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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20100M3571996-02-26026 February 1996 Forwards Proprietary Documentation of Algebraic for of GE Critical Power Correlation.Ge Requests Concurrence Recognizing Attachment as Legal Documentation of GEXL & GEXL-PLUS Critical Quality Correlations ML20099F5851992-08-0404 August 1992 Clarifies Statement Made in NRC Safety Evaluation of Rept NEDE-31758P-A, GE Marathon Control Rod Assembly, W/ Regards to Stress Limit Used by Ge.Nrc Concurrence W/ Clarification Requested by 920930 ML20055E0691990-06-29029 June 1990 Forwards Synopsis of NRC Investigation Rept 03-87-011 Re Investigation Performed at Facility,For Info ML20235S9511989-02-25025 February 1989 Responds to NRC Bulletin 88-010, Test Program. Recommends That Temp Test Be Permitted as Alternate to Millivolt Drop/ Pole Resistance ML20235L1561989-01-17017 January 1989 Forwards Endorsements 141 & 142 to Nelia Policy NF-1, Endorsements 44 & 45 to Maelu Policy MF-95 & Endorsements 5 to Nelia Policy NW-1 & Maelu Policy MW-66 ML20155E1331988-06-0606 June 1988 Partial Response to FOIA Request for Documents.Forwards App B Documents.App a & B Documents Available in PDR ML20153B1541988-03-15015 March 1988 Informs of Relocation of NRR to Stated Address in Rockville, MD ML20235L6161987-09-25025 September 1987 Extends Invitation to Attend Region V 871110 Meeting in South San Francisco,Ca to Discuss NRC Reactor Operator Licensing Program.W/O Stated Encl ML20235M4251987-07-13013 July 1987 Partial Response to FOIA Request for Documents Re Acrs. Forwards Documents for Categories One & Three of FOIA Request.Review of 21 Addl ACRS Documents Continuing ML20234E4571987-06-23023 June 1987 Partial Response to FOIA Request for 771026 Minutes of ACRS Subcommittee on Fluid/Hydraulic Dynamic Effects Meeting in Portland,Or & Addl ACRS Documentation.Documents Identified on App H & Addl ACRS Documents Encl ML20207S5001987-03-0606 March 1987 Forwards Technical Evaluation Repts for Domestic Mark III Plants (Grand Gulf,Clinton,River Bend & Perry) & Gessar Ii. Inserts to Be Included in Section 6.2.1.8 of Draft Sser 2 for Clinton,River Bend & Perry Plants Also Encl IA-86-821, Final Response to FOIA Request Re GESSAR-II.App a Document Available in Pdr.App B Document Partially Withheld (Ref FOIA Exemption 4)1987-01-0909 January 1987 Final Response to FOIA Request Re GESSAR-II.App a Document Available in Pdr.App B Document Partially Withheld (Ref FOIA Exemption 4) ML20207M6941987-01-0909 January 1987 Final Response to FOIA Request Re GESSAR-II.App a Document Available in Pdr.App B Document Partially Withheld (Ref FOIA Exemption 4) ML20207M6741986-11-17017 November 1986 FOIA Request for GESSAR-II Chapters on Human Factors & Engineering & GESSAR-II Probabilistic Safety Study ML20210J3961986-09-22022 September 1986 Forwards Amend 2 to Final Design Approval FDA-1 for BWR/6 Nuclear Island Design (GESSAR-II) & Notice of Issuance of Amend.Amend Removes Constraints on Issuing CPs & OLs to Applicants Ref GESSAR-II Design NUREG-0979, Forwards Sser 5,(NUREG-0979).W/o Encl1986-06-25025 June 1986 Forwards Sser 5,(NUREG-0979).W/o Encl ML20211K8171986-06-17017 June 1986 Proposes Final Design Approval (Fda) Conditions 3-6 Be Treated as Interface Items & Removed from Amend 2 to FDA-1. Action on Condition 1 Should Be Taken by Nrc,Not GE ML20199D5321986-06-11011 June 1986 Forwards Proposed Amend 2 to Final Design Approval-1 for BWR/6 Nuclear Island Design,Gessar Ii,Documenting Staff & ACRS Review of Gessar II for Severe Accident Concerns,For Comment.Amend Removes Constraints on Issuance of CPs & OLs ML20155G0971986-04-25025 April 1986 Forwards Nonproprietary & Proprietery Amend 21 to Gessar II,238 Nuclear Island. Amend Responds to NRC Proposed Severe Accident Policy Statement.Proprietary Amend Withheld (Ref 10CFR2.790) ML20137L4871986-01-22022 January 1986 Forwards,For Info & Comment,Acrs Rept Re Review of GESSAR-II for Concerns Addressed in Commission Severe Accident Policy Statement.Comments Requested by 860204 ML20137H8641986-01-14014 January 1986 Disagrees W/Nrc Re Final Design Approval of Gessar II BWR/6 Nuclear Island Design Applicable to Future Plants.Design Does Not Satisfy All Concerns of Commission Severe Accident Policy Statement.W/Addl Comments by ACRS Members ML20140F3691986-01-14014 January 1986 Further Response to FOIA Request for Several Categories of Documents Re Pressure Suppression Containment.Fsar & SER for Limerick Only Documentation Re 4x4 Tests.Encl Apps D-G Documents Responsive to Item 4 Also Available in PDR ML20154A6611986-01-13013 January 1986 Responds to FOIA Request for Specified Documents to Be Placed in Pdr.Encl App a Documents & Listed App B Document Placed in Pdr.Portions of Document 2 on App a Withheld (Ref FOIA Exemption 4) IA-85-804, Responds to FOIA Request for Specified Documents to Be Placed in Pdr.Encl App a Documents & Listed App B Document Placed in Pdr.Portions of Document 2 on App a Withheld (Ref FOIA Exemption 4)1986-01-13013 January 1986 Responds to FOIA Request for Specified Documents to Be Placed in Pdr.Encl App a Documents & Listed App B Document Placed in Pdr.Portions of Document 2 on App a Withheld (Ref FOIA Exemption 4) ML20209H4261985-10-30030 October 1985 Forwards marked-up Proprietary Review of BWR/6 Std Plant Pra:Vol 2:Seismic Events...Analysis in Response to 851009 Request.Technical Error Identified on Encl Pages 6/3 & 6/4. Review Withheld IA-84-175, Responds to Appeal Re Denial of FOIA Request for GE PRA for GESSAR-II Standardized Plant Design.Forwards 11 Pages from PRA Due to Court Approved Stipulation of 850718 Settlement. Info Also Available in PDR1985-10-11011 October 1985 Responds to Appeal Re Denial of FOIA Request for GE PRA for GESSAR-II Standardized Plant Design.Forwards 11 Pages from PRA Due to Court Approved Stipulation of 850718 Settlement. Info Also Available in PDR ML20133J3821985-10-11011 October 1985 Responds to Appeal Re Denial of FOIA Request for GE PRA for GESSAR-II Standardized Plant Design.Forwards 11 Pages from PRA Due to Court Approved Stipulation of 850718 Settlement. Info Also Available in PDR ML20135B7601985-09-0505 September 1985 Ack Receipt of 850806 Memo Re ACRS Severe Accident Review. NRR Ltr to ACRS Endorsed.Acrs Review Completion Expected by Sept or Oct 1985 Meeting ML20133N9891985-08-12012 August 1985 Forwards Proprietary Suppl 1 to Draft Gessar II Amend Supporting Leak-Before-Break. Submittal Based on Recommendations of NUREG-1061,Vol 3 for leak-before-break Mechanistic Methodology.Suppl Withheld (Ref 10CFR2.790) ML20134A5511985-08-0909 August 1985 Forwards Amend 1 to Final Design Approval FDA-1 & Fr Notice of Issuance.Amend Removes Constraint on Forward Referenceability of GESSAR-II Design & Permits Ref in New CP & OL Applications ML20133L5951985-08-0606 August 1985 Expresses Concern Over Progress of Severe Accident Review of Design.Requests That Steps Be Taken to Complete Review on Schedule That Would Result in Ltr to Commission in Sept 1985 ML20128H3171985-06-28028 June 1985 Forwards NRR Sser 4 Re Severe Accident Design.Severe Chatter Issue Will Be Resolved Prior to Publishing Final Suppl.W/O Encl ML20129B7391985-06-25025 June 1985 Advises of Review of Proposed SERs for Proprietary Info,Per 850618 Request.Page 3 of Ref 3, Table 2:Conditional Consequences Predicted by GE for Internally Initiated Events... Classified as Proprietary ML20128Q6981985-06-19019 June 1985 Responds to FOIA Request for from GG Sherwood to Hl Thompson on Review of Leak-Before-Break Approach on Gessar II Docket. Forwards Document IA-85-412, Responds to FOIA Request for 850404 Ltr from GG Sherwood to Hl Thompson on Review of Leak-Before-Break Approach on Gessar II Docket. Forwards Document1985-06-19019 June 1985 Responds to FOIA Request for 850404 Ltr from GG Sherwood to Hl Thompson on Review of Leak-Before-Break Approach on Gessar II Docket. Forwards Document ML20126B8981985-06-10010 June 1985 Forwards Info Re Resolution of Open Item Concerning Clutter on GE Emergency Response Info Sys.Ge Will Display Changes Recommended by Human Factors Consultant,Anacapa Sciences,Inc & NRC ML20126F4911985-06-0707 June 1985 Forwards Proposed Amend 1 to FDA-1 for GESSAR-II BWR/6 Nuclear Island Design,For Review.Amend Prepared in Anticipation of Final Commission Action on Severe Accident Policy Statement.Comments Requested by 850614 ML20128Q6731985-06-0606 June 1985 FOIA Request for GG Sherwood to Hl Thompson on Review of Leak-Before-Break on Gessar II Docket ML20117K0761985-05-0909 May 1985 Forwards Anacapa Technical Rept TR-550-1, Human Factors & Performance Evaluations of Emergency Response Info Sys. Rept Should Resolve Questions Raised by NRC Re Amount of Info Contained in Gessar Displays.W/O Encl ML20117H5241985-05-0707 May 1985 Permits NRC to Reproduce,Furnish to Third Parties & Make Public Rept NEDC-30885, Generic Emergency Response Info Sys (Basic Rtad) Software Validation ML20133A2391985-05-0303 May 1985 Further Response to FOIA Appeal & Ucs Motion for Summary Judgement That 10 Categories of Info in GESSAR-II PRA Could Be Released.No Basis Found to Recommend Reversal of Determination.Documents Released by GE Encl ML20154A6791985-05-0202 May 1985 Forwards NUREG/CR-4135 P, Review of BWR/6 Std Plant PRA: Vol-1 Internal Events,Core Damage Frequency. Task 12 of GESSAR-II Review Project Complete ML20116M0941985-05-0101 May 1985 Submits Supplemental Info Re Concerning Addendum 1 to NEDO-10466, Power Generation Control Complex (Pgcc) Fire Suppression Licensing Topical Rept. Establishment of Halon Concentration Requirement for Control Room Discussed ML20116E5961985-04-26026 April 1985 Forwards Proprietary Updated Draft Gessar II Amend Supporting Leak-Before-Break. Submittal for Carbon Steel Piping Scheduled for 850618.Rept Withheld (Ref 10CFR2.790) ML20126J0841985-04-19019 April 1985 Responds to Appeal Re Denial of FOIA Request for GESSAR-II Pra.Forwards Pages 2-7 - 2-16 of Document 5 on App A. Portions Withheld (Ref FOIA Exemption 4) ML20117J5801985-04-17017 April 1985 Forwards NEDC-30885, Generic Emergency Response Info Sys (Basic Rtad) Software Validation, Re Program to Evaluate & Test Integrated Software,Data Bases & Command Files Associated W/Emergency Response Info Sys NUREG-0770, Partial Response to FOIA Request for Four Categories of Documents Re APS Source Term Review.Forwards Documents in App A.App B Documents Available in Pdr.App a Documents Being Placed in PDR1985-04-15015 April 1985 Partial Response to FOIA Request for Four Categories of Documents Re APS Source Term Review.Forwards Documents in App A.App B Documents Available in Pdr.App a Documents Being Placed in PDR ML20128M6211985-04-15015 April 1985 Partial Response to FOIA Request for Four Categories of Documents Re APS Source Term Review.Forwards Documents in App A.App B Documents Available in Pdr.App a Documents Being Placed in PDR ML20126C4481985-04-0404 April 1985 Advises of Preparations to Update & Resubmit Draft Amend Supporting leak-before-break Approach to Achieve Consistency W/Vol 3 of NUREG-1061 ML20126E0031985-04-0404 April 1985 Further Response to Appeal Re Partial Denial of FOIA Request for Documents Re GE PRA for GESSAR-II Standardized Plant Design.App Lists Documents Responsive to Request 1996-02-26
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20100M3571996-02-26026 February 1996 Forwards Proprietary Documentation of Algebraic for of GE Critical Power Correlation.Ge Requests Concurrence Recognizing Attachment as Legal Documentation of GEXL & GEXL-PLUS Critical Quality Correlations ML20099F5851992-08-0404 August 1992 Clarifies Statement Made in NRC Safety Evaluation of Rept NEDE-31758P-A, GE Marathon Control Rod Assembly, W/ Regards to Stress Limit Used by Ge.Nrc Concurrence W/ Clarification Requested by 920930 ML20235S9511989-02-25025 February 1989 Responds to NRC Bulletin 88-010, Test Program. Recommends That Temp Test Be Permitted as Alternate to Millivolt Drop/ Pole Resistance ML20235L1561989-01-17017 January 1989 Forwards Endorsements 141 & 142 to Nelia Policy NF-1, Endorsements 44 & 45 to Maelu Policy MF-95 & Endorsements 5 to Nelia Policy NW-1 & Maelu Policy MW-66 ML20207S5001987-03-0606 March 1987 Forwards Technical Evaluation Repts for Domestic Mark III Plants (Grand Gulf,Clinton,River Bend & Perry) & Gessar Ii. Inserts to Be Included in Section 6.2.1.8 of Draft Sser 2 for Clinton,River Bend & Perry Plants Also Encl ML20207M6741986-11-17017 November 1986 FOIA Request for GESSAR-II Chapters on Human Factors & Engineering & GESSAR-II Probabilistic Safety Study ML20211K8171986-06-17017 June 1986 Proposes Final Design Approval (Fda) Conditions 3-6 Be Treated as Interface Items & Removed from Amend 2 to FDA-1. Action on Condition 1 Should Be Taken by Nrc,Not GE ML20155G0971986-04-25025 April 1986 Forwards Nonproprietary & Proprietery Amend 21 to Gessar II,238 Nuclear Island. Amend Responds to NRC Proposed Severe Accident Policy Statement.Proprietary Amend Withheld (Ref 10CFR2.790) ML20209H4261985-10-30030 October 1985 Forwards marked-up Proprietary Review of BWR/6 Std Plant Pra:Vol 2:Seismic Events...Analysis in Response to 851009 Request.Technical Error Identified on Encl Pages 6/3 & 6/4. Review Withheld ML20135B7601985-09-0505 September 1985 Ack Receipt of 850806 Memo Re ACRS Severe Accident Review. NRR Ltr to ACRS Endorsed.Acrs Review Completion Expected by Sept or Oct 1985 Meeting ML20133N9891985-08-12012 August 1985 Forwards Proprietary Suppl 1 to Draft Gessar II Amend Supporting Leak-Before-Break. Submittal Based on Recommendations of NUREG-1061,Vol 3 for leak-before-break Mechanistic Methodology.Suppl Withheld (Ref 10CFR2.790) ML20129B7391985-06-25025 June 1985 Advises of Review of Proposed SERs for Proprietary Info,Per 850618 Request.Page 3 of Ref 3, Table 2:Conditional Consequences Predicted by GE for Internally Initiated Events... Classified as Proprietary ML20126B8981985-06-10010 June 1985 Forwards Info Re Resolution of Open Item Concerning Clutter on GE Emergency Response Info Sys.Ge Will Display Changes Recommended by Human Factors Consultant,Anacapa Sciences,Inc & NRC ML20128Q6731985-06-0606 June 1985 FOIA Request for GG Sherwood to Hl Thompson on Review of Leak-Before-Break on Gessar II Docket ML20117K0761985-05-0909 May 1985 Forwards Anacapa Technical Rept TR-550-1, Human Factors & Performance Evaluations of Emergency Response Info Sys. Rept Should Resolve Questions Raised by NRC Re Amount of Info Contained in Gessar Displays.W/O Encl ML20117H5241985-05-0707 May 1985 Permits NRC to Reproduce,Furnish to Third Parties & Make Public Rept NEDC-30885, Generic Emergency Response Info Sys (Basic Rtad) Software Validation ML20154A6791985-05-0202 May 1985 Forwards NUREG/CR-4135 P, Review of BWR/6 Std Plant PRA: Vol-1 Internal Events,Core Damage Frequency. Task 12 of GESSAR-II Review Project Complete ML20116M0941985-05-0101 May 1985 Submits Supplemental Info Re Concerning Addendum 1 to NEDO-10466, Power Generation Control Complex (Pgcc) Fire Suppression Licensing Topical Rept. Establishment of Halon Concentration Requirement for Control Room Discussed ML20116E5961985-04-26026 April 1985 Forwards Proprietary Updated Draft Gessar II Amend Supporting Leak-Before-Break. Submittal for Carbon Steel Piping Scheduled for 850618.Rept Withheld (Ref 10CFR2.790) ML20117J5801985-04-17017 April 1985 Forwards NEDC-30885, Generic Emergency Response Info Sys (Basic Rtad) Software Validation, Re Program to Evaluate & Test Integrated Software,Data Bases & Command Files Associated W/Emergency Response Info Sys ML20126C4481985-04-0404 April 1985 Advises of Preparations to Update & Resubmit Draft Amend Supporting leak-before-break Approach to Achieve Consistency W/Vol 3 of NUREG-1061 ML20113A8501985-04-0404 April 1985 Forwards Application Fees for Amends 10 & 11 to Gessar II Topical Rept NEDE-24011-P-A-6 ML20108F2501985-02-28028 February 1985 Forwards Addendum 1 to NEDO-10466, Power Generation Control Complex Design Criteria & Safety Evaluation. Addl Halon Concentration & Soak Time Option for Fire Suppression Sys Documented.Fee Paid ML20107G0471985-02-0808 February 1985 Provides Supplemental Info Re Capability of Ultimate Plant Protection Sys.Capability of Sys to Provide Makeup to Suppression Pool Discussed ML20106H7161985-02-0505 February 1985 Forwards Comments on R&D Assoc Rept Re Potential Design Mods.Response to Issues Identified in Sser 3 on Seismic Events Relative to Pool Bypass Sequences Encl.Proprietary Info Withheld (Ref 10CFR2.790).W/affidavit ML20101G3351984-12-20020 December 1984 Submits Addl Info Re Gessar II Spds,Per NRC Request.Info Re Display Clutter & Reliability Analysis Submitted ML20101D4061984-12-10010 December 1984 Forwards Rev 21 to App a of Response 3.84 Re Gessar, Concerning Calculations & Assumptions for Auxiliary & Control Bldg Sliding Stability Analysis ML20100R6901984-12-0303 December 1984 Forwards Proprietary Containment Pressure Carrying Capability Study & Responses to Informal Questions on Design Mods.Encls Withheld (Ref 10CFR2.790) ML20093M5711984-10-0404 October 1984 Informs of Necessity to Close Portions of ACRS Subcommittee on GESSAR-II Meetings to Accommodate Discussions of GE Proprietary Info ML20095D0651984-08-20020 August 1984 Forwards Draft Amend to Gessar II Sections 1G.12 & 1G.21,in Response to 10CFR50.34(f),Items (1)(xii) & (2)(ix) Re Evaluation of Alternate Hydrogen Control Sys (HCS) & HCS Preliminary Design,Respectively ML20095F0441984-08-10010 August 1984 Requests Exemption to Revise 10CFR170 License Fee Schedule Re Gessar II Review.Exemption to Schedule Appropriate Since Review of Gessar II Design Committed Under Regulations & Policies in Existence in Early 1982 ML20107K8951984-08-0606 August 1984 Appeals Denial of FOIA Request for PRA for GESSAR-II,NRC Reviews of PRA & Identification of Reviewing Organizations & Contract Details.Complete Disclosure or Justification for Deletion of Minor Portions of Document Requested ML20106C7751984-08-0606 August 1984 Appeals Denial of FOIA Request for Documents Re PRA for GESSAR-II Standardized Plant Design ML20093F5291984-07-13013 July 1984 Forwards NEDO-30670, Resolution of Applicable Unresolved Safety Issues & Generic Issues for Gessar II, Providing Technical Resolution of Issues ML20093F5561984-07-13013 July 1984 Forwards Info Re Nuclear Island/Balance of Plant Interfaces, Including Interface Assumptions in PRA & Documentation of Gessar II Design Evolution,Per DC Scaletti 840607 Memo Re Closure Activities for Severe Accident Review ML20090E1371984-07-12012 July 1984 Forwards Gessar II External Event Risk, Providing Qualitative Assessment of Risk from Hurricanes,Tornados, External Floods,Aircraft Strike & Hazardous Matls,Per NRC 840607 Request ML20090E2561984-07-11011 July 1984 Forwards Containment Structural Analysis Plan to Support Conclusions Reached in App G to PRA on Containment Failure Mode & Pressure,Per 840626-27 Meetings ML20094B4451984-07-0505 July 1984 Informs of Difficulty in Obtaining Scheduling Info Re Ge/Nrc Meetings Concerning GESSAR-II.All Applicant/Nrc Meetings Should Be Announced 10 Days in Advance by Posting Notices in PDR & Including Notices in NRC Tapes ML20092K0761984-06-21021 June 1984 Forwards Proprietary, Evaluation of Proposed Mods to Gessar II Design, in Response to NRC 840413 Request for Addl Info Re Severe Accident Review.Affidavit Requesting Info Be Withheld (Ref 10CFR2.790) Also Encl.Rept Withheld ML20091J8951984-06-0404 June 1984 Requests That NRC Schedule No Further Meetings W/Ge Re Gessar II Until Public Attendance Can Be Accommodated by Acceptable Proprietary Nondisclosure Form.Form Offered at 840524 Meeting Covered Matl Beyond Info Learned by Author ML20197G7461984-05-30030 May 1984 Forwards Response to Vendor Commitment in SER (NUREG-0979), Section 7.2.2.2 Re Design Verification Testing of Optical Isolators.Individual Failure of Card or Component Can at Most,Affect Only Equipment within Same Chamber ML20091R6771984-05-30030 May 1984 Forwards Response to Commitment in SER,NUREG-0979,Section 7.2.2.2 Re Design Verification Testing of Optical Isolators ML20091J8741984-05-14014 May 1984 Requests Help in Expediting Attendance at Future GE-NRC Meetings Re Gessar.Ge Nondisclosure Form Overly Restrictive & Caused Inconvenience During 840501 Meeting.Std Nondisclosure Form Should Be Devised.W/O Encl ML20084F0781984-04-20020 April 1984 Forwards Proprietary Responses to 840126 Request for Addl Info Re Severe Accident Review & Rationale for Treatment of Fire & Flood Event Uncertainty Analysis.Affidavit Encl. Response & Rationale Withheld (Ref 10CFR2.790) ML20084F0511984-04-20020 April 1984 Forwards Proprietary Responses to NRC Request for Addl Info Re Severe Accident Portion of GE Gessar II Submittal.Encl Withheld (Ref 10CFR2.790) ML20084E8941984-04-20020 April 1984 Responds to Co Thomas 840413 Request for Addl Info Re Severe Accident Review.Design Mods Will Be Evaluated Per NUREG/CR-3385, Measures of Risk Importance & Applications. Draft Rept Expected by Mid Apr ML20084M4471984-04-17017 April 1984 Requests Assistance in Obtaining Permit to Attend GE-NRC Meetings Re Accident Source Term Evaluation for Gessar PRA Considered Proprietary.Disclosure Form Would Prohibit Divulging Any Info Discussed in Meetings ML20099J7331984-04-0505 April 1984 Appeals Denial of FOIA Request for Info Re GESAR-II PRA ML20105D2831984-03-29029 March 1984 FOIA Request for Three Categories of Documents Re NRC Meetings W/Ge on 840209,22,28 & 0320 Concerning Facility ML20084R6311984-03-29029 March 1984 FOIA Request for Four Categories of Documents Re SER on GESSAR-II Severe Accident Evaluation 1996-02-26
[Table view] Category:VENDOR/MANUFACTURER TO NRC
MONTHYEARML20235S9511989-02-25025 February 1989 Responds to NRC Bulletin 88-010, Test Program. Recommends That Temp Test Be Permitted as Alternate to Millivolt Drop/ Pole Resistance ML20211K8171986-06-17017 June 1986 Proposes Final Design Approval (Fda) Conditions 3-6 Be Treated as Interface Items & Removed from Amend 2 to FDA-1. Action on Condition 1 Should Be Taken by Nrc,Not GE ML20155G0971986-04-25025 April 1986 Forwards Nonproprietary & Proprietery Amend 21 to Gessar II,238 Nuclear Island. Amend Responds to NRC Proposed Severe Accident Policy Statement.Proprietary Amend Withheld (Ref 10CFR2.790) ML20209H4261985-10-30030 October 1985 Forwards marked-up Proprietary Review of BWR/6 Std Plant Pra:Vol 2:Seismic Events...Analysis in Response to 851009 Request.Technical Error Identified on Encl Pages 6/3 & 6/4. Review Withheld ML20135B7601985-09-0505 September 1985 Ack Receipt of 850806 Memo Re ACRS Severe Accident Review. NRR Ltr to ACRS Endorsed.Acrs Review Completion Expected by Sept or Oct 1985 Meeting ML20133N9891985-08-12012 August 1985 Forwards Proprietary Suppl 1 to Draft Gessar II Amend Supporting Leak-Before-Break. Submittal Based on Recommendations of NUREG-1061,Vol 3 for leak-before-break Mechanistic Methodology.Suppl Withheld (Ref 10CFR2.790) ML20129B7391985-06-25025 June 1985 Advises of Review of Proposed SERs for Proprietary Info,Per 850618 Request.Page 3 of Ref 3, Table 2:Conditional Consequences Predicted by GE for Internally Initiated Events... Classified as Proprietary ML20126B8981985-06-10010 June 1985 Forwards Info Re Resolution of Open Item Concerning Clutter on GE Emergency Response Info Sys.Ge Will Display Changes Recommended by Human Factors Consultant,Anacapa Sciences,Inc & NRC ML20117K0761985-05-0909 May 1985 Forwards Anacapa Technical Rept TR-550-1, Human Factors & Performance Evaluations of Emergency Response Info Sys. Rept Should Resolve Questions Raised by NRC Re Amount of Info Contained in Gessar Displays.W/O Encl ML20117H5241985-05-0707 May 1985 Permits NRC to Reproduce,Furnish to Third Parties & Make Public Rept NEDC-30885, Generic Emergency Response Info Sys (Basic Rtad) Software Validation ML20116E5961985-04-26026 April 1985 Forwards Proprietary Updated Draft Gessar II Amend Supporting Leak-Before-Break. Submittal for Carbon Steel Piping Scheduled for 850618.Rept Withheld (Ref 10CFR2.790) ML20117J5801985-04-17017 April 1985 Forwards NEDC-30885, Generic Emergency Response Info Sys (Basic Rtad) Software Validation, Re Program to Evaluate & Test Integrated Software,Data Bases & Command Files Associated W/Emergency Response Info Sys ML20126C4481985-04-0404 April 1985 Advises of Preparations to Update & Resubmit Draft Amend Supporting leak-before-break Approach to Achieve Consistency W/Vol 3 of NUREG-1061 ML20113A8501985-04-0404 April 1985 Forwards Application Fees for Amends 10 & 11 to Gessar II Topical Rept NEDE-24011-P-A-6 ML20108F2501985-02-28028 February 1985 Forwards Addendum 1 to NEDO-10466, Power Generation Control Complex Design Criteria & Safety Evaluation. Addl Halon Concentration & Soak Time Option for Fire Suppression Sys Documented.Fee Paid ML20107G0471985-02-0808 February 1985 Provides Supplemental Info Re Capability of Ultimate Plant Protection Sys.Capability of Sys to Provide Makeup to Suppression Pool Discussed ML20106H7161985-02-0505 February 1985 Forwards Comments on R&D Assoc Rept Re Potential Design Mods.Response to Issues Identified in Sser 3 on Seismic Events Relative to Pool Bypass Sequences Encl.Proprietary Info Withheld (Ref 10CFR2.790).W/affidavit ML20101G3351984-12-20020 December 1984 Submits Addl Info Re Gessar II Spds,Per NRC Request.Info Re Display Clutter & Reliability Analysis Submitted ML20101D4061984-12-10010 December 1984 Forwards Rev 21 to App a of Response 3.84 Re Gessar, Concerning Calculations & Assumptions for Auxiliary & Control Bldg Sliding Stability Analysis ML20100R6901984-12-0303 December 1984 Forwards Proprietary Containment Pressure Carrying Capability Study & Responses to Informal Questions on Design Mods.Encls Withheld (Ref 10CFR2.790) ML20093M5711984-10-0404 October 1984 Informs of Necessity to Close Portions of ACRS Subcommittee on GESSAR-II Meetings to Accommodate Discussions of GE Proprietary Info ML20095D0651984-08-20020 August 1984 Forwards Draft Amend to Gessar II Sections 1G.12 & 1G.21,in Response to 10CFR50.34(f),Items (1)(xii) & (2)(ix) Re Evaluation of Alternate Hydrogen Control Sys (HCS) & HCS Preliminary Design,Respectively ML20093F5291984-07-13013 July 1984 Forwards NEDO-30670, Resolution of Applicable Unresolved Safety Issues & Generic Issues for Gessar II, Providing Technical Resolution of Issues ML20093F5561984-07-13013 July 1984 Forwards Info Re Nuclear Island/Balance of Plant Interfaces, Including Interface Assumptions in PRA & Documentation of Gessar II Design Evolution,Per DC Scaletti 840607 Memo Re Closure Activities for Severe Accident Review ML20090E1371984-07-12012 July 1984 Forwards Gessar II External Event Risk, Providing Qualitative Assessment of Risk from Hurricanes,Tornados, External Floods,Aircraft Strike & Hazardous Matls,Per NRC 840607 Request ML20090E2561984-07-11011 July 1984 Forwards Containment Structural Analysis Plan to Support Conclusions Reached in App G to PRA on Containment Failure Mode & Pressure,Per 840626-27 Meetings ML20092K0761984-06-21021 June 1984 Forwards Proprietary, Evaluation of Proposed Mods to Gessar II Design, in Response to NRC 840413 Request for Addl Info Re Severe Accident Review.Affidavit Requesting Info Be Withheld (Ref 10CFR2.790) Also Encl.Rept Withheld ML20197G7461984-05-30030 May 1984 Forwards Response to Vendor Commitment in SER (NUREG-0979), Section 7.2.2.2 Re Design Verification Testing of Optical Isolators.Individual Failure of Card or Component Can at Most,Affect Only Equipment within Same Chamber ML20091R6771984-05-30030 May 1984 Forwards Response to Commitment in SER,NUREG-0979,Section 7.2.2.2 Re Design Verification Testing of Optical Isolators ML20084E8941984-04-20020 April 1984 Responds to Co Thomas 840413 Request for Addl Info Re Severe Accident Review.Design Mods Will Be Evaluated Per NUREG/CR-3385, Measures of Risk Importance & Applications. Draft Rept Expected by Mid Apr ML20084F0511984-04-20020 April 1984 Forwards Proprietary Responses to NRC Request for Addl Info Re Severe Accident Portion of GE Gessar II Submittal.Encl Withheld (Ref 10CFR2.790) ML20084F0781984-04-20020 April 1984 Forwards Proprietary Responses to 840126 Request for Addl Info Re Severe Accident Review & Rationale for Treatment of Fire & Flood Event Uncertainty Analysis.Affidavit Encl. Response & Rationale Withheld (Ref 10CFR2.790) ML20112F9301984-03-13013 March 1984 Discusses Action Plan Proposed at 840222 Meeting for Consideration of Source Term Issues as Part of Gessar II Severe Accident Review.Series of Sensitivity Studies to Be Performed on Parameters Affecting Containment Failure Modes ML20086L2581984-02-0101 February 1984 Forwards Proprietary Response to NRC 840126 Request for Addl Info Re Severe Accident Review of Gessar Ii.Rationale for Treatment of Fire & Flood Event Uncertainty Analysis & Affidavit Requesting Info Be Withheld (Ref 10CFR2.790) Encl ML20079R6741984-01-31031 January 1984 Forwards Proprietary Draft Amend to Gessar Ii,Supporting Leak Before Break Approach.Submittal Extends Leak Before Break Approach Only to Recirculation Sys Piping.Affidavit Encl.Rept Withheld (Ref 10CFR2.790) ML20079K1441984-01-19019 January 1984 Forwards Proprietary Info Supporting Gessar II Seismic Fragility Analysis Requested at 840109 & 10 Meetings in San Jose,Ca.Info Withheld (Ref 10CFR2.790) ML20086G3601983-12-29029 December 1983 Forwards Proprietary Draft Gessar II Seismic Event Uncertainty Analysis. Formal Amend Will Be Submitted in Early 1984.Draft Rept Withheld (Ref 10CFR2.790).Affidavit Encl ML20082M8081983-12-0505 December 1983 Forwards marked-up Draft App 15E,Station Blackout Capability, Concluding That Station Blackout Capability Exceeds 10 H.Formal Amend Will Be Submitted in Early 1984, Upon Completion of NRC Review ML20082E5371983-11-17017 November 1983 Forwards Proprietary Gessar II Internal Event PRA Uncertainty Analysis, in Support of Severe Accident Review, in Response to PRA Question 720.143.Rept Withheld (Ref 10CFR2.790) ML20086A7091983-11-0707 November 1983 Forwards Proprietary Gessar II Fire & Flood External Event Analysis, in Response to NRC Draft Policy Statement on Severe Accidents.Affidavit Encl.Rept Withheld (Ref 10CFR2.790) ML20081A2731983-10-0404 October 1983 Forwards Amend 20 to GESSAR-II,responding to Confirmatory Issue 18 of Ser,Suppl 1 to NUREG-0979,revised Responses to NRC Re Communication & Lighting Sys & Updating Interface Tables of Subsection 1.9.1 ML20080U5471983-10-0404 October 1983 Forwards Proprietary Rev 20 to GESSAR-II Re Environ Qualification of safety-related Equipment.Rev Should Be Withheld (Ref 10CFR2.790).Affidavit Encl ML20080K7641983-09-21021 September 1983 Forwards Proprietary GESSAR-II Seismic Event Analysis, in Response to NRC Draft Policy Statement on Severe Accidents. Analysis Withheld (Ref 10CFR2.790) ML20080H2541983-09-14014 September 1983 Forwards Proprietary Response to NRC 830902 Request for Addl Info Re Severe Accident Portion of Gessar Ii.Responses to Questions 720.98,720.99,720.100 & 720.101 Will Be Provided by 831015.Response Withheld (Ref 10CFR2.790) ML20076L4421983-09-0909 September 1983 Forwards Supplemental Containment Vessel Dimensions Needed for BNL to Conduct Review of GESSAR-II PRA Re Containment Structural Sys pressure-carrying Assessment ML20076F4731983-08-22022 August 1983 Informs That GESSAR-II Drywell Structure Drawings Requested by BNL Transmitted to M Reisch.Drawings Will Be Used in Review of PRA Re Containment Structural Sys pressure- Carrying Capacity ML20080C1041983-08-17017 August 1983 Forwards Impell Corp two-vol Rept, Confirmatory Soil- Structure Interaction Analysis for GESSAR-II, in Response to SER Confirmatory Issue 3.Rept Will Be Incorporated Into GESSAR-II by Amend ML20080A8541983-07-26026 July 1983 Forwards GESSAR-II Responses to Action Plan for Resolving Containment Design Issues,In Response to . Affidavit for Withholding Proprietary Info Encl.Portions Withheld ML20077G7161983-07-22022 July 1983 Forwards Nonproprietary Amend 19 to GESSAR-II,updating Section 3.11 on Environ Qualification & Responding to Outstanding Issue 3 to Gessar II SER,NUREG-0979 ML20077G5221983-07-22022 July 1983 Forwards Proprietary Amend 19 to GESSAR-II Re Human Factors. Discussion of Methodology GE Will Employ to Environmentally Qualify safety-related Equipment Provided.Affidavit for Withholding Info (Ref 10CFR2.790) Encl 1989-02-25
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GENER AL $ ELECTRIC uucteAn POwen SYSTEMS DIVISION GENERAL ELECTRIC COMPANY,175 CURTNER AVE., SAN JOSE, CAUFORNIA 95125 NFN 070-83 (408) 925-5722 M/C 682 JNF 025-83 April 15, 1983 U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Washington, DC 20555 Attention: Mr. D.G. Eisenhut Division of Licensing Gentlemen:
SUBJECT:
IN THE MATTER OF 238 NUCLEAR ISLAND GENERAL ELECTRIC STANDARD SAFETY ANALYSIS REPORT (GESSAR II) DOCKET NO. STN 50-447 RESULUTION OF OUTSTANDING ISSUES Attached please find proposed resolutions to selected outstanding issues.
This inforraation is provided in the following attachments:
Attachment Number Branch 1 Chemical Engineering 2 Containment Systems 3 Materials Engineering 4 Structural & Geotecnnical Engineering Sincerel;,,
d Glenn G. Sherwood, Manager Nuclear 'afety & Licensing Operation Attachment.
cc: F.J. iiiraglia (w/o attachments) C.O. Thomas (w/o attachments)
D.C. Scaletti L.S. Gifford (w/o attachments)
/
p'od B30'1190446 830415 PDR ADDCK 05000447 A PDR
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ATTACHMENT NO. 1 PROPOSED RESOLUTION OF CHEMICAL ENGINEERING BRANCH OUTSTANDING ISSUE 15 l
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l Discussiodtem 9 /
Smoke tectors will added to ti air intakes r the control 11 ding.
This 11 resolve scussion item .
scussion I 6 i
Discussio item 6 is an N staff action tem concerning he shu'tdown capabil y. Since the SAR II desig will have redun ant m mote shutd
- capab ity which meets he requirene for fire sepa tion, no future neerns are xpecthd. 1 j .f t Discussion Ite 4 and 7 NP
- : % ^s-ot .O00=9..sk sfire d dampers
' s su < cm c.t.veJ in ventilation ducts used for smoke r
venting. Some of these ventilation ducts are shared systems in that they '
- also provide normal ventilation. Other ducts are for smoke venting only.
Based on the discussion below the present ESSAR II design should be adequate and should be acceptable to the NRC. so that it: : ' e4 ' should be resolved.
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The auxiliary building smoke removal system is shown on Figure 9.4-4 and
- described in Section 9.4.3.2.1.11. Each set of duct work serves and traverses only fire areas of one afety division. There is a smoke vent intake in each l fire area with a remote manually operated fire damper which is normally closed.
There .is a fusible link from the air operator to the vanes so that the damper
, will close on high temperature. The fire rating of the dampers is 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br />.
The duct is heavy gage, welded construction which exceeds the requirements for 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> fire rated construction. Hence, the design is considered ccapletely adequate for the service.
One of the design objectives of E3SAR II is to avoid fire dampers in smoke vents, as their automatic closure would render the smoke vent inoperative at the very time it was needed. With two exceptions, smoke vents pass through safety areas only of the same division as the vented area. The two exceptions are the Division 2 cable tunnel vent and the primary containment vent.
P M The Division 2 cable tunnel located in the corridor of (-)6' # elevation of the auxiliary building has a dedicated smoke removal system Michpasses thrcugh the division 1 area. The inlet to the duct is fitted with a standard .
sprinkler head. Any heat or smoke that exceeds 1650 F will fuse the link
@oef ws/ allowing fire water to flow through the head. The duct opening is 2.5 so ft._
j,,g,,gThis deluge spray will be sufficient to cool inlet gases from eiYher direction g gf below a temperature that could cause duct failure which could allow migration of heat to other fire resistence areas. This is consistent with NFPA 13 usino_
NO 3b sprinklers to protect openings in fire resistence walls where dampers cannot be fitted for other overriding criteria. The calculated flow rate from the
@s re. cable tunnel during smoke ventginis 3000 efm. a relatively hw flow rate.
gr, kler The sprinkler is designed to flow .25 gpm per 100 square foot of floor area be ,d w ,l/ or a minimum of _15 an- therefore, 3000 cfm will be cooled by a minimum of be deknW.15 gpm water. ThiL~ is sufficient flow to cooi gases or smoke below the temperature that would weaken or coll 6pse even e duct cf standard gage construction. The duct h65 a thick wall and is all weided construction, which (adds a redundant degree of protec tion.
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The can'ftunmen+ exhautrf W :tkr enei, tier, u na n;; tr ;-1 r;; ce-t:in ;ng -M has two inboard (1 manual) isolation valves and one outboard isolation valve.
If a fire occurs, either the inboard valves or the outboard valve would be located out of the fire area and could be closed. The valve within the fuel building is located in a room with 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> rated walls. The room is directly accessible from the fuel building or the stair tower between the fuel and auxiliary building. All return registers except for the pool sweep are located high in the containment so that bulk mixing, sided by the dome mixing system, would occur before any combustion gases enter the ventilation duct. The containment is more sensitive to bulk air temperature than the ventilation duct. If a fire raised the bulk temperature excessively, containment spray would be initiated to protect the containment at a temperature well below the threshold of damage to the ventilation duct. For these reasons, the current GESSAR II design ha for the c nta nment Ih ventilation is gonsideredWe-ldecl hoch ie 4:heaulo 50 proper and qu jotje Wi /adge. aye. th 9 3
. sign ~l~hegw'ust c uc e<>y ys m rw inp Tne remaining smoke vents which do not have fire dampers are the two in the control building. Each one of these smoke vents serves and traverses l
one division. Since it is impossible for these smoke vents to allow the fire in the area of cne division to spread to another division, the current GESSAR 11 design is considered to be adequate and proper.
There 13 Q COh Qihn4 thy VCMf an Th g su a coh%Menf Effh Y b' d Cvir S N h1 fb C Ouk/llbtj- hl/ bin ha:ffs on agc, ); '
[be hdMS W!ar-f*are }ocaYec/ Jh Q /W OM e fe f foo t- O f [be 00)fJbGY bO/ bY/ . TbCY b00h0[Q/~/cs'hf hg: t-C0 nq sujo n ducYbctYe cf,oc2C2 -?!o a : /3M 8/rS*cYll bow fire '/O in hiYe Ybe
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ATTACHMENT NO. 2 l
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PROPOSED RESOLUTION TO CONTAINMENT SYSTEMS BRANCH OUTSTANDING ISSUES 7,8 AND 9 i
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, (7) Secondary Containment Bypass Leakage NRC concern Bypass leakage may occur prior to PLCS actuation and should be accounted for in the dose calculation.
GE response GE will calculate the transport delay time to the environment on each containment penetration line with the PLCS installed. If the transport delay time from any line is less than the PLCS actuation time, GE will re-do the dose calculation to account that particular bypass leakage.
(8) Containment Repressurization NRC concern Post-LOCA containment repressurization by the PLCS should be limited to 50% design containment pressure at 30 days.
GE response GE will comply. GE will re-do the containment repressurization calculation to a less conservative method and will consider reducing the allocated leakages of the isolation valves.
- (9) Type C tests (gang vs. individual valve test)
NRC concern Gang testing of valves may not able to detect for potential single valve failure.
GE response GE will first gang test the valves with the PLCS. The acceptance criteria for this test will be the threshold leakage of a single valve (allocated leakage of the smallest single valve of the group). If this gang test exceeds the test criteria, a partial gang test will be performed with the same acceptance criteria as the first gang test. Individual valve test will be performed until the valve with excess leakage is located and corrected.
The responses to the corresponding NRC questions will be revised accordingly.
GESSAR II will be revised via amendment upon completion of the effort described above.
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ATTACHMENT NO. 3 1*
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SUPPLEMENT TO PROPOSED RESOLUTION OF MATERIALS ENGINEERING BRANCH OUTSTANDING ISSUE 5
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GESSAR II 22A7007
. 238 NUCLEAR ISLAND R;v. 14 5.2.3.3.4 Moisture Control for Low Hydrogen, Covered Arc
() Welding Electrodes (Continued)
Electrodes are distributed from sealed containers or ovens as required. At the end of each work shift, unused electrodes are returned to the storage ovens. Electrodes which are damaged, wet, or contaminated are discarded. If any electrodes are inadvertently left out of the ovens for more than one shift, they are discarded or reconditioned in accordance with manufacturer instructions.
5.2.3.4 Fabrication and Processing of Austenitic Stainless Steels 5.2.3.4.1 Avoidance of Stress / Corrosion Cracking 5.2.3.4.1.1 Avoidance of Significant Sensitization m kh R m. M Ako Gm k I,44 Rev.O u el m deSx
+ Ag cUs\ g.44oF wwtso-ohis nam I
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. I egulatory GES GuideSA R.
1.44 aadresses 10CFR50, Appendix A, GDCs 1 and 4, an ppendix B, requirements to control the application and proc essin of stainless steel to avoid severe sensitization tha ould lead to ess/ corrosion cracking. ;
All austenitic inless steel is purchased in solution-heat-treated condit' n in accordance with a .icable ASME and ASTM specifications.
Cooling rates from solution h treating' temperatures are required to be rapid enoug i . pr ent sensitization. Non-sensitization is verif using ASTM 62, Practice A methods.
~~
Material cha s have been made to minimize e possibility of intergra ar stress / corrosion cracking (IGSCC). All welded ,T.
wro austenitic stainless steel in the reactor c lant pressure p"{,q
,. undary which could be susceptible to stress / corrosion acking y II low carbon nuclear grade Type 304 or Type 316 L or LN withN i
5.2-39 [*r .
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-- GESSAR II 22A7007 238 NUCLEAR ISLAND, . Rsv. 14
- 5. .3.4.1.1 Avoidance of Significant Sensitization (Continued)
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0.02% imum carbon content and nitrogen control. There is piping whi is service sensitive or nonconforming as defi d in NUREG-0313, vision 1.
9 For machine, automatic, and manual elding interpass temperature is restri'cted to 350*F for all a in as steel welds. High heat welding processes such as blo welding nd electroslag welding were not permitted. All we filler meta and castings are required by specificatio o have a minimum 5% ferrite. ,
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.These contr s were used to avoid severe sensitization and o comply v . Regulatory Guide 1.44, Control of the Use of Sens' tized Stainl s Steel.
F commitment and revision, see Section l~.8.. _
5.2.3.4.1.2 Process Controls to Minimize Exposure to Contaminants Exposure to contaminants capable of causing stress / corrosion
- cracking of austenitic stainless steel components was avoided by i.
O 5.2-40
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ATTACHMENT NO. 4 SUPPLEMENT TO PROPOSED RESOLUTION OF OUTSTANDING ISSUE 1 (QUESTION 220.11)
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220.11 At the time of this review, Appendix 3H which decribes the effect of (3.7.2L the concrete between the containment and the. shield building on the
.. seismic analysis, is not available. Indicate when this appendix will be provided. This inforisation should be made available prior to the forthcoming structural audit in December 1982. .
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.In the Suppression Pool region of the containment vessel the shell has been stiffened by filling the annulus between the Containment and the Shield Building with reinforced concrete, t- A seismic dynamic analysis was performed to determine the ,
effects of this added concrete on the seismic responses of --
various structures in the Reactor Building. These structures
. include the Shield Building, Containment vessel Drywell, ~
, _ _ _ . Shield wall and the RPV pedestal, e.-.
Specifically, the objective of this analysis was toVtf eteQ,, h t' :
that the original seismic envelope curves used in the plant design .
envelope the seismic response of the Building structures with the added guncretey!te,g f actor, 3 ' ~~
y envelope curves as required. W h pdh,.
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Soil Cases Ob M.2/
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Four soil cases were used in the seismic ~ dynamic analysis -
_ - _ for the horizontal ground motion. They are the following:
CASE NUMBER DESIGNATION -
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2 GE-75-A-H2 f, ;
4 GE-75-VP3
6 GE-75-HR-H2 !
7 GE-FB-H2 (Fixed Base) ;
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Two soil cases were used in the analysis for the vertical motion.- ,'
They are the following: ,
CASE NUMBER DESIGNATION 11 GE-75-A-V 12 GE-FB-V (Fixed Base)
The case numbers above refer to those listed in GESSAR Table 3A-1.
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Mathematical Model The mathematical model originally u* sed for the analysis to develop the design loads and building gespenses did not include the concrete added to the region betw(en the containment and the Shield Buildin b low elevation uts, o b c4 (-J } ft 3 in.
] (. (L For this analysis solid ents were ad ed to represent the Y
i d annular concrete, The rest of the model is similar to that used previously, (See Figure -1 ) . The computer program for yd
- axisymetric structures (AXIS) was used in the analysis.
4 Dynamic Analys s y The horizontal and vertical analyses were perforned separately, e Shell forces, shell moments and element stresses were obtained g for individual soil cases. These results were, then enveloped j $ to arrive at a set of final responses for horizontal and vertical 0 4 motions respectively. Tables '- 1 through . 18 depict the a C' final results. These tabulated values were then compared with
.5 those in Section 3.7.
b Response spectra were generated for the soil cases studied.
- They were enveloped to arrive at a final set of curves.
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