disposition of Listed Items,Including Case 5-85-042, Allegation 1717 Re Discrimination Against Former Document QA Reviewer for Pullman Power Products
ML20154N8751986-03-12012 March 1986
Summary of Operating Reactor Events 860310 Meeting 86-07 W/Ornl Re Events Occurring Since 860303 Meeting.Followup Review Assignments,Status of Previous Assignments,List of Attendees & Viewgraphs Encl
ML20141F0461985-12-30030 December 1985
Summary of Operating Reactors Events Meeting 85-28 on 851223.List of Attendees & Viewgraphs Encl
ML20138M9281985-12-12012 December 1985
Summary of Operating Reactor Events Meeting 85-25 on 851202 Re Listed Events.Attendee List,Summary of Events Discussed & Viewgraphs Encl
ML20134L0291985-07-30030 July 1985
Summary of ACRS Subcommittee on Diablo Canyon 850710 Meeting W/Pg&E in Washington,Dc Re NRC Evaluation of Util long-range Seismic Program for Plant.Fr Notice,Meeting Agenda & List of Handouts Encl
ML20127E1361985-05-25025 May 1985
Trip Rept of ACRS Subcommittees on Extreme External Phenomena & Diablo Canyon 850321-22 Meetings in Los Angeles,Ca Re NRC Seismic Margins Program & Long-Term Seismic Program of Diablo Canyon Power Plant
ML20128L6941985-05-24024 May 1985
Summary of ACRS Subcommittees on Extreme External Phenomena & Diablo Canyon Units 1 & 2 840524 Meeting in Los Angeles,Ca Re Chairman Palladino 840413 Request for Comments on Technical Paper Which Recharacterizes Hosgri Fault
ML20210E6611984-08-22022 August 1984
Summary of 840424 Meeting W/R Kranzdorf,M Mcgee,D Jeter & J Carsel in San Luis Obispo,Ca Re Roles of Federal,State & Local Agencies in Development of Emergency Plans.Allegation Task 80 Closed.Supporting Documentation Encl
ML20215G5261983-12-22022 December 1983
Summary of 831222 Meeting Re Clarification of Lockert Termination & Subsequent Grievance Which Originally Presented & Denied by Pullman Power Products on 831219. Attendee List Encl.Partially Withheld Related Info Encl
ML20215G5011983-12-19019 December 1983
Summary of 831219 Meeting Re Submittal of Grievance to Pullman Power Products Concerning Termination of Lockert, QA Inspector,On 831215.List of Attendees Encl
ML20210E6861983-10-14014 October 1983
Summary of Review Panel 831012 Meeting Re Reinstatement of License.Knighton Aware of Licensee Request for Exemption from Requirements of 10CFR50,App R & Will Determine Required Licensee Action & Schedule.Related Info Encl
ML20212M1071982-05-18018 May 1982
Summary of 820518 Meeting W/Bechtel & Util Re Role of Bechtel in Completion of Diablo Canyon Project.Related Info Encl
ML20197F6761981-11-17017 November 1981
Summary of 811109-10 Site Visit to Review Physical Model of Backwater & Surrounding Coastal Areas
ML20197F6651981-10-14014 October 1981
Summary of 810925 Meeting W/Util Re Various Approaches Available to Resolve UHS Intake Structure Flood Protection Concerns
ML20150B5381978-10-18018 October 1978
Summary of 781005 Meeting Re Status of Review Schedule. List of Attendees Encl
ML20147F6501978-10-0606 October 1978
Summary of ACRS Subcommittee on Diablo Canyon 780614-15 Meetings Re Status of Seismic Design Criteria & Status of Seismic Reevaluation Program
ML20212M4191977-06-29029 June 1977
Summary of 770602 Meeting W/Util,Westinghouse & Ctr for Law in Public Interest Re Plant Seismic Design.Attendee List Encl
ML20237F7941975-10-30030 October 1975
Summary of 750828 Meeting W/Util in Bethesda,Md Re Forthcoming Geology & Seismology Submital for Facilities. Attendees List Encl
ML20236C3891975-07-24024 July 1975
Summary of ACRS 750605 Meeting in Washington,Dc Re Plant. List of Attendees & Proposed Meeting Agenda Encl
ML20236C7821975-06-17017 June 1975
Summary of ACRS Subcommittee 750523 Meeting in Los Angeles, CA Re Plant.List of Attendees & Agenda Encl
ML20236C8661975-05-0808 May 1975
Summary of 750404 Meeting W/Util,Westinghouse & John Blume & Assoc in Bethesda,Md Re Seismic Design of Plant
ML20237F8101975-02-24024 February 1975
Summary of 750131 Meeting W/Usgs in Denver,Co Re Geology & Seismology Input to Diablo Canyon Ser.Attendees List Encl. W/O Encl
ML20236B5141974-09-27027 September 1974
Summary of ACRS Subcommittee 740912 Meeting W/Util & Consultants,Westinghouse & USGS in Washington DC Re Early Review of Util OL Application.Attendance List Encl
ML20237F8301974-07-11011 July 1974
Summary of 740705 Meeting W/Util & Earth Sciences Assoc in San Francisco Re Review of Progress of Offshore Geological Investigations Initiated by Util.Attendees List & Summary of Facility Offshore Seismic Interpretation Progress Encl
ML20236B8591973-09-0707 September 1973
Summary of 730821 Meeting W/Util & Westinghouse in Bethesda,Md Re Deficiencies in Plant FSAR Submittal. Attendance List Encl
ML20237G0671967-08-17017 August 1967
Summary of 670815 Meeting W/Util,Westinghouse,Usc&Gs, Newmark & Hall,Phillips Petroleum & Ja Blume & Assoc Re Continued Review of Seismic Design Bases for Plant. Attendees List Encl
ML20237G0881967-05-25025 May 1967
Summary of 670516 Meeting W/Util,Acrs & AEC Consultants Re Discussions of Seismic Design of Diablo Canyon Reactor. Meeting Attended by Listed Persons
1996-11-05
[Table view]
Category:TRIP REPORTS
MONTHYEARML20129J5741996-11-0505 November 1996
Trip Rept of 961001-03 Visit to Omega Point Labs in San Antonio,Tx to Witness Three Fire Endurance Tests Conducted for PG&E
ML20206J6561986-06-23023 June 1986
Trip Rept of 860612 Training Session in Lacey,Wa Re Federal Radiological Emergency Response Plans & Meeting W/Utils & State of Wa Concerning Potential Emergency Preparedness Issues.Attendees Listed & Training Agenda Encl
ML20127E1361985-05-25025 May 1985
Trip Rept of ACRS Subcommittees on Extreme External Phenomena & Diablo Canyon 850321-22 Meetings in Los Angeles,Ca Re NRC Seismic Margins Program & Long-Term Seismic Program of Diablo Canyon Power Plant
ML20197F6761981-11-17017 November 1981
Summary of 811109-10 Site Visit to Review Physical Model of Backwater & Surrounding Coastal Areas
1996-11-05
[Table view] |
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TRIP REPORT 21-22 MARCH ~1985 MEETING ACRS SUBCOMMITTEES ON EXTREME EXTERNAL PHENOMENA AND DIABLO CANYON LOS ANGLES, CA "t e d
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ACRS Subcommittee Meetins, March 21-22,1985
- 1. NTRODUCTION Two major topic areas were discussed at the ACRS subcommitte meetins:
(1) NRC Seismic Marsins Prosram (SMP)
(2) Lons Term Seismic Prosram (LTSP) of the Diablo Canyon Powe'r Plant (DCPP)
Presentations were made t y the NRC Staff, Consultants to the NRC. PGLE Staff, and Consultants to PG&E.
Listed below are some of my Comments relevant to these two TOPIC areas.
2.0 DISCUSSION 2.1 ELECTRICAL RELAYS There is concern about the response and operation of electrical relays durins a seismic event. A frasility test Prosram is Planned. This test Prosram is very imPortant to insure Plant safety.
-1
- The US Navy has developed sisnificant experience on the response of Circuit breakers and the behavior of other electrical equipment to hish impact shock loads. It is recommended that the NRC Staff make use of this experience in their evaluation of electrical components for nuclear Power plants.
2.2 CAST / BRITTLE MATERIALS Materials with low ductility respond Poorly to dynamic loads. Specifically,' Gray and White Cast Irons, Cast Aluminums, Fiber Glass Epoxy Composites and Ceramics historically have failed when subjected to vibration or shock loads. This statement does not mean that every component With ga Part fabricated from one of these materials Will fail.
- However failure of one of these components is much more I likely than those fabricated from ductile materials. For example, the only failure in a fossile fuel Power Plant (not seismically desisned) that I know of occured in a cast iron Pipe fittin9 or flan 9e. It should be emphasized that the type of' cast iron' used ice this fittins'(sray ductile, etc.) is not known.
As a result, it is recommended that a survey be made of the materials used in safety related items of nuclear Power Plants and that sPeCial Consideration be siven to the
- !frasility-of these items fabricated from brittle materials usins both test and analysis.
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U 2 ACRS Subcommittee Meetins, March 21-22,1985 2.3 ANCHORS Failures of equipment from earth 9uake excitation haVe often occured from bolt or anchor failures. Furthemore, equipment is often anchored into concrete. As a resulte frasility of anchors of safety related equipment must be throushly evaluated.
2.4 BOLTS It was mentioned in the Presentation (by Dr. R. Kennedy) that bolt yieldins is sometimes considered in Joint analyses.
Furthermore, it is understood that hish strensth bolts are sometimes used to anchor major Components to the Containment structure.
It is stronsly recommended that anchor bolts be desisned for maximum enersy absortion by cuttine the shank diameter to the root diameter of the bolt if this desien feature is not already beine employed. If this modification is not done and if the bolt is loaded beyond the yield Pointe Plastic strains concentrate at the first few threads of the bolt. In seneral, the stronser the bolt the less the Plastic strain before fracture. The fatisue impact strensth of bolts can be increased by a factor of two to four (or more) by cuttins the bolt shank to the root diameter.(Ref. Harris & Crede "SHOCH AND VIBRATION HANDB00K",2nd Edition, McGraw HilleP 43-8).
Thus, this simple modification can increase the marsin of safety for dynamic loads sisnificantly and , therefore, should be considered in both the SMP and the LTSP of DCPP.
2.5 SOIL-STRUCTURE INTERACTION The LTSP Proposed by PGLE is to be commended of its throushness. A few susestion are offered related to the soil-structure interaction Problem.
(1)Prosram The Proposed Prosram ProVides a uni 9ue opportunity to further understand soil structure interaction and the_ tau effect for a stiff soil (soft rock) site (Vs about 4000fes).
(2) Free Field Ground motion Three triaxial accelerometers at different
' locations on the Plant Property Can be used to record free field sround motion. However, because of the complex toPo9PaPhy, it is expected that recordines at these three
" free field" locations may be sisnificantly different. This Problem should be investi9ated by ComParin9 both time-history motion and response spectra of the motion at these three
- locations. If~these three motiont e sisnificantly Ldifferente consideration should be siven to FEM analysis of
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' ri .
ACRS Subcommittee Meetins, March 21-22,1985 different, consideration should be siven to FEM analysis of the Plant site in an attempt to understand recorded motions and to. extend that work to study soil-structure interaction effects.
(3) Calculated Ground Motion It is understood that an estimate of site free motion will be made startins with an assumed fault motion. It is sussested that an attempt be made to calculate free field motion of small recorded earthquakes measured at the site in order to assess the accuracy of the analytical procedure.
2.6 FIRE SAFETY CONSIDERATIONS The interrelationship betWeen fire started by an earth 9uake and Plant safety should be evaluated. For example, a Ceramic hish voltase insolator could fail startins a fire. How would Plant safety be compromised?
2.7 EMPHASIS The orisinal seismic desien of the DCPP was based on a Peak scound acceleration of 0.2G. Reevaluation of this motion in lisht of the Hossri fault and additional earthquake data will probably lead to analyses of seismic marsins based on scound motions f rom O'.5 G to 1.0 G Peak 9 Pound accelerations. As a result Code allowable stress criteria may be exceeded at some locations. Howevere because of the enersy absorbtion Capability of ductile metalse failure of ductile Components or structures is not expected. Failures of anchors, materials with low ductility and control systems is much more likely.
Emphasis should be Placed on these failure modes.
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