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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20206S2911999-05-0505 May 1999 Informs That on 990420 Council Provided ten-day Comment Period on Council Order 731 Recommending Governor Approval of Amend of Site Certification Agreement for Satsop Power Plant Site ML20202C7671999-01-22022 January 1999 Forwards Order Terminating Construction Permit CPPR-154 for WNP-3/5 Site.Safety Evaluation Associated with Action Also Encl ML20198Q7131999-01-0404 January 1999 Forwards EA & Fonsi Re 960808 Application.Assessment Being Forwarded to Ofc of Fr for Publication ML20155J9731998-11-0505 November 1998 Forwards Addl Detailed Info Re Restoration & Renovation of Site Bldgs Re Util Plans to Renovate Site for Reuse as Industrial Park by Local Government Entity ML20155G7791998-11-0202 November 1998 Forwards Insp Rept 50-508/98-201 on 981027-28.No Violations Noted.Insp Included Review of Activities to Terminate Construction Permit CPPR-154 ML20116M7191996-08-0808 August 1996 Requests Termination of Construction Permit (CPPR-154) of Nuclear Project 3 & Withdrawal of Pending OL WNP-3 ML20082A7771995-03-28028 March 1995 Forwards WPPSS Nuclear Projects 1,3,4 & 5 Restoration Plan ML20078M4961995-02-0303 February 1995 Advises of Termination of Util Projects 1 & 3 ML20059B7681993-10-20020 October 1993 Requests Code Case N-520 Approval for Nuclear Projects 1 & 3 ML20057A6031993-09-0303 September 1993 Forwards Rev 6 to Procedure WMC-051, Preservation of Assets Program, Reflecting Installation of Two Desiccant Type Dehumidifiers for Controlling Relative Humidity within Reactor Auxiliary/Reactor Bldg Superstructure ML17286B2741991-10-0808 October 1991 Forwards Rev 0 to Washington Nuclear Plant 3 Seismic Design Basis Model Validation,Soil Variation Studies, in Response to Open Items in Draft Safety Evaluation Re Soil/Structure Interaction/Deconvolution Issue ML17286B2661991-06-0707 June 1991 Requests Approval to Revise Tornado Design Criteria,Per Reg Guide 1.76,Section C.1.2 for Rotational & Translational Velocities. Justification for Revised Tornado Design Criteria Encl ML20073P9471991-05-13013 May 1991 Forwards Rev 5 to WMC-051, WNP-3 Preventive Maint Requirements by Equipment Type ML17286A5361991-01-0202 January 1991 Discusses Interpretation of 10CFR73,App B,Paragraph Ii.B Re Security Records Retention Period ML17286A3571990-10-12012 October 1990 Requests That Name Be Kept on Mailing List & That Firm Name Be Changed to Winston & Strawn in Response to 900927 Ltr ML20062A8981990-10-0101 October 1990 Responds to NRC Re Wish to Remain on Mailing List ML20059M0921990-09-27027 September 1990 Advises That Name Will Be Removed from Mailing List Unless Notification of Wish to Remain on List to Continue to Receive Info Re Facility Received within 30 Days ML20059M0901990-09-27027 September 1990 Informs That Name Will Be Removed from Mailing List Unless Notification of Wish to Remain on List to Continue to Receive Info Re Facility Received within 30 Days ML20059A5411990-08-16016 August 1990 Provides Notice of Changes in Key Personnel ML20056A7171990-07-27027 July 1990 Forwards Partial Vol 1 & Vols 4,5,6 & 7 of FSAR Re Potential Subduction Zones Earthquakes in State of Wa Coastal Area.W/O Encls ML20044A4931990-06-0808 June 1990 Requests That NRC Review of Facility Seismic Rept Completed & SER Issued as Soon as Possible.Facility Seismic Issue Resolution to Minimize Uncertainties Surrounding Economic Evaluations of Deferred Plants Important ML20042G3971990-05-11011 May 1990 Forwards Revised WMC-051, Washington Nuclear Plant-3 Preservation of Assets Program, Incorporating Changes Noted Through Preservation Experience & Successes Achieved in Improving Environ within Plant Bldgs ML20012B6941990-03-0101 March 1990 Forwards Compilation of Responses to Regulatory Impact Survey Questionnaire,Per Generic Ltr 90-01 ML19325D1831989-10-12012 October 1989 Confirms That Seismic Design Data Submitted Under Separate Cover to R Pichumani,Per 891003 Request ML20246N3191989-08-30030 August 1989 Forwards Addl Info Re Plant Soil Structure Interaction Analysis/Deconvolution Issue,Per 890213 Request.Results Presented in Encl Supplemental Rept Demonstrate Overall Significant Level of Conservatism in Seismic Design Basis ML20247R6131989-05-25025 May 1989 Documents Understanding of Agreements Re Geosciences Review & Preparation of Draft SER & Requests That Staff Schedule Geoscience Review to Be Completed by Sept 1989 in Order That Work Accomplished Currently Not Lost ML20247L3141989-05-11011 May 1989 Forwards Insp Rept 50-508/89-01 on 890413-14 & 0508.No Violations Noted ML17285A2071989-01-23023 January 1989 Forwards Wppss 1988 Annual Financial Rept.W/O Encl ML20206L7671988-11-21021 November 1988 Submits Addl Info in Response to Questions on Geosciences Program Clarifying Rates of Erosion Along State of or & State of Wa Coastlines Re Formation of Modern Wavecut Platforms.Questions Arose from NRC Sept 1988 Visit ML20153F4041988-08-29029 August 1988 Forwards Sassi Analysis & Further Clarification of Elastic Half Space Analysis Providing Confirmation That Finite Element Methodology Used for Plant Design Basis Sufficiently Conservative ML20153E2801988-08-26026 August 1988 Forwards Corrected Page 1 of NRC Forwarding Insp Rept 50-508/88-02 Re Readiness Review Module C3-02 Concrete. Ltr Issued W/O Date Annotated on First Page ML20153G4231988-08-22022 August 1988 Forwards Readiness Review Module C3-02 Concrete Insp Rept 50-508/88-02.Concrete Const Completed at Time of Work Stoppage Deemed Acceptable Assuming Open Items Resolved. Listed Items Will Be Pursued During Future Reviews & Insps ML20207G5251988-08-10010 August 1988 Forwards Plots Showing Computed Distributions of Frequency of Exceedance Displayed in Terms of Fractile Hazard Curves in Seismic Hazard Rept ML20150G0441988-06-30030 June 1988 Forwards Response to Questions 230.1 & 230.2 Re Resolution of Key Licensing Issues Concerning Questions on Cascadia Subduction Zone ML20196C3091988-06-17017 June 1988 Defers Responses to NRC Bulletins & Generic Ltrs Unless NRC Specifically Requests That Util Respond for Facility.Util Will Reply to Outstanding Bulletins & Generic Ltrs That Require Response Following Resumption of Const ML20154D2661988-05-16016 May 1988 Forwards Order Extending Const Completion Date to 990701 for Plant,Per Util 841102 & 860310 Requests.Safety Evaluation & Environ Assessment & Finding of No Significant Impact Also Encl ML20154R9251988-05-13013 May 1988 Responds to NRC Bulletin 88-003, Inadequate Latch Engagement in Hfa Type Latching Relays Mfg by Ge. Action on Bulletin Will Be Added to Plant Tracking Sys as Work to Be Accomplished Following Restart of Const ML20154F3191988-05-13013 May 1988 Advises That Due to long-term Const Delay Status of Plant, Action Re Suppl 1 to NRC Bulletin 87-002, Fastner Testing to Determine Conformance W/Applicable Matl Specs, Will Be Deferred Until After Restart of Const ML20154F5901988-05-13013 May 1988 Informs That Assurance That Program Implemented to Address Corrosive Effects of RCS Leakage at Less than Tech Spec Limits Per Generic Ltr 88-05 Will Not Be Provided Until After Restart of Const ML20151S4161988-04-21021 April 1988 Responds to Generic Ltr 88-03, Steam Binding of Auxiliary Feedwater Pumps. Commitment to Developing Procedures & Training for Recognizing Gas Binding Conditions & Restoring Operable Status of Safety Sys Still Valid ML20153G5781988-04-0505 April 1988 Advises That 880226 Changes & Corrections to Amend 7 of FSAR Section 17.3 Consistent W/Provisions of 10CFR50,App B & Acceptable ML20150D1301988-03-18018 March 1988 Forwards Responses to NRC 830503 & 11 Requests for Addl Info Re Application for Ol.W/Eight Oversize Drawings ML20148B5101988-03-15015 March 1988 Informs of Relocation of NRR to Stated Address in Rockville,Md ML20148G1241988-03-11011 March 1988 Forwards Insp Rept 50-508/88-01 on 880222-26.No Violations Noted ML20147J0341988-03-0707 March 1988 Responds to Sorensen Providing Proposed Schedule for Completion of Review of Geosciences Issues.Proposed Schedule Acceptable.Eforts Will Be Made to Accommodate Geosciences Issues for Facility ML20147H2741988-03-0404 March 1988 Informs That Response to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers, Delayed Until After Restart of Const ML20147D3841988-02-29029 February 1988 Forwards Seismic Hazards Assessment, Final Rept Per NRC 830503 Request for Addl Info Re Question 230.6 ML20147E1181988-02-26026 February 1988 Forwards Changes to FSAR Section 17.3, QA During Long-Term Preservation. Revised Section 17.3 Incorporated Into FSAR Amend 7 ML20149L9961988-02-23023 February 1988 Ack Receipt of 880205 Request for Info & Documents Re Certain Costs Billed to Util for June 1984 - Dec 1986 Review Period.Response Forthcoming ML20149M0031988-02-0505 February 1988 Requests Review of Details of Billings for Listed Periods & Transmittal of Copies of Billings for Periods of June 1984 - Dec 1984 & Dec 1984 - June 1985.Questions Delineated in Encl 1999-05-05
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20206S2911999-05-0505 May 1999 Informs That on 990420 Council Provided ten-day Comment Period on Council Order 731 Recommending Governor Approval of Amend of Site Certification Agreement for Satsop Power Plant Site ML20155J9731998-11-0505 November 1998 Forwards Addl Detailed Info Re Restoration & Renovation of Site Bldgs Re Util Plans to Renovate Site for Reuse as Industrial Park by Local Government Entity ML20116M7191996-08-0808 August 1996 Requests Termination of Construction Permit (CPPR-154) of Nuclear Project 3 & Withdrawal of Pending OL WNP-3 ML20082A7771995-03-28028 March 1995 Forwards WPPSS Nuclear Projects 1,3,4 & 5 Restoration Plan ML20078M4961995-02-0303 February 1995 Advises of Termination of Util Projects 1 & 3 ML20059B7681993-10-20020 October 1993 Requests Code Case N-520 Approval for Nuclear Projects 1 & 3 ML20057A6031993-09-0303 September 1993 Forwards Rev 6 to Procedure WMC-051, Preservation of Assets Program, Reflecting Installation of Two Desiccant Type Dehumidifiers for Controlling Relative Humidity within Reactor Auxiliary/Reactor Bldg Superstructure ML17286B2741991-10-0808 October 1991 Forwards Rev 0 to Washington Nuclear Plant 3 Seismic Design Basis Model Validation,Soil Variation Studies, in Response to Open Items in Draft Safety Evaluation Re Soil/Structure Interaction/Deconvolution Issue ML17286B2661991-06-0707 June 1991 Requests Approval to Revise Tornado Design Criteria,Per Reg Guide 1.76,Section C.1.2 for Rotational & Translational Velocities. Justification for Revised Tornado Design Criteria Encl ML20073P9471991-05-13013 May 1991 Forwards Rev 5 to WMC-051, WNP-3 Preventive Maint Requirements by Equipment Type ML17286A5361991-01-0202 January 1991 Discusses Interpretation of 10CFR73,App B,Paragraph Ii.B Re Security Records Retention Period ML17286A3571990-10-12012 October 1990 Requests That Name Be Kept on Mailing List & That Firm Name Be Changed to Winston & Strawn in Response to 900927 Ltr ML20062A8981990-10-0101 October 1990 Responds to NRC Re Wish to Remain on Mailing List ML20059A5411990-08-16016 August 1990 Provides Notice of Changes in Key Personnel ML20056A7171990-07-27027 July 1990 Forwards Partial Vol 1 & Vols 4,5,6 & 7 of FSAR Re Potential Subduction Zones Earthquakes in State of Wa Coastal Area.W/O Encls ML20044A4931990-06-0808 June 1990 Requests That NRC Review of Facility Seismic Rept Completed & SER Issued as Soon as Possible.Facility Seismic Issue Resolution to Minimize Uncertainties Surrounding Economic Evaluations of Deferred Plants Important ML20042G3971990-05-11011 May 1990 Forwards Revised WMC-051, Washington Nuclear Plant-3 Preservation of Assets Program, Incorporating Changes Noted Through Preservation Experience & Successes Achieved in Improving Environ within Plant Bldgs ML20012B6941990-03-0101 March 1990 Forwards Compilation of Responses to Regulatory Impact Survey Questionnaire,Per Generic Ltr 90-01 ML19325D1831989-10-12012 October 1989 Confirms That Seismic Design Data Submitted Under Separate Cover to R Pichumani,Per 891003 Request ML20246N3191989-08-30030 August 1989 Forwards Addl Info Re Plant Soil Structure Interaction Analysis/Deconvolution Issue,Per 890213 Request.Results Presented in Encl Supplemental Rept Demonstrate Overall Significant Level of Conservatism in Seismic Design Basis ML20247R6131989-05-25025 May 1989 Documents Understanding of Agreements Re Geosciences Review & Preparation of Draft SER & Requests That Staff Schedule Geoscience Review to Be Completed by Sept 1989 in Order That Work Accomplished Currently Not Lost ML17285A2071989-01-23023 January 1989 Forwards Wppss 1988 Annual Financial Rept.W/O Encl ML20206L7671988-11-21021 November 1988 Submits Addl Info in Response to Questions on Geosciences Program Clarifying Rates of Erosion Along State of or & State of Wa Coastlines Re Formation of Modern Wavecut Platforms.Questions Arose from NRC Sept 1988 Visit ML20153F4041988-08-29029 August 1988 Forwards Sassi Analysis & Further Clarification of Elastic Half Space Analysis Providing Confirmation That Finite Element Methodology Used for Plant Design Basis Sufficiently Conservative ML20207G5251988-08-10010 August 1988 Forwards Plots Showing Computed Distributions of Frequency of Exceedance Displayed in Terms of Fractile Hazard Curves in Seismic Hazard Rept ML20150G0441988-06-30030 June 1988 Forwards Response to Questions 230.1 & 230.2 Re Resolution of Key Licensing Issues Concerning Questions on Cascadia Subduction Zone ML20196C3091988-06-17017 June 1988 Defers Responses to NRC Bulletins & Generic Ltrs Unless NRC Specifically Requests That Util Respond for Facility.Util Will Reply to Outstanding Bulletins & Generic Ltrs That Require Response Following Resumption of Const ML20154R9251988-05-13013 May 1988 Responds to NRC Bulletin 88-003, Inadequate Latch Engagement in Hfa Type Latching Relays Mfg by Ge. Action on Bulletin Will Be Added to Plant Tracking Sys as Work to Be Accomplished Following Restart of Const ML20154F5901988-05-13013 May 1988 Informs That Assurance That Program Implemented to Address Corrosive Effects of RCS Leakage at Less than Tech Spec Limits Per Generic Ltr 88-05 Will Not Be Provided Until After Restart of Const ML20154F3191988-05-13013 May 1988 Advises That Due to long-term Const Delay Status of Plant, Action Re Suppl 1 to NRC Bulletin 87-002, Fastner Testing to Determine Conformance W/Applicable Matl Specs, Will Be Deferred Until After Restart of Const ML20151S4161988-04-21021 April 1988 Responds to Generic Ltr 88-03, Steam Binding of Auxiliary Feedwater Pumps. Commitment to Developing Procedures & Training for Recognizing Gas Binding Conditions & Restoring Operable Status of Safety Sys Still Valid ML20150D1301988-03-18018 March 1988 Forwards Responses to NRC 830503 & 11 Requests for Addl Info Re Application for Ol.W/Eight Oversize Drawings ML20147H2741988-03-0404 March 1988 Informs That Response to NRC Bulletin 88-001, Defects in Westinghouse Circuit Breakers, Delayed Until After Restart of Const ML20147D3841988-02-29029 February 1988 Forwards Seismic Hazards Assessment, Final Rept Per NRC 830503 Request for Addl Info Re Question 230.6 ML20147E1181988-02-26026 February 1988 Forwards Changes to FSAR Section 17.3, QA During Long-Term Preservation. Revised Section 17.3 Incorporated Into FSAR Amend 7 ML20149M0031988-02-0505 February 1988 Requests Review of Details of Billings for Listed Periods & Transmittal of Copies of Billings for Periods of June 1984 - Dec 1984 & Dec 1984 - June 1985.Questions Delineated in Encl ML20150C4591988-01-13013 January 1988 Describes Basic Aspects of 871221 Meeting W/Util in Bethesda,Md Re Ssi/Deconvolution Issues Re Audit Finding 1 & Provides Recommendations for Resolving Associated Issues ML20234D7321987-12-21021 December 1987 Proposes Deferral of Response to Compliance Bulletin 87-002 Until After Restart of Const ML20236S9331987-11-23023 November 1987 Discusses Violation Noted During Insp Rept 50-508/82-04 Re Questionable Welds.Items Identified on Nonconformance Rept (Ncr 15313) & Implementation of Corrective Action Will Be Entered Into Site Tracking Sys & Accomplished at Restart ML20236X2531987-11-20020 November 1987 Forwards Addl Info Re Geosciences Program for Resolution of Key Licensing Issues on Seismicity of Western Area of State of Wa,Per NRC 870708 Request.Responses to Seismic & Ground Motion Questions Will Be Submitted Soon ML20236Q4451987-10-28028 October 1987 Requests Supporting Documentation Providing Basis for OL Application Review Costs for Period of 860622-1220. Documentation & Verification Requirements for Public Fund Expenditures Exist Since WPPSS Is State Municipal Corp ML20236A8001987-10-0808 October 1987 Forwards Description of Status of Plant Seismic Review,Per Request.Meeting Will Be Requested W/Util to Resolve Audit Finding 1 Issue ML20235J8801987-09-30030 September 1987 Forwards Revised FSAR QA Program Description (Section 17.3) Re Organizational Realignments,Effective on 870701,per Util .Qa Program During Plant Asset Preservation Stage Discussed ML20237H6771987-08-19019 August 1987 Proposes to Defer Response to Generic Ltr 87-12 Re Loss of RHR While RCS Partially Filled Until After Const Restart, When Resources Will Be Available.Deferral Will Allow Util to Consider in Response Info Gained by NRC ML20237H4791987-08-0707 August 1987 Requests Response to Re NRC Billings for OL Review & Insp Fees ML20235B8211987-08-0707 August 1987 Requests That Sending of Unneeded Circular Info Be Discontinued.School No Longer Has Nuclear Reactor ML20236N3711987-07-31031 July 1987 Forwards Addl Info Re Soil Structure Interaction Deconvolution Issue,Per NRC 870417 Request ML20236F6121987-07-29029 July 1987 Responds to Request for Info Re NRC Bulletin 87-001, Thinning of Pipe Walls in Nuclear Power Plants. Util Not Able to Submit Info at Present Time Due to Const Delay.Const Activities Will Not Resume Before 1994 ML20237G3911987-07-20020 July 1987 Requests Supporting Documentation Providing Basis for NRC Billing & Operating License Reviews & Insp Fees for 850623 Through 860621 ML20235M4401987-06-25025 June 1987 Forwards EGG-NTA-7673, Conformance to Generic Ltr 83-28, Item 2.2.2--Vendor Interface Programs for All Other Safety- Related Components:WNP-1/-3, Final Informal Rept 1999-05-05
[Table view] Category:RESEARCH INSTITUTION/LABORATORY TO NRC
MONTHYEARML20150C4591988-01-13013 January 1988 Describes Basic Aspects of 871221 Meeting W/Util in Bethesda,Md Re Ssi/Deconvolution Issues Re Audit Finding 1 & Provides Recommendations for Resolving Associated Issues ML20236A8001987-10-0808 October 1987 Forwards Description of Status of Plant Seismic Review,Per Request.Meeting Will Be Requested W/Util to Resolve Audit Finding 1 Issue ML20153F1881986-02-0404 February 1986 Forwards Draft Readiness Review,Const Assurance Program Insp of Washington Nuclear Power,Unit 3. If Proposal Approved,Formal Approval Will Be Requested from Lab Mgt ML17276B0731982-02-10010 February 1982 Comments on Const of Two Power Reactors by Skagit/Hanford Nuclear Project at Hanford.Purchasing & Finishing Terminated Wppss Plants at Hanford & Satsop Should Be Considered as One Alternative to Proposed Action ML20098C8521976-03-26026 March 1976 Forwards Revised Concept Calculations Requested by Jc Petersen for Facilities & Results of Calculations 1988-01-13
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_ _. . -
- y. f N BROOKHAVEN NATIONAL LAB 6RATORY h, Q l ASSOCIATED UNIVERSITIES, INC. p4 Upton, Long Island. New York ii973 ")y.
(516) 282s '
i FT$ g y 2115 Departrnentof Nuc!eorEnergy f October 8,1987
.h R t Dr. Raman Pichumani facility Operation Branch g' Nail Stop P-1114 .g Phillips Building l U.S. Nuclear Ragulatory Commission 7920 Norfolk Avenue t Bethesda, MD 20814 !
Dear Raman:
i (1 In response to your request, enclosed please find a description of the .
1 status of the WNP-3 seismic review which is being carried out by BNL. Based on this description it should be apparent that at this time there is not a 1
.~
sufficient basis to conclude our review and prepara a TER. In order to complete our evaluation it is proposed to have a meeting with the utility.
The objaetive of the proposed meeting vill be to resolve the " Audit Finding No. 1" issue.
Sincerely youri, -
t -
Jo,4 A. Philippa'copoul.s AJPtkas ,
cet M.' Reich .
C. Costantino -
. P. Betler 8710230140 871014 PDR ADOCK 0500050s
,R PDR i
STATUS OF WP-3 REVIEW (FIN A-3850)-
1
)
The WP-3 Seismic Evaluation is based on a soil-structure interaction l
analysis which is described in Section .3.7 of the WP-3 PS AR. Specifically, l the SSI models are shown in Figures 3.7.2-1 and 3.7.2-2 and' art discussed in section 3.7.2.1.1 of the FSAR. The scil-structure interaction method used is )
of the finite eleaant type and it 'is referrad_ by the utility (WPP$$) to as finite elemer.t/boundarias approach. According to the latter, a deconvolution was performed '(by Ebasco) using the 5KAKE code from which the input at the bottom boundary of a finite element model of the rock-structure system was derived. This is a standard approach used widely to. perform soil-structure interaction ans. lysis. From a review of the results, however, the staff concluded that the deconvolution produced a reduction (over 351) in spectal accelerations at the base of the mat (difference between action at the surface and at the base). According to the staff such a reduction would not be expected for a rock site. This issue was termed as " Audit Finding No. 1". In order to resolve this issue, two options were proposed: i
- a. Perform a half-space analysis and apply seismic input directly at the [ ;
base
- b. Perform a fixed base analysis. 1-The utility chosen the first option. Specifically, a half-space analysis was performed which is documented in the following reports-WPPSS WP-3 "Saismic Dynamic Analysis Comparison of Pinite Boundaries Approach and Half-Space Approach", June 1984 Subsequent to the half-space avlysis by Ebasco,. an additional analysis
,1 g
was performed by the otility which is called " Owner's Astaysis". This' ~/ O analysis is documented in the following reports WPPSS WP-3: " Validation of Ebasco's Foundation Spring Modeling for Riastic flalf-Space $aismic Model", June 1906.
According to the utility, the " Owner's Analysis" was performed with the objective to fully resolve the " Audit Finding No. 1". Specifically, the utility recreated Ebasco's foundation model which was used to generate the foundation springs for the elastic half-space analysis. Using this model, the utility performed studies to validate the Ebasco's model. .
The objective of our review is to evaluate the adequacy of the utility's submittals reisted to their efforts to resolve the " Audit Finding No. 1". We reviewed the above two (i.e., June 1984 and June 1986) subaittals by the utilfty describing the half-space analysis and the validation studies for the Ebasco's foundstion springs. In order to proceed with our review, a request for additional information was prepared and send to NRC on February, 1987. We receive the response by WPPSS to our questions on August,1987. This information was subsequently reviewed. A list of comments with respect to this information is attached.
As can be seen from this attachment, although some items were resolved on the basis of the WPPS$'s submittal (kly 31,1987) there are still concerne -
which need further justification. There concerns are summarised belows I. Comparison of Finite Element Versus Halfspace Results: .
An important item which is needed in ord6e to resolve " Audit Finding No.
1" is the justification of the differences in floor response specta between finite element and half-space analyses. In the finite element celeulation which is the basis for the seismic design of WNP-3, the input at .
the base of the model was defined through a deconvolution procedure. On the
- . . , i
, l g ;
4p7 other hand, in the half space analysis the seismic input was applied directly ,
1 to the SSI model at the base. Comparisons of' floor spects at various buildings which were ma'de by WPPSS show significant differences in spectal accelerations. In certain frequency ranges tha finite element results envelopfthecorrespondinghalf-spaceresults. For exampis, the N-S, E-W and vertical floor response spectra obtained from the finics elemenc solution at ,
the top of the Shield Building envelope the corresponding results from tha :
f half-space analysis (Figures 8,9 and.10 of 1984 report). In this particular -l case the issue of deconvolution analysis is irrelevant since the seinie design basis _results apprear to be conservative as compared to the. corresponding i half-space results. However, this is not always the case as can be seen from stailar comparisons given by WFPSS for the top; of the Rasetor Auxiliary ~1 Building (Figures 11,12 and 13 of 1984 report), containment vessel / vertical compotent (Figure 16 of 1984 report) and other locations. In the June 1984 report the utility concludes that the half-space approach correlates well with l the finite element approach. This conclusion is not clear from the results obtained by WPP88 and needs further , justification.
II. Foundation Springs t! sed in the Ralf-Space Analysist As can be seen from our response to question No. 2 (attachment) the utility did act answer our questione retarding the foundation springe employed in the half-space analysis. Details pertinent to this issue were further amplified during our telecon with WPP88, following the submittal of the
- question.
l Based on the review performed so far for the WNP-3 it appears that in order to complete our evaluation and prepare a TER it will be necessary to have a meeting with the utility. The purpose of.this meeting will be to discuss and resolve the " Audit Finding No. 1" issur..
3
- a. : _ _ _
j 1
.. 4
,?
/ M. A n:: .u,f )
ATTAcIDatNT 1 l
l With respect to the information provided by the utility, the fo11oving j Comments hre Bade.
j 1
j Question No. ESI-1 l l
The data provided by the utility is satisfactory and show that the calculated shear strains are in teasonable agreement with the available ;
rock data.
Questio_n_No. SSI-2 s
- d. Themethodofanalysisusedtoobtainthesidavall. springs (itemd)is !
,, l incomplete. Specifically, fixing the bottoa modes of the finite element model does not ensure that the proper stiffnesses result. Since the structure is embedded, it is important to properly assess these I; I
parameters. ,
- a. No justification was provided for the choice of sidewall damping I i
parameters as requested in it.am e. The use of the shear asterial damping l to sieuinte sidewall compressive damping is inappropriate. 'j
- f. With respect to item f, it is not true that methodologies are not j available to treat this problem. Solutions for the rigid wall case -
sppsat to be reasonable for this. application.
- g. A similar response to item a was siven by the utility. j 1
)
q
i
~~~" ~
4 n
. rn
' sc, '*, sa f J
Question No.__S$1-3
- a. The applicant's response appears to have misunderstood the intent of the question. In the June 1984 report, the utility has presented data The comparing the finite element approach with the half-space approach.
intent of the question (as completed by telecon following submittal fo the question) was to explain differences in floor response spectra determined by the two methods. The applicant discussed the selection of the width for the finite element mesh used to determine sidewall springs for use in the half-space analaysis. The intent of the question is to speak to the applicability of deconvolution for the site.
- b. 34 solved.
- c. Essolved.
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