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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20202H8821997-12-0303 December 1997 Final Response to FOIA Request for Documents.Records in App a Being Made Available in PDR & Encl IA-97-428, Final Response to FOIA Request for Documents.Records in App a Being Made Available in PDR & Encl1997-12-0303 December 1997 Final Response to FOIA Request for Documents.Records in App a Being Made Available in PDR & Encl ML20202H8981997-10-27027 October 1997 FOIA Request for Listed Pages from Section 19 of General Electric ABWR Ssar ML20210J3591997-08-11011 August 1997 Transmits Revised Fda for Us ABWR Std Design,Per App 0 of 10CFR52.FDA Allows ABWR Std Design to Be Ref in Application for Const Permit or Operating License,Per 10CFR50 or in Application for Combined License,Per 10CFR52 ML20149J7101997-07-23023 July 1997 Requests That R Simard Be Removed from Service Lists & R Bell Be Added to Svc Lists,Due to Recent NEI Reorganization ML20148A5701997-05-0202 May 1997 Forwards Affirmation Ltr Complying W/Filing Requirements of 10CFR52.45(d) & 50.30(b) Re Application for Review of ABWR Design Control Document,Rev 4 for Design Certification ML20196F8771997-03-28028 March 1997 Forwards Licensee ABWR Design Control Document,Rev 4 to Incorporate Changes Needed to Reflect Commission SRM Decisions & Subsequent Discussion W/Staff & to Support Ssar ML20137G3161997-03-28028 March 1997 Forwards Rev 4 to Ge'S ABWR Design Control Document to Incorporate Changes That Are Needed to Reflect Commission SRM Decisions & Subsequent Discussions W/Staff ML20147C1041997-01-23023 January 1997 Responds to Requesting Opportunity to Review Design Certification Rule for ABWR Before Sent to Ofc of Fr for Publication.Request Denied ML20133A9791996-12-18018 December 1996 Approves Rules Certifying Asea Brown Boveri-Combustion Engineering Sys 80+ & General Electric Nuclear Energy Advanced Boiling Water Reactor ML20133A9811996-12-18018 December 1996 Informs That NRC Has Approved Rules Certifying Two Evolutionary Reactor Designs:Asea Brown Boveri-Combustion Engineering Sys 80+ & GE Nuclear Energy ABWR ML20133A9871996-12-18018 December 1996 Informs of NRC Approval of Rules Certifying Two Evolutionary Reactor Designs,Asea Brown Boveri-CE Sys 80+ & GE Nuclear Energy ABWR ML20133A9901996-12-18018 December 1996 Informs That NRC Has Approved Asea Brown Boveri CE Sys 80+ & GE Nuclear Energy ABWR as Evolutionary Reactor Designs ML20133B0191996-12-18018 December 1996 Informs of Approval of Rules Certifying Two Evolutionary Reactor Designs,Asea Brown Boveri-Combustion Engineering Sys 80+ & GE Nuclear Energys Advanced BWR ML20128P4981996-09-23023 September 1996 Forwards Proposed Rule Language for 3 Design Certifications Discussed at 960827 NRC Briefing ML20128N6001996-09-16016 September 1996 Provides Addl Info in Response to Several Questions Raised by Commission During 960827 Briefing on Design Certification Rulemaking ML20117H3311996-08-30030 August 1996 Forwards GE ABWR Dcd,Rev 3 (Filed in Category A),Abwr Cdm, Rev 8 (Filed in Category a) & ABWR Ssar,Amend 37,Rev 9 (Filed in Category K) to Incorporate Changes Ref in 960701 & s from Jf Quirk ML20115C0861996-07-0101 July 1996 Forwards GE Providing Background for Need for Proposed Changes to ABWR Design Control Document (Dcd), Markups Incorporating Comments Resulting from Interactions W/Nrc & DCD Markups for Addl Proposed Change ML20115G2201996-06-10010 June 1996 Provides Comments from Two NRR Organizations on Cdm & Ssar Change Pages.Markups of DCD & Ssar Encl ML20108D4481996-04-26026 April 1996 Responds to Staff Ltr Re ABWR DCD Change Package Which Recommends That GE Submit All Changes Identified by Foake Program.Ltr Contrary to Previous Understandings ML20107H3241996-04-16016 April 1996 Forwards marked-up Proposed Changes to ABWR Design Description Resulting from Info Developed in Course of ABWR Engineering Program ML20108D3111996-04-0303 April 1996 Forwards Marked Up Proposed Changes to ABWR Design Description Resulting from Info Developed in Course of ABWR First-Of-A-Kind Engineering Program ML20101G9021996-03-22022 March 1996 Forwards Amend 36 to Rev 8 to 23A6100, ABWR Ssar & Rev 7 to 25A5447, Certified Design Matl ML20101P1231996-03-15015 March 1996 Expresses Appreciation for Opportunity on 960308 to Brief Commission on Views on Design Certification Rules, Particularly W/Respect to Issue of Applicable Regulations ML20092G0171995-09-15015 September 1995 Forwards Missing Pp 103-117 from Attachment B of from SR Specker on Behalf of GE Nuclear Energy Re Response to Proposed RM for Std Design Certification of Us Advanced BWR Design LD-95-041, Forwards Response to Ocre 950812 Comment on Design Features of GE Abwr.Disagrees W/Any Suggestion That NRC Extend Favorable Consideration of Comment to Sys 80+ Std Plant Design1995-09-0505 September 1995 Forwards Response to Ocre 950812 Comment on Design Features of GE Abwr.Disagrees W/Any Suggestion That NRC Extend Favorable Consideration of Comment to Sys 80+ Std Plant Design ML20092B6431995-09-0101 September 1995 Forwards Analysis of Ocre 950812 Supplemental Comments on Design of Abwr,Notice of Final Rule & Statement of Considerations,In Order to Ensure That NRC Has Complete Technical Info on Subj ML20086G7981995-07-12012 July 1995 Informs of Changes to Svc List,Per Request of Jn Fox ML20084Q0621995-05-31031 May 1995 Forwards Revised Effective Page Listing for ABWR Design Control Document ML20078F4271995-01-26026 January 1995 Provides Info for Closure of ABWR FSER Confirmatory Item F1.2.2-2 Previously Addressed in 941222 Closure Ltr ML20077R9141995-01-17017 January 1995 Forwards Rev 2 to ABWR Design Control Document. Rev of Design Control Document Accompanied by List of Currently Effective Pages.List Provided as Attachment 2 ML20081K9361994-12-22022 December 1994 Documents Closure of ABWR FSER Confirmatory Items ML20080D3341994-12-22022 December 1994 Forwards Rev 1 to Advanced BWR Design Control Document ML20077A7471994-11-23023 November 1994 Forwards Revised Fda for Us ABWR Std Design,Per App O of 10CFR52 & Notice of Issuance of Fda ML20081K9031994-11-18018 November 1994 Forwards Rev 0 to Technical Support Document (Tsd) for ABWR & Updated ABWR Ssar App 19P Markup.Updated Version of App 19P Incorporated as Attachment a to Tsd,As Agreed During 941006 Meeting W/Nrc ML20073M7221994-11-0404 November 1994 Forwards Proposed Rev to Section 3.8 of DCD Introduction for ABWR Re GE Meeting on 941102 ML20078E6391994-11-0101 November 1994 Forwards Description of Proposed Process for Controlling Changes to Severe Accident Evaluations & Explains Bases for Proposed Process ML20149G9751994-10-31031 October 1994 Requests That Encl Ltrs Be Distributed to Controlled Copy of Licensee QA Program ML20149G7081994-10-28028 October 1994 Forwards Rev 0 to ABWR Design Control Document (Dcd). DCD Comprised of Introduction,Certified Design Matl & Approved Safety Analysis Matl.Responses to NRC Comments Requested by Also Encl ML20081K8881994-10-13013 October 1994 Maintains That Proposition That GE Be Designated in Notice of Proposed Rulemaking as Source from Which Public Could Request Copies of Design Control Document (DCD) Inappropriate.Public Should Obtain Access to DCD from NRC ML20076F8451994-10-0505 October 1994 Responds to Re Root Cause & Corrective Measures on Unidentified Changes That Occurred in Design Control Document ML20081K8721994-09-20020 September 1994 Requests That ABWR Final Design Approval (Fda) Be Amended to Provide for Term of 15 Years from Date of Issuance & That,As Provided in SRM on COM-SECY-95-025,FDA Be Updated as Needed to Conform to Any Changes Resulting from Certification RM ML20149F7681994-09-0707 September 1994 Forwards Rev 0 to Advanced BWR Design Control Document ML20072T2691994-08-30030 August 1994 Advises That Industry Intends to Comment in Opposition to Applicable Regulations Approach & Proposed Text of Applicable Regulations in Design Certification Rulemaking Proceeding for Both ABWR & Sys 80+ ML20072Q2811994-08-30030 August 1994 Submits mark-up of Previous Version of Design Control Document Introduction Together W/Typed Rev ML20072C9821994-08-12012 August 1994 Responds to Re NRC Fee Regulations for Design Certification & Request Confirmation of Understanding of 10CFR170 ML20072E3381994-08-0909 August 1994 Requests Addition of Author Name to Svc List for Advanced BWR ML20072A8451994-08-0303 August 1994 Forwards Chapter 21 17x22 Inch Drawings to Replace Temporary 11x17 Drawings Provided in ML20071Q9091994-08-0202 August 1994 Forwards Ten Copies of Draft ABWR Design Control Document ML20070H9651994-07-20020 July 1994 Forwards Rev 7 to 23A6100, ABWR Ssar, Amend 35 & Rev 6 to 25A5447, ABWR Certified Design Matl 1997-08-11
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20202H8981997-10-27027 October 1997 FOIA Request for Listed Pages from Section 19 of General Electric ABWR Ssar ML20149J7101997-07-23023 July 1997 Requests That R Simard Be Removed from Service Lists & R Bell Be Added to Svc Lists,Due to Recent NEI Reorganization ML20148A5701997-05-0202 May 1997 Forwards Affirmation Ltr Complying W/Filing Requirements of 10CFR52.45(d) & 50.30(b) Re Application for Review of ABWR Design Control Document,Rev 4 for Design Certification ML20196F8771997-03-28028 March 1997 Forwards Licensee ABWR Design Control Document,Rev 4 to Incorporate Changes Needed to Reflect Commission SRM Decisions & Subsequent Discussion W/Staff & to Support Ssar ML20137G3161997-03-28028 March 1997 Forwards Rev 4 to Ge'S ABWR Design Control Document to Incorporate Changes That Are Needed to Reflect Commission SRM Decisions & Subsequent Discussions W/Staff ML20128P4981996-09-23023 September 1996 Forwards Proposed Rule Language for 3 Design Certifications Discussed at 960827 NRC Briefing ML20128N6001996-09-16016 September 1996 Provides Addl Info in Response to Several Questions Raised by Commission During 960827 Briefing on Design Certification Rulemaking ML20117H3311996-08-30030 August 1996 Forwards GE ABWR Dcd,Rev 3 (Filed in Category A),Abwr Cdm, Rev 8 (Filed in Category a) & ABWR Ssar,Amend 37,Rev 9 (Filed in Category K) to Incorporate Changes Ref in 960701 & s from Jf Quirk ML20115C0861996-07-0101 July 1996 Forwards GE Providing Background for Need for Proposed Changes to ABWR Design Control Document (Dcd), Markups Incorporating Comments Resulting from Interactions W/Nrc & DCD Markups for Addl Proposed Change ML20115G2201996-06-10010 June 1996 Provides Comments from Two NRR Organizations on Cdm & Ssar Change Pages.Markups of DCD & Ssar Encl ML20108D4481996-04-26026 April 1996 Responds to Staff Ltr Re ABWR DCD Change Package Which Recommends That GE Submit All Changes Identified by Foake Program.Ltr Contrary to Previous Understandings ML20107H3241996-04-16016 April 1996 Forwards marked-up Proposed Changes to ABWR Design Description Resulting from Info Developed in Course of ABWR Engineering Program ML20108D3111996-04-0303 April 1996 Forwards Marked Up Proposed Changes to ABWR Design Description Resulting from Info Developed in Course of ABWR First-Of-A-Kind Engineering Program ML20101G9021996-03-22022 March 1996 Forwards Amend 36 to Rev 8 to 23A6100, ABWR Ssar & Rev 7 to 25A5447, Certified Design Matl ML20101P1231996-03-15015 March 1996 Expresses Appreciation for Opportunity on 960308 to Brief Commission on Views on Design Certification Rules, Particularly W/Respect to Issue of Applicable Regulations ML20092G0171995-09-15015 September 1995 Forwards Missing Pp 103-117 from Attachment B of from SR Specker on Behalf of GE Nuclear Energy Re Response to Proposed RM for Std Design Certification of Us Advanced BWR Design LD-95-041, Forwards Response to Ocre 950812 Comment on Design Features of GE Abwr.Disagrees W/Any Suggestion That NRC Extend Favorable Consideration of Comment to Sys 80+ Std Plant Design1995-09-0505 September 1995 Forwards Response to Ocre 950812 Comment on Design Features of GE Abwr.Disagrees W/Any Suggestion That NRC Extend Favorable Consideration of Comment to Sys 80+ Std Plant Design ML20092B6431995-09-0101 September 1995 Forwards Analysis of Ocre 950812 Supplemental Comments on Design of Abwr,Notice of Final Rule & Statement of Considerations,In Order to Ensure That NRC Has Complete Technical Info on Subj ML20086G7981995-07-12012 July 1995 Informs of Changes to Svc List,Per Request of Jn Fox ML20084Q0621995-05-31031 May 1995 Forwards Revised Effective Page Listing for ABWR Design Control Document ML20078F4271995-01-26026 January 1995 Provides Info for Closure of ABWR FSER Confirmatory Item F1.2.2-2 Previously Addressed in 941222 Closure Ltr ML20077R9141995-01-17017 January 1995 Forwards Rev 2 to ABWR Design Control Document. Rev of Design Control Document Accompanied by List of Currently Effective Pages.List Provided as Attachment 2 ML20080D3341994-12-22022 December 1994 Forwards Rev 1 to Advanced BWR Design Control Document ML20081K9361994-12-22022 December 1994 Documents Closure of ABWR FSER Confirmatory Items ML20081K9031994-11-18018 November 1994 Forwards Rev 0 to Technical Support Document (Tsd) for ABWR & Updated ABWR Ssar App 19P Markup.Updated Version of App 19P Incorporated as Attachment a to Tsd,As Agreed During 941006 Meeting W/Nrc ML20073M7221994-11-0404 November 1994 Forwards Proposed Rev to Section 3.8 of DCD Introduction for ABWR Re GE Meeting on 941102 ML20078E6391994-11-0101 November 1994 Forwards Description of Proposed Process for Controlling Changes to Severe Accident Evaluations & Explains Bases for Proposed Process ML20149G9751994-10-31031 October 1994 Requests That Encl Ltrs Be Distributed to Controlled Copy of Licensee QA Program ML20149G7081994-10-28028 October 1994 Forwards Rev 0 to ABWR Design Control Document (Dcd). DCD Comprised of Introduction,Certified Design Matl & Approved Safety Analysis Matl.Responses to NRC Comments Requested by Also Encl ML20081K8881994-10-13013 October 1994 Maintains That Proposition That GE Be Designated in Notice of Proposed Rulemaking as Source from Which Public Could Request Copies of Design Control Document (DCD) Inappropriate.Public Should Obtain Access to DCD from NRC ML20076F8451994-10-0505 October 1994 Responds to Re Root Cause & Corrective Measures on Unidentified Changes That Occurred in Design Control Document ML20081K8721994-09-20020 September 1994 Requests That ABWR Final Design Approval (Fda) Be Amended to Provide for Term of 15 Years from Date of Issuance & That,As Provided in SRM on COM-SECY-95-025,FDA Be Updated as Needed to Conform to Any Changes Resulting from Certification RM ML20149F7681994-09-0707 September 1994 Forwards Rev 0 to Advanced BWR Design Control Document ML20072Q2811994-08-30030 August 1994 Submits mark-up of Previous Version of Design Control Document Introduction Together W/Typed Rev ML20072T2691994-08-30030 August 1994 Advises That Industry Intends to Comment in Opposition to Applicable Regulations Approach & Proposed Text of Applicable Regulations in Design Certification Rulemaking Proceeding for Both ABWR & Sys 80+ ML20072C9821994-08-12012 August 1994 Responds to Re NRC Fee Regulations for Design Certification & Request Confirmation of Understanding of 10CFR170 ML20072E3381994-08-0909 August 1994 Requests Addition of Author Name to Svc List for Advanced BWR ML20072A8451994-08-0303 August 1994 Forwards Chapter 21 17x22 Inch Drawings to Replace Temporary 11x17 Drawings Provided in ML20071Q9091994-08-0202 August 1994 Forwards Ten Copies of Draft ABWR Design Control Document ML20070H9651994-07-20020 July 1994 Forwards Rev 7 to 23A6100, ABWR Ssar, Amend 35 & Rev 6 to 25A5447, ABWR Certified Design Matl ML20070D9381994-07-12012 July 1994 Forwards D-RAP Design Description & ITAAC for Inclusion in Section 3.6 of Cdm & Cdm & Ssar Markups Addressing Minor Corrections ML20069Q3001994-06-23023 June 1994 Forwards Rev 6 for Ssar Amend 35 & Rev 5 for Certified Design Matl ML20070E1981994-06-0808 June 1994 Forwards Ssar Markup Indicating Applicable Edtion to UBC, AISI SG-673 & NEMA FB1 to ABWR Ssar.Changes Will Be Included in Amend 35 Mod Package.Notifies That Applicable Edition of Bechtel Rept BC-TOP-3-A Is Rev 3 ML20070E1891994-06-0808 June 1994 Forwards Ssar Markup of Section 1A.2.34 Which Responds to TMI Item III.D.1(1).Mod Makes Section Consistent W/Ts 5.5.2.2.Change Will Be Included in Amend 35 Mod Package Scheduled for Distribution Later This Month ML20070D9331994-05-26026 May 1994 Forwards Results of Analyses to Assess Impact of Drywell Spray Actuation Following LOCA to Ensure Bounding Scenario ML20069H2101994-05-25025 May 1994 Forwards 25A5447,Rev 4, ABWR Certified Design Matl & Nonproprietary & Proprietary Version of 23A6100,Rev 5, ABWR Ssar. Proprietary Version of Ssar Withheld ML20069G9301994-05-25025 May 1994 Submits non-proprietary Ssar Amend 35 & Certified Design Material Rev 4 to Listed NRR Recipients ML20069B1831994-05-25025 May 1994 Resubmits Affidavit for GE Abwr,Proprietary Info Section 18H, Supporting Analysis for Emergency Control Operation Info ML20069A7371994-05-20020 May 1994 Forwards Proprietary Ssar Sections 11A.2 & 11A.4 to Specified NRR Recipients Listed on Attachment 1.Encl Withheld ML20029D4211994-04-29029 April 1994 Forwards Revised Ssar Markups Responding to Commitments Made at 940415 Meeting in Rockville,Md,Including Addl Info Reflecting Locking Mechanisms of Subassemblies & European Experience & Finalized TS for CRD Removal - Refueling 1997-07-23
[Table view] |
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From y ,;, cog, fy (74 f~g y 175 Curtner Avenue San Jose, CA 95125 Phone (408) 925- /*/ ,2 Y FAX (408) 925-1193 or (408) 925-1687 Subject pra/f CowkesNe a f L hirdian 1. 9 4 - .
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From B e r br i c l e x e N / Man Code fy p fgy 175 Curtner Avenue San Jose, CA 95125 Phone (408) 925- /7 2Y FAX (408) 925-1193-or (408) 925-1687 i
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AM W K uutrma Slan~dard Plant my 3 ance with the ASME Boiler and Pressure vessel 3.93J.1.1 Considerition of Loading, Code Scct' ion !!!. For Class ! piping, stressses Stress, and Acceleration Condiflons la the are calculated on an clast:c basis and evaluated Analysis in accordance with NB.3600 of the ASME Code, Section Ill. For Class 2 and 3 piping, stresses in order to avoid damage to the ECCS pumps are calc ulated on an elastic basis and esaluated during the faulted plant cor'dition, the stres-in accordance with NC/ND 3600 of the Code, ses caused by the combination of normal ope.
rating loads, SSE, other RBV loads, and dyna-3.9J.; Pump and Vabe Operability Assurance mic system loads are limited to the material clastic litnit. A three dimensional finite.
Aaise mechanical (with or without e!cctrical element model of the pump and associated motor operation; equipment are Seisreic Category I and (s e e S u bs e ctions 3.9.3.2.2 and 3.9.3.2.1.5 for each is designed to perform a mechanical motion RCIC pump and turbine, respectively) and its for its safety-related function during the life support is developed and analyzed using the of the plant under postulated plant conditions. response spectrum and the dynamic analysis me.
Equipment with faulted condition functional thod. The same is analyzed due to statie nor.
requirements include actne pumps and valves in zie loads, pump thrust loads, and dead weight.
fluid systems such as the residual heat removal Critical location stresses are com pared with system, emergency core cooling system, and main the allowable stresses and the cri- tical steam system. location deflections with the allow ables; and accelerations are checked to eval- unte This Subsection discusses operability operability. The average membrane stress cru assurance of active ASME Code Section Ill pumps for tbc faulted condition loads is limited to and valves. including motor, turbine or operator 1.2S o r a p p r oxim a t ely 0.75 0 (0 =
that is a part of the pump or valve (See yield stress), and the maximum streslin l5 cal S ubse ction 3.9.2.2). The COL applicant must fibers (Om + bending stress ab) is limited ensure that specific environmental parameters are to 1.8S or approximately 1,10 . The properly defined and enveloped in the methodology maximum faulted evenfnozzle loads Iare also for in 3p-cific plant and impleasented in its considered in an analysis of the putap supports i equipment qualification program. to assure that a system :nisalignment cannot occur.
Safety.related valves and pumps are qualified by testing .nd analysis and by satisfying the Performing these analyses with the stress and deformation criteria at the critical conservative loads stated and with the locations within the pumps and valves. restrictive stress llenits as allowables assures Operability is assured by meeting the that critical parts of the pump and associated r e q uire:n e nt s of the progr ams define d in motor or turbine will not be damaged during the Subsection 3.9.2.2 Section 3.10, Section 3.11 faulted condition and that the operability of and the followin bsections, the pump for post faulted condition operation i W sW 7 3.9, u will not be impaired.
S e c tion 4.4 of G E's E nviron m e n t al Qualification Program (Reference 6) applies to 3.9.3.2.1.2 Pump / Motor OperatJon During and this subsection, and the seismie qualification Following Dynamle Loading methodology presented therein is applicable to mechanical as well as electrical equipment. Active ECCS pump /tnotor rotor combinations are designed to rotate at a constant speed under all 3.93.2.1 ECCS Pumps, Motors and Turbine couditions Motors are designed to withstand short perii ds of severe overload. The high Dynamic quahfication of the ECCS (RHR, RCIC rotary inertia in the operating pump and HPCF) pumps with motor or turbine usembly is also described in Subsections 3.9.2.2.2.6 a n d 3.9.2.2.2.7 14%RT 3 9.12
.ie s q n an ci 9 OH Ochn rquiremenh .fg f 3 ge fy,, 34, f A rr.e n dm e n t M 22
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, ance with the ASME Boiler and Pressure Vessel 3.9.3.2.1.1 Conalderat!on of Loading, Code Settton !!!. Por Class 1 piping, stressses Stress, and Acceleration Conditions la the are calcu' lated on an elastic basis and evaluated Analysis in accordance with NB.3600 of the ASME Code.
Section !!!. For Class 2 and 3 piping, stresses In order to avoid damage to the ECCS pumps are calculated on an clastic basis and evaluated during the f aulted plant condition, the stres.
in accordance with NC/ND 3600 of the Code. ses caused by the combination of normal opc.
rating loads, SSE, other RBV loads, and dyna.
3.9J.; Pump and Vabe Operibility Assurance mit system loads are limited to the material clastic limit. A three dimensional finite.
Actne mechanic.nl (wnh or without electrical element model of the pump and associated motor operation) equipment are Seismic Category I and (s ee S u bs ections 3.9.3.2.2 and 3.9.3.2.1.5 for each is designed to perform a mechanical motion RCIC pump and turbine, respectively) and its for its safety.related function during the life support is developed and analysed using the of the plant under postulated plant conditions. response spectrum and the dynamie analysis me.
Equipment with faulted condition functional thod. The same is analyzed due to static nor-requirements include active pumps and valves in zie loads, pump thrust loads, and dead wei6 ht.
fluid systems such as the residual beat removal Critical location stresses are com. pared with system, emergency core cooling system, and main the allowable stresses and the erl. tical steam system. location deflections with the allow ables; and accelerations are checked to eval- unte This S ubse ction discusse s operability operability. The average membrane stress am assurance of active ASME Code Section III pumps for the faulted condition loads is limited to and valves, including motor, turbine or operator 1. 2 5 o r approximately 0.75 a (0 =
that is a part of the pump or valve (See yield stress), and the maximum stre:I in IUcal Subsection 3.9.2.2). The COL applicant must fibers (am + bending stress ab) is limited ensure that specific environmental parameters are t o 1.8S or approxim a t ely 1.1 0 . The properly defined and enveloped in the methodology maximum faulted event nozzle loadsYarc also for its specific plant and implemented in its considered in an analysis of the pump supports equipment qualification program. to assure that a system misalignment cannot occur.
Safety-related valves and pumps are qualified by testing and analysis and by satisfying the Performing these analyses with the stress and deformation criteria at the critical conservative loads stated and with the locations within the pumps and valves. restrictive stress limits as allowables assures O pe r abilit y is assured by meeting the that critical parts of the pump and associated requirements of the programs defined in motor or turbina will not be damaged during the Subse ction 3.9.2.2 Section 3.10, Section 3.11 faulted condition and that the operability of and the followin bsections. the pump for post faulted condition operation tw m 3.9.s.y will not be impaired.
S e c tion 4.4 o f G E's Environmental Qualification Program (Reference 6) applies to 3.9.3.2.1.2 Pump / Motor Operstjon During and this subsection, and the seismic qualification Following Dpamic Imding methodology presented therein is applicable to mechanical as well as electrical equipment. Active ECCS pump / motor rotor combinations are designed to rotate at a constant speed under all 3.9.3.2.1 ECCS Pumps, Moton and Turbine conditions. Motors are designed to withstand short periods of severe overload. The high Dynamic qualification of the ECCS (RHR, RCIC rotary inertia in the operating pump and HPCF) pumps with motor or turbine auembly is also described in Subsections 3.9.2.2.2.6 a nd 3.9 2.2.2.7.
M U T 3 9. .t 2 des in and g$ u o/, (,'cdo on repirement.s So L ucWorr 3.q.4 Amendment 19-U
. b.: JJ- . y GE Nuclear Energy
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May 19.1993 Docket No. STN 52 001 I l
Chet Poslusny, Senior Project Manager Standardization Project Directorate Associate Directorate for Advanced Reactors and License Renewal Office of the Nuclear Reactor Regulation
Subject:
Submittal Supporting Accelerated ABWR Review Schedule Draft Composite of Subsection 3.9.6
Dear Cher:
Enclosed is a draft composite of SSAR Subsection 3.9.6.
Please provide a copy of this transmittal to Renee Li.
Sincerely, a
Jack Fox Advanced Reactor Programs ec: Bernie Genetti (GE)
Norman Fletcher (DOE) amoi P35ga5cisa !. f
' i .:J T 2, 1
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, CE Nuctur Energy
.. ,0 . c 3: . -
i May 19,1993 Docket No. STN 52 001 I
Chet Poslusny, Senior Project Manager Standardization Project Directorate Associate Directorate for Advanced Reactors and License Renewal Office of the Nuclear Reactor Regulation Sutsject: Submittal Supporting Accelerated ABWR Review Schedule Draft Composite of Subsection 3,9.6
Dear Chet:
Enclosed is a draft compcsite of SSAR Subsection 3.9.6.
Please provide a copy of this transmittal to Renee Li.
Sincerely, 9
Jack Fox Advanced Reactor Programs cc. Bernie Genetti(GE)
Norman Retcher (DOE) l im a. I LQ p - #
, } .D.eX 5'f E 2' / ,
f'