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| {{#Wiki_filter:}} | | {{#Wiki_filter:; Kf f UNITED STATES NUCLEAR REGULATORY COMMISSION 0 W ASHfNGToH. O. C. 20555 FE.o 14 1975 Docket Nos. 50-416 and 50-417 Applicant: Missis |
| | , -- sippi Power & Light Company Facility: Grand Gulf Nuclear Station Units 1 and 2 |
| | |
| | ==SUMMARY== |
| | OF MEETING HELD ON FEBRUARY 5,1975 TO DISCUSS THE DERIVATION OF DYNAMIC LOADS CONSIDERED IN THE CONTAINMENT STRUCTURES DESIGN. |
| | A meeting was held on February 5, 1975, at the NRC offices in Bethesda, Maryland to discuss in detail the derivation of dynamic loads considered in the design of containment structures and the significance of these loads to the overall loading on the structures. An attendance list is provided in Enclosure I. |
| | The applicants' Architect Engineer (Bechtel) began the meeting by identi-fying the principal structures that would be subject to loading from sup-pression pool dynamic effects. These structures are: the containment walls, the drywell and wierwell walls, and concrete and metal grating floors at approximately the 120 ft. and 135 ft. elevation. Bechtel draw-ings (No. M-1308, M-1300, M-1207 5 c-1000) were provided for staf f infor-mation and will be made available in the public document room. The pre- - |
| | liminary bounding calculation of suppression pool dynamic loading provided by the General Electric Company in 1972 was used by Bechtel in the design of these structures. The conservatism of these loads is currently being verified by the G.E. Mark III Containment Test Program. The applicants stated that, with exception of the safety / relief valve discharge line loads, a]l suppression pool dynamic loads were supplied by the General Electric Company and the applicants are relying upon GE for justification of the con-servatism of these loads. Bechtel did make a presentation of.their method for calculating loads induced by operation of safety / relief valves. How-ever, the staff expressed strong disagreement with the calculational tech-niques used and the applicants agreed e.o provide additional information to support the correctness and conservatism in their approach, ocutio,k V 5 We.#6 |
| | / |
| | 8806160317 FOI A 000606 PDR PDR l CONNOR88-91 l |
| | |
| | I Mississippl Power 6 f.ight Co. p |
| | ~d The staff noted that.all suppression pool dynamic loads used by Bechtel were assumed to occur symmetrically about the circumference of contain-ment structures. The staff stated that the potential for asymmetrical loading must be considered and the applicant will be required to show that structures will tolerate the loads, or provide justification for assuming that asymnetrical loading effects are not significant. It was noted by all that the General Electric test program is not designed to resolve this concern and, therefore, independent action by the applicants is required. |
| | The applicants summarized the construction progress at the site by stating that they will begin pouring concrete for containment structures' foundations in June or July, 1975. There is about a 1,000 man. construction force on the site now with a peak force of 3,000 men projected for some time in 1976. |
| | Concern wac expressed that concrete for structures subject to suppression pool dynamic loading would be poured before the results of the GE tests were available to verify the etnservatism in the design loads. The staff stated that the validity of suppression pool dynamic loads supplied by G.E. had not yet been agreed to by the staff and that the applicants proceed at their own risk in placing structures whose design is based on. unverified loads. (Note: |
| | PSAR Amendment 18 states' "Floors are presently being designed using a con-servative model to calculate loads induced by suppression pool swell. The desien, however, is capable of being strengthened after construction, .if necessary, to accommodate results of tests underway at General Electric. The floors will be designed for whatever loads the tests show are necessary.") |
| | The staff further stated that the GE Mark III containment test program is designed to provide the neccssary data ta confirm the conservatism of the suppression pool dynamic loads with the exception of loads due to safety / |
| | relief valve operation and asymmetrical considerations. This information must be provided directly by the applicants since the staff evaluation of the results of the G.E.' test program will not resolve this issue. |
| | Tha staff asked several questions in order to determine the significance of suppression pool dynamic loads in the overs 11 loading combinations used in the containment structures design. The applicants were unable to provide I a soecific' break down of the significance of pool dynamic loads as compared with temperature, pressure and hydrostatic loads for each structure. Bechtel stated that the information was available and could be provided. To facili- l tate the staff evaluation of the overall importance of pool dynamic loads, l the applicants agreed to provide the following detailed information for each. ! |
| | structure: |
| | : 1. The controlling loading combination used for design; |
| | |
| | __r.._ _. . _ . _ . . . _ . . . . - _ _ _ - _ __ |
| | 1 |
| | /. gt n!6 |
| | * Mississippi Power & Light Co. ii |
| | : 2. The magnitude of each component of the loading combination; |
| | : 3. The basis (justification) for pool- dynamic loads as they appear in each loading combination (i.e. test data or analytical cal-culation); and |
| | : 4. References for documentation.of each basis (3. above) for pool-dynamic loads. |
| | It was soggested that.this information could be added to Bechtel Drw. |
| | C-1000 to make uit a more complete document, describing p,ool dynamic load-ing. Also this information will be provided ASAP'and.in advance of other additional information requested so that the evaluation of the importance of suppression pool dynamic loads to the design as it now exists can-proceed prior to.the placing of concrete, |
| | , ,[.r,.,f ^ |
| | : b. . |
| | Edward J. Butcher, Project Engineer |
| | ' Light Water Reactors Branch 1-2 Division of Reactor Licensing i |
| | e l |
| | d i |
| | a |
| | |
| | i 4 |
| | ENCf.0SURE ATTENDANCE LIST MEETING WITH MISSISSIPPI POWER 6 LIGHT COMPANY ON GRAND GULF FEBRUARY 5 1975 NRC BECHTEL POWER CORP. |
| | E. J. Butcher R. L. Hails |
| | *W. R. Butler J. J. Tkacik V. A. Kudrick C. L. Reid G. C. Lainas F. C. Cheng L. Slegers R. Cudlin MISSISSIPPI POWER & LIGHT |
| | *F. P. Schaver L. F. Dale |
| | *R. L. Tedesco ACRS G.E. |
| | P. T. Burnette N. C. Shirley Z. Zudans |
| | *Part time attendance i |
| | 4 |
| | _ ________m.__________}} |
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Category:MEETING MINUTES & NOTES--CORRESPONDENCE
MONTHYEARML20210P1611999-08-0404 August 1999 Summary of 990415 Meeting with Utils in Knoxville,Tn Re Status of Mark 3 Program Designed to Determine & Validate Submerged Structure Drag Loads of Newley Installed ECCS Strainers at Perry,Grand Gulf & Clinton Facilities ML20198G5501998-12-18018 December 1998 Summary of 981201-02 Workshop with Entergy Operations,Inc in Taft,La Re Licensing Processes,Licensing Submittals & Other Topics That May Affect Licensing Processes & Submittals. Copy of Slides Presented During Workshop Encl ML20155H3931998-11-0202 November 1998 Summary of 981007 Meeting with Util Re Review Status of Standard Quality Assurance Manual for All Util Sites.List of Meeting Attendees Encl ML20154C4771998-10-0202 October 1998 Summary of 980908 Meeting with Cleveland Electric Illuminating Co,Entergy Operations,Inc & Illinois Power Co Re Joint Effort to Propose TSs to Reduce Requirements on Secondary Containment Integrity During Refueling ML20151X0011998-09-10010 September 1998 Summary of 980827 Meeting W/Util to Discuss Status of Review of Std QA Manual.List of Attendees Encl ML20237E0271998-08-25025 August 1998 Summary of 980625 Meeting W/Entergy Operations,Inc to Discuss Bulletin 96-003 Re Installation of ECCS Suction Strainer in Ninth Refueling Outage for Plant.List of Attendees & Licensee Handout ML20236M0501998-07-0808 July 1998 Summary of 980702 Meeting W/Entergy Operations,Inc to Discuss Review Status of Std QA Manual for All Entergy Sites.List of Attendees Encl ML20236F8171998-06-24024 June 1998 Summary of 980331 Meeting W/Util to Brief NRC on Licensee Risk Mgt of Upcoming Ninth Refueling Outage.List of Attendees & Handouts Encl ML20217K5141998-04-24024 April 1998 Summary of 980416 Meeting W/Entergy Corp Re Standardization of site-specific Security Plans.List of Meeting Attendees & Agenda for Meeting Encl ML20217K3461998-04-24024 April 1998 Summary of 980401 Meeting W/Entergy Operations,Inc Re Licensing Issues & Regulatory Performance Efficiencies.List of Attendees & Agenda for Meeting Encl ML20217F4811998-03-26026 March 1998 Summary of 980319 Meeting W/Licensee to Discuss Status of Development of Std QA Manual for All Entergy Sites.List of Attendees Encl ML20216C6471998-03-0505 March 1998 Summary of 980123 Meeting W/Entergy Operations,Inc Re EP Changes Being Considered by Licensee.List of Meeting Attendees,Meeting Agenda & Info Provided by Licensee at Meeting in Handout Encl ML20203B5741998-02-11011 February 1998 Summary of 980122 Meeting W/Entergy in Rockville,Maryland Re Licensing Issues & Standardization of Licensing Documents. List of Meeting Attendees & Meeting Agenda Encl ML20212G8521997-10-29029 October 1997 Summary of 971022 Meeting W/Entergy Svcs,Inc Re Development & Implementation of Common or Std QAP for All Sites.List of Meeting Attendees & Viewgraphs Encl ML20217E0131997-09-29029 September 1997 Trip Rept of 970825-26 Visit to Plant,Unit 1 for Interviews in Preparation of Salp.Agenda for Interviews Encl ML20198R3481997-09-0404 September 1997 Trip Rept of 961121 Visit to GGNS to Discuss Implementation Methodologies Employed for Graded Aq in Procurement Area ML20141H3661997-07-17017 July 1997 Summary of 970710 Meeting W/Util to Discuss Licensee Emergency Plan Change 28.001-95 & to Determine If Change Reduces Effectiveness of Emergency Plan for Plant,Unit 1. List of Attendees,Agenda & Info Provided by Licensee Encl ML20137U1331997-04-10010 April 1997 Summary of 970325 Meeting W/Util in Clariborne County,Ms to Discuss Entergy Operations,Inc MOV Thrust Methodology Used for GL 95-07 for Plant.List of Attendees & Info Provided by NRC Staff Encl 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 ML20132D1421996-12-17017 December 1996 Summary of 960827 Meeting W/Util in Rockville,Md Re Graded Quality Assurance Initiative at Facility.W/Attendees List, Summary of Licensee Presentation & Licensee Expert Panel Guidance Document ML20149M3611996-12-11011 December 1996 Summary of 96111 Meeting W/Licensee in Rockville,Md to Discuss Comments Developed in Response to NRC Advance Notice of Proposed Rulemaking on Financial Assurance Requirements for Decommissioning Nuclear Reactors.List of Attendees Encl ML20134N5661996-11-21021 November 1996 Summary of 961003 Meeting W/Licensee in Rockville,Md to Discuss Licensee Upcoming Eighth Refueling Outage for Ggns,Unit 1 ML20134M6611996-11-21021 November 1996 Summary of 961114 Meeting W/Listed Licensees in Rockville,Md to Discuss Results of Self Assessment of Accuracy of Info in FSARs for Four Nuclear Reactor Sites.List of Attendees & Licensee Handout Encl ML20129G5261996-07-31031 July 1996 Summary of ACRS Plant Operations Subcommittee Meeting on 960521 to Review Proposed Rule on Shutdown Operations & Associated Reg Guide as Well as Studies on Shutdown Risk at Surry & Grand Gulf Nuclear Plants ML20059C4041993-12-27027 December 1993 Summary of 931206 Meeting W/Entergy Operations,Inc in Rockville,Md to Discuss Licensee Proposed Changes to Security Plans for Plant,Units 1 & 2.List of Attendees Encl ML20058P4491993-12-15015 December 1993 Summary of 931206 Meeting W/Entergy Operations,Inc in Rockville,Md Re 931021 Submittal of Proposed Alternative to 10CFR50.55a(f) & (g),10-Year Inservice Insp & Inservice Testing Update. List of Attendees Encl ML20058G3081993-11-19019 November 1993 Summary of Operating Reactors Events Meeting 93-43 on 931117 ML20056H5721993-08-0505 August 1993 Summary of Operating Reactors Events Meeting 93-28 on 930728 ML20217C5121991-07-0303 July 1991 Summary of Operating Reactors Events Meeting 91-12 on 910626 ML20062H4811990-11-28028 November 1990 Summary of 901023 Meeting W/Util Re Control Room Emergency Filtration Sys.Proposed Change to TS 3/4.7.2 & Handout Encl ML20056B4161990-08-17017 August 1990 Summary of 900615 Meeting W/Licensee at Site to Discuss Licensing Activities.List of Attendees,Meeting Agenda, Handout & Licensee Comments on Draft Safety Evaluation of Fire Protection Program 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 ML20247E3641989-09-0606 September 1989 Summary of 890717 Meeting W/Numarc,B&W Owners Group & Representatives of Lead Plants Re Status of STS Amends & Outstanding Issues Associated W/Lead Plant STS Submittals ML20247D5291989-09-0505 September 1989 Summary of Operating Reactors Events Meeting 89-31 on 890830.Significant Event for Input Into NRC Performance Indicator Program Identified ML20247K2471989-08-24024 August 1989 Trip Rept of Staff 890718-19,21 & 0801-02 Visits to Nuclear Power Plants to Gather Info Re Industry Actions to Address Loss of Oil Malfunctions of Rosemount Models 1153 & 1154 Transmitters ML20246K2171989-08-24024 August 1989 Summary of Operating Reactors Events Meeting 89-30 on 890823 Re Reactor Trip W/Multiple Instrumentation & Equipment Failures at DC Cook Unit 2 on 890814 & Auxiliary Feedwater Flows at Hb Robinson ML20248B5171989-08-0303 August 1989 Summary of 890725 Interface Meeting W/Util in Birrmingham,Al Re Sonopco/Util Corporate Organization Including Generic Activities & Initiatives Re Plants.Agenda & Viewgraphs Encl 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 ML20246P7771989-07-13013 July 1989 Summary of Operating Reactors Events Meeting 89-26 on 890712.Events Discussed & Significant Elements of Events Presented in Encl 2.List of Attendees Also Encl ML20246F8691989-06-22022 June 1989 Summary of Operating Reactors Events Meeting 89-24 on 890621.On 890615,potential Unmonitored Primary Coolant Release Path to Environ Discovered at WPPSS-2.On 890617,loss of Offsite Power Occurred at Brunswick,Unit 2 ML20245G6411989-06-15015 June 1989 Summary of Operating Reactors Events Meeting 89-23 on 890614.On 890607,multiple Electrical Distribution Sys Problems Occurred at Oconee,Units 1,2 & 3.On 890610,unit Power Signal Caused Scram ML20244D8961989-06-12012 June 1989 Summary of 890518 Meeting W/Util Re Performance of Licensing Activities.Meetings Should Be Scheduled to Seek Means for Eliminating Weaknesses Identified by NRC ML20244C6441989-06-0909 June 1989 Summary of 890517 Meeting W/Seri in Rockville,Md Re Licensee Plans for Fuel Cycle 5,which Include Use of New Type of Fuel Assembly Developed by Advanced Nuclear Fuels Corp ML20245F2221989-06-0808 June 1989 Summary of Operating Reactors Events Meeting 89-21 on 890531.List of Attendees & Related Info Encl ML20245A3851989-05-30030 May 1989 Summary of Operating Reactors Events Meeting 89-20 on 890524.List of Meeting Attendees & Viewgraphs Encl ML20247M7961989-05-24024 May 1989 Summary of 890502 Meeting W/Util,Sargent & Lundy & Rl Cloud Assoc in Rockville,Md Re Nonlinear Piping Analyses Used to Justify Removal of Snubbers & Pipe Supports.List of Attendees & Presentation by Licensee & Contractors Encl ML20247K0901989-05-23023 May 1989 Summary of 890517 Meeting W/Inpo Re Similarities & Differences Between Performance Indicator Programs.Detailed Discussion Encl ML20247J7051989-05-19019 May 1989 Summary of 890501 Meeting w/C-E Owners Group in Rockville,Md Re Diverse Emergency Feedwater Actuation Sys,Per 10CFR50.62 Requirements.List of Meeting Attendees & Viewgraphs Encl. Record Copy ML20247J6991989-05-19019 May 1989 Summary of 890501 Meeting w/C-E Owners Group in Rockville,Md Re Diverse Emergency Feedwater Actuation Sys,Per 10CFR50.62 Requirements.List of Meeting Attendees & Viewgraphs Encl ML20247K1011989-05-16016 May 1989 Summary of 890517 Meeting W/Inpo in Bethesda,Md Re Similarities & Differences Between INPO & NRC Performance Indicators 1999-08-04
[Table view] Category:MEETING SUMMARIES-INTERNAL (NON-TRANSCRIPT)
MONTHYEARML20210P1611999-08-0404 August 1999 Summary of 990415 Meeting with Utils in Knoxville,Tn Re Status of Mark 3 Program Designed to Determine & Validate Submerged Structure Drag Loads of Newley Installed ECCS Strainers at Perry,Grand Gulf & Clinton Facilities ML20198G5501998-12-18018 December 1998 Summary of 981201-02 Workshop with Entergy Operations,Inc in Taft,La Re Licensing Processes,Licensing Submittals & Other Topics That May Affect Licensing Processes & Submittals. Copy of Slides Presented During Workshop Encl ML20155H3931998-11-0202 November 1998 Summary of 981007 Meeting with Util Re Review Status of Standard Quality Assurance Manual for All Util Sites.List of Meeting Attendees Encl ML20154C4771998-10-0202 October 1998 Summary of 980908 Meeting with Cleveland Electric Illuminating Co,Entergy Operations,Inc & Illinois Power Co Re Joint Effort to Propose TSs to Reduce Requirements on Secondary Containment Integrity During Refueling ML20151X0011998-09-10010 September 1998 Summary of 980827 Meeting W/Util to Discuss Status of Review of Std QA Manual.List of Attendees Encl ML20237E0271998-08-25025 August 1998 Summary of 980625 Meeting W/Entergy Operations,Inc to Discuss Bulletin 96-003 Re Installation of ECCS Suction Strainer in Ninth Refueling Outage for Plant.List of Attendees & Licensee Handout ML20236M0501998-07-0808 July 1998 Summary of 980702 Meeting W/Entergy Operations,Inc to Discuss Review Status of Std QA Manual for All Entergy Sites.List of Attendees Encl ML20236F8171998-06-24024 June 1998 Summary of 980331 Meeting W/Util to Brief NRC on Licensee Risk Mgt of Upcoming Ninth Refueling Outage.List of Attendees & Handouts Encl ML20217K3461998-04-24024 April 1998 Summary of 980401 Meeting W/Entergy Operations,Inc Re Licensing Issues & Regulatory Performance Efficiencies.List of Attendees & Agenda for Meeting Encl ML20217K5141998-04-24024 April 1998 Summary of 980416 Meeting W/Entergy Corp Re Standardization of site-specific Security Plans.List of Meeting Attendees & Agenda for Meeting Encl ML20217F4811998-03-26026 March 1998 Summary of 980319 Meeting W/Licensee to Discuss Status of Development of Std QA Manual for All Entergy Sites.List of Attendees Encl ML20216C6471998-03-0505 March 1998 Summary of 980123 Meeting W/Entergy Operations,Inc Re EP Changes Being Considered by Licensee.List of Meeting Attendees,Meeting Agenda & Info Provided by Licensee at Meeting in Handout Encl ML20203B5741998-02-11011 February 1998 Summary of 980122 Meeting W/Entergy in Rockville,Maryland Re Licensing Issues & Standardization of Licensing Documents. List of Meeting Attendees & Meeting Agenda Encl ML20212G8521997-10-29029 October 1997 Summary of 971022 Meeting W/Entergy Svcs,Inc Re Development & Implementation of Common or Std QAP for All Sites.List of Meeting Attendees & Viewgraphs Encl ML20141H3661997-07-17017 July 1997 Summary of 970710 Meeting W/Util to Discuss Licensee Emergency Plan Change 28.001-95 & to Determine If Change Reduces Effectiveness of Emergency Plan for Plant,Unit 1. List of Attendees,Agenda & Info Provided by Licensee Encl ML20137U1331997-04-10010 April 1997 Summary of 970325 Meeting W/Util in Clariborne County,Ms to Discuss Entergy Operations,Inc MOV Thrust Methodology Used for GL 95-07 for Plant.List of Attendees & Info Provided by NRC Staff Encl 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 ML20132D1421996-12-17017 December 1996 Summary of 960827 Meeting W/Util in Rockville,Md Re Graded Quality Assurance Initiative at Facility.W/Attendees List, Summary of Licensee Presentation & Licensee Expert Panel Guidance Document ML20149M3611996-12-11011 December 1996 Summary of 96111 Meeting W/Licensee in Rockville,Md to Discuss Comments Developed in Response to NRC Advance Notice of Proposed Rulemaking on Financial Assurance Requirements for Decommissioning Nuclear Reactors.List of Attendees Encl ML20134N5661996-11-21021 November 1996 Summary of 961003 Meeting W/Licensee in Rockville,Md to Discuss Licensee Upcoming Eighth Refueling Outage for Ggns,Unit 1 ML20134M6611996-11-21021 November 1996 Summary of 961114 Meeting W/Listed Licensees in Rockville,Md to Discuss Results of Self Assessment of Accuracy of Info in FSARs for Four Nuclear Reactor Sites.List of Attendees & Licensee Handout Encl ML20129G5261996-07-31031 July 1996 Summary of ACRS Plant Operations Subcommittee Meeting on 960521 to Review Proposed Rule on Shutdown Operations & Associated Reg Guide as Well as Studies on Shutdown Risk at Surry & Grand Gulf Nuclear Plants ML20059C4041993-12-27027 December 1993 Summary of 931206 Meeting W/Entergy Operations,Inc in Rockville,Md to Discuss Licensee Proposed Changes to Security Plans for Plant,Units 1 & 2.List of Attendees Encl ML20058P4491993-12-15015 December 1993 Summary of 931206 Meeting W/Entergy Operations,Inc in Rockville,Md Re 931021 Submittal of Proposed Alternative to 10CFR50.55a(f) & (g),10-Year Inservice Insp & Inservice Testing Update. List of Attendees Encl ML20058G3081993-11-19019 November 1993 Summary of Operating Reactors Events Meeting 93-43 on 931117 ML20056H5721993-08-0505 August 1993 Summary of Operating Reactors Events Meeting 93-28 on 930728 ML20217C5121991-07-0303 July 1991 Summary of Operating Reactors Events Meeting 91-12 on 910626 ML20062H4811990-11-28028 November 1990 Summary of 901023 Meeting W/Util Re Control Room Emergency Filtration Sys.Proposed Change to TS 3/4.7.2 & Handout Encl ML20056B4161990-08-17017 August 1990 Summary of 900615 Meeting W/Licensee at Site to Discuss Licensing Activities.List of Attendees,Meeting Agenda, Handout & Licensee Comments on Draft Safety Evaluation of Fire Protection Program 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 ML20247E3641989-09-0606 September 1989 Summary of 890717 Meeting W/Numarc,B&W Owners Group & Representatives of Lead Plants Re Status of STS Amends & Outstanding Issues Associated W/Lead Plant STS Submittals ML20247D5291989-09-0505 September 1989 Summary of Operating Reactors Events Meeting 89-31 on 890830.Significant Event for Input Into NRC Performance Indicator Program Identified ML20246K2171989-08-24024 August 1989 Summary of Operating Reactors Events Meeting 89-30 on 890823 Re Reactor Trip W/Multiple Instrumentation & Equipment Failures at DC Cook Unit 2 on 890814 & Auxiliary Feedwater Flows at Hb Robinson 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 ML20248B5171989-08-0303 August 1989 Summary of 890725 Interface Meeting W/Util in Birrmingham,Al Re Sonopco/Util Corporate Organization Including Generic Activities & Initiatives Re Plants.Agenda & Viewgraphs Encl ML20246P7771989-07-13013 July 1989 Summary of Operating Reactors Events Meeting 89-26 on 890712.Events Discussed & Significant Elements of Events Presented in Encl 2.List of Attendees Also Encl ML20246F8691989-06-22022 June 1989 Summary of Operating Reactors Events Meeting 89-24 on 890621.On 890615,potential Unmonitored Primary Coolant Release Path to Environ Discovered at WPPSS-2.On 890617,loss of Offsite Power Occurred at Brunswick,Unit 2 ML20245G6411989-06-15015 June 1989 Summary of Operating Reactors Events Meeting 89-23 on 890614.On 890607,multiple Electrical Distribution Sys Problems Occurred at Oconee,Units 1,2 & 3.On 890610,unit Power Signal Caused Scram ML20244D8961989-06-12012 June 1989 Summary of 890518 Meeting W/Util Re Performance of Licensing Activities.Meetings Should Be Scheduled to Seek Means for Eliminating Weaknesses Identified by NRC ML20244C6441989-06-0909 June 1989 Summary of 890517 Meeting W/Seri in Rockville,Md Re Licensee Plans for Fuel Cycle 5,which Include Use of New Type of Fuel Assembly Developed by Advanced Nuclear Fuels Corp ML20245F2221989-06-0808 June 1989 Summary of Operating Reactors Events Meeting 89-21 on 890531.List of Attendees & Related Info Encl ML20245A3851989-05-30030 May 1989 Summary of Operating Reactors Events Meeting 89-20 on 890524.List of Meeting Attendees & Viewgraphs Encl ML20247M7961989-05-24024 May 1989 Summary of 890502 Meeting W/Util,Sargent & Lundy & Rl Cloud Assoc in Rockville,Md Re Nonlinear Piping Analyses Used to Justify Removal of Snubbers & Pipe Supports.List of Attendees & Presentation by Licensee & Contractors Encl ML20247K0901989-05-23023 May 1989 Summary of 890517 Meeting W/Inpo Re Similarities & Differences Between Performance Indicator Programs.Detailed Discussion Encl ML20247J7051989-05-19019 May 1989 Summary of 890501 Meeting w/C-E Owners Group in Rockville,Md Re Diverse Emergency Feedwater Actuation Sys,Per 10CFR50.62 Requirements.List of Meeting Attendees & Viewgraphs Encl. Record Copy ML20247J6991989-05-19019 May 1989 Summary of 890501 Meeting w/C-E Owners Group in Rockville,Md Re Diverse Emergency Feedwater Actuation Sys,Per 10CFR50.62 Requirements.List of Meeting Attendees & Viewgraphs Encl ML20247K1011989-05-16016 May 1989 Summary of 890517 Meeting W/Inpo in Bethesda,Md Re Similarities & Differences Between INPO & NRC Performance Indicators ML20247D3441989-05-16016 May 1989 Summary of Operating Reactors Events Meeting 89-19 on 890510.List of Attendees,Events Discussed & Significant Elements of Events & Rept of long-term Followup Assignments & Summary of Scrams for Wk Ending 890507 Encl ML20247F8481989-05-11011 May 1989 Summary of 890214 Meeting W/Util in Rockville,Md Re Proposed Alternate DHR Sys & Proposed Exceptions to Tech Spec 3.0.4. Agenda & Related Info Encl ML20246L4791989-05-11011 May 1989 Summary of 890214 Meeting W/Util in Rockville,Md Re Pipe Support Calculations.List of Attendees & Handouts Encl 1999-08-04
[Table view] |
Text
- Kf f UNITED STATES NUCLEAR REGULATORY COMMISSION 0 W ASHfNGToH. O. C. 20555 FE.o 14 1975 Docket Nos. 50-416 and 50-417 Applicant
- Missis
, -- sippi Power & Light Company Facility: Grand Gulf Nuclear Station Units 1 and 2
SUMMARY
OF MEETING HELD ON FEBRUARY 5,1975 TO DISCUSS THE DERIVATION OF DYNAMIC LOADS CONSIDERED IN THE CONTAINMENT STRUCTURES DESIGN.
A meeting was held on February 5, 1975, at the NRC offices in Bethesda, Maryland to discuss in detail the derivation of dynamic loads considered in the design of containment structures and the significance of these loads to the overall loading on the structures. An attendance list is provided in Enclosure I.
The applicants' Architect Engineer (Bechtel) began the meeting by identi-fying the principal structures that would be subject to loading from sup-pression pool dynamic effects. These structures are: the containment walls, the drywell and wierwell walls, and concrete and metal grating floors at approximately the 120 ft. and 135 ft. elevation. Bechtel draw-ings (No. M-1308, M-1300, M-1207 5 c-1000) were provided for staf f infor-mation and will be made available in the public document room. The pre- -
liminary bounding calculation of suppression pool dynamic loading provided by the General Electric Company in 1972 was used by Bechtel in the design of these structures. The conservatism of these loads is currently being verified by the G.E. Mark III Containment Test Program. The applicants stated that, with exception of the safety / relief valve discharge line loads, a]l suppression pool dynamic loads were supplied by the General Electric Company and the applicants are relying upon GE for justification of the con-servatism of these loads. Bechtel did make a presentation of.their method for calculating loads induced by operation of safety / relief valves. How-ever, the staff expressed strong disagreement with the calculational tech-niques used and the applicants agreed e.o provide additional information to support the correctness and conservatism in their approach, ocutio,k V 5 We.#6
/
8806160317 FOI A 000606 PDR PDR l CONNOR88-91 l
I Mississippl Power 6 f.ight Co. p
~d The staff noted that.all suppression pool dynamic loads used by Bechtel were assumed to occur symmetrically about the circumference of contain-ment structures. The staff stated that the potential for asymmetrical loading must be considered and the applicant will be required to show that structures will tolerate the loads, or provide justification for assuming that asymnetrical loading effects are not significant. It was noted by all that the General Electric test program is not designed to resolve this concern and, therefore, independent action by the applicants is required.
The applicants summarized the construction progress at the site by stating that they will begin pouring concrete for containment structures' foundations in June or July, 1975. There is about a 1,000 man. construction force on the site now with a peak force of 3,000 men projected for some time in 1976.
Concern wac expressed that concrete for structures subject to suppression pool dynamic loading would be poured before the results of the GE tests were available to verify the etnservatism in the design loads. The staff stated that the validity of suppression pool dynamic loads supplied by G.E. had not yet been agreed to by the staff and that the applicants proceed at their own risk in placing structures whose design is based on. unverified loads. (Note:
PSAR Amendment 18 states' "Floors are presently being designed using a con-servative model to calculate loads induced by suppression pool swell. The desien, however, is capable of being strengthened after construction, .if necessary, to accommodate results of tests underway at General Electric. The floors will be designed for whatever loads the tests show are necessary.")
The staff further stated that the GE Mark III containment test program is designed to provide the neccssary data ta confirm the conservatism of the suppression pool dynamic loads with the exception of loads due to safety /
relief valve operation and asymmetrical considerations. This information must be provided directly by the applicants since the staff evaluation of the results of the G.E.' test program will not resolve this issue.
Tha staff asked several questions in order to determine the significance of suppression pool dynamic loads in the overs 11 loading combinations used in the containment structures design. The applicants were unable to provide I a soecific' break down of the significance of pool dynamic loads as compared with temperature, pressure and hydrostatic loads for each structure. Bechtel stated that the information was available and could be provided. To facili- l tate the staff evaluation of the overall importance of pool dynamic loads, l the applicants agreed to provide the following detailed information for each. !
structure:
- 1. The controlling loading combination used for design;
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- 2. The magnitude of each component of the loading combination;
- 3. The basis (justification) for pool- dynamic loads as they appear in each loading combination (i.e. test data or analytical cal-culation); and
- 4. References for documentation.of each basis (3. above) for pool-dynamic loads.
It was soggested that.this information could be added to Bechtel Drw.
C-1000 to make uit a more complete document, describing p,ool dynamic load-ing. Also this information will be provided ASAP'and.in advance of other additional information requested so that the evaluation of the importance of suppression pool dynamic loads to the design as it now exists can-proceed prior to.the placing of concrete,
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Edward J. Butcher, Project Engineer
' Light Water Reactors Branch 1-2 Division of Reactor Licensing i
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ENCf.0SURE ATTENDANCE LIST MEETING WITH MISSISSIPPI POWER 6 LIGHT COMPANY ON GRAND GULF FEBRUARY 5 1975 NRC BECHTEL POWER CORP.
E. J. Butcher R. L. Hails
- W. R. Butler J. J. Tkacik V. A. Kudrick C. L. Reid G. C. Lainas F. C. Cheng L. Slegers R. Cudlin MISSISSIPPI POWER & LIGHT
P. T. Burnette N. C. Shirley Z. Zudans
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