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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] |
Text
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NovemberL18,1994 MFN No.14894? !
Docket No.52-001.. ;
i i
i i
- . Document Control Desk l U.S. Nuclear Regulatory Commission .
.> Washington, D.C. 20555 i
Attention: R. W., Borchardt, Director !
Standardization Project Directorate l
Subject:
NEPA/SAMDA Submittal for the ABWR l
Reference:
Letter,J.F. Quirk to R.W. Borchardt, same title, August 26,1993, min No.137-93 i The attached Technical Support Document (TSD) for the ABWR supersedes the TSD transmitted August 26,1993 (reference). On October 6,1994, GE met with NRC staff senior management to discuss the staffs comments on GE's proposed ;
- . . introduction to the Design Control Document (DCD). One of the items agreed to ;
was not to incorporate ABWR SSAR Appendix 19P with its probabilistic values into the DCD, but incorporate this information into the TSD. An updated version of Appendix 19P (see attached markup) was incorporated as Attachment A to the TSD. Several editorial changes accompanied the updated
- technical information in forming Attachment A. l The conclusions remain unchanged and GE believes that this TSD provides a sufficient basis for the NRC to issue an amendment to 10CFR51 which !
concludes:
- 1) that the probability of severe accidents in the ABWR is remote and speculative,
- 2) that the risks of severe accidents and the radiological impacts of normal operation of the ABWR do not constitute a significant impact to the quality of the human environment, and
- 3) that there are no reascmable alternatives for reducing these risks or impacts. I i 9503290334 941118 5 PDR ADOCK 05200001 ,}
A PDR 4 k.
30000G 21 f @.a &
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~
R. W. Borchardt
. MFN No.148-94 -
Docket No.52-001 Page 2 -
. If you have any questions on the attached TSD, please call Peter D. Knecht at ;
(408) 92 % 215. .;
r Sincerely, j e/ - l
( . y.-yy eat l
r seph F. Quirk j Project Manager l ABWR Certification ;
MC-782 (408) 92%219 ,
\ i Att. .
cc: S.A. Hucik ..(GE) F.J. Miraglia,Jr. (NRC) l A.C. Thadani !(NRC) T.H. Boyce (NRC) !
D.M. Crutchfield (NRC) F.A. Ross (DOE)
N.D. Fletcher (DOE) K.E. Stahlkopf (EPRI) . l D.J. McGoff (DOE) a F
i i
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' 4 i a l
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7, ,t i ~
._ A
11/18/94 ABWR SSAR APPENDIX 19P MARKUP
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.ABlWR saseneresansqasewnsuaspart :
I
'19P.4.2.4 Safety-Related Condensate StorageTank ,
' The current ABWR design consists of a standard non-seismically qualified Condensate _-
Storage Tank (CST). This modification would upgrade the structure of the CST such l that it would be avalable to provide makeup to the reactor following a seismic event.
- l This modificadon only benefits the risks of core damage following seismic events. .;
However, because the suppression pool provides an alternate suction source and the !
HCLPF for the suppression pool is relauvely high (Appendix 191), the dominant failure ' . l modes are not limited bywater availability. Therefore the benefit of this modification is l considered small. A benefit of OE person-Sievert averted was arbitranly chosen for .- l an upgnded CST. .- g ,,4 A/p 7 l i . o s.-4 742 '
e q 19P.4.3 Containment Capability !
i l- The ABWR containment is designed for about 0.411 MPa internal pressure and includes a containment rupture disk which would relieve excessive pressure ifit develops during a severe accident. By providing the release point from the wetwell i airspace, mitign. tion of releases are achieved through scrubbing of the fission products . l in the suppression pool.
19P.4.3.1 Larger Volume Containment ,
This modification would provide a larger volume containment as a means to mitigate >
the effects of severe accidents. By increasing the size the containment could be able to
, absorb additional noncondensible gas generation and delay activation of the !
containment rupture disk or early containment failure. i This item would mitigate the consequence of an accident by delaying the time before l the severe accident source term is released and allowing more time for radioactive decay i and recovery of systems. However, if recovery does not occur, eventual release is not l prevented and if operation of the containment ove: pressure rupture' disk does not i occur, ultimately the containment will fait due to the long term pressuruation caused ;
by core concrete intemcuon an s generanon. .
0u+ !
If sequences involving drywell head failure were eliminated (Cases 3,6,7,8 and 9), the l l offsite risks would be reduced by about 82% and about 15E-04 person-Sievert would be j averted.
19P.4/5.2 Increased Containment Pressure Capacity The design pressure of the ABWR containmentis 0.411 MPa (45 psig).The !
containment rupture disk pressure and ultimate capability are significantly higher. By increasing the ultimate pressure capability of the containment (including seals), the effects of a severe accident could be reduced or eliminated by delaying the time of I" valuation of Potential Modificatrons to the ABWn Design - Amendment 34 19P 9 l
'I l
l
. ,, , .r,-~. . , - - , ~ m-, , , -. - - -
i Y _
22Asa nev. s ;
b ABWR stonnentsannyAnarysesnevert i c. Tyroval %denawce. Peedve/M wals t G E-04 Table 19P-5 Summary of Benefits Potential Person Sievert '
Modi 6 cation Averted 1 Accident Mac:;: : l [ !
1a. Severe Accident EPGs/AMGs 1.5E-04 I 1b
- p. Computer Aided instrumentation 1.0E-04 7
2 Decay Heat Removal 2a. Passive High Pressure Systam Vf*
J
_6.9 E- O 4, Q3_ .8E-0J4 I" ' " ' ' ' *
- 26. Improved Depressurization 4.2E-04 2c. Suppression Pool Jockey Pump 0.2E-04 2d. Safety Related Condensate Storage Tank 1.0E-04 3 Containment Capability 7
,d y y , 7I,, p 3a. Larger Volume Containment 15E-04 e<9*"
4 ,
3b. Increased Containment Pressure Capacity i6E-04 l 3c. Improved Vacuum Breakers 0.004E-04 ;
3d. Improved Bottom Fenetration Design 5.7E-04 4 Containment Heat Removal da. Larger Volume Suppression Pool 0.02E-04 5 Containment Atmosphere Gas Removal Sa. Low Flow Filtered Vent 1.4E-04 7 Containment Sprey Systems 7a. Drywell Head Flooding 6.0E-04 8 Prevention Concepts Ba. Additional Service Water Pump 1.6E-04 l 9 AC Fower Suppass 9a. Steam Driven Turbine Generator 5.2E-04 9b. Aktemate Fump Power Source 6.9E-04 10 DC Power Supplies
]
10a. Dedicated DC Power Supply 6.9E-04 )
11 ATWS CapabiRty lla. ATWS Sized Vent 3.0E-04 13 System Simplification 13a. Reactor Building Sprays 1.N-04 1
14 Core Retention Device i 0.1E-04 I 14a. Flooded Rubble Bed Evaluation of PotentialModi6 cations to the ABnft Design - Amendment 35 19P-29 l
1
-e w e
s
23A6100 Mov.1 iABWR audsonsanyAnnysieneperr Table 19P-6 Summary of Costs Estimated Cost Modl6cetion (K) 1 Aeoident Management I a. Severe Accident EPGs $600.0 lb. Computer Aided instrumentation - $599.6 1c. Improved Maintenance Procedures / Manuals $299.0 2 Decay Heat Removal
- t. 2a. Passive High Pressure System $1744.0 2b. Improved Depressurization $598.6 2c.
2d.
Suppression Pool Jockey Pump Safety Related Condensate Storage Tank
$1000.0
-6 Il3.S 3 Containment Capatnuty 3a. Larger Volume Containment $8000.0 3b. Increased Containment Pressure Capacity $12000.0 3c. Improved Vacuum Breakers $100.0 3d. Improved Bottom Penetration Design $750.0 4 Containment Heat Removal da. Larger Volume Suppression Pool $8000.0 l 5 Containment Ar jw; Gas Removal )
5a. Filtered Containment Vent $3000.0 7 Containment Sprey Systems 7a. Drywell Head Flooding $100.0 )
8 Prevention Concepts 8a. Additional Service Water Pump $5999.0 9 AC Power Supplies 9a. Steam Driven Turbine Generator $5994.3 9b. Altemate Pump Power Source $1194.0 10 DC Power Supplies 10a. Dedicated RHR DC Power Supply $3000.0 11 ATWS Capability
- 11a. ATWS Sized Vent 5300.0 l- 13 System Simpiincetion 13a. Reactor Building Sprays $100.0 l l
14 Core Retention Devices l 14a. Flooded Rubble Bed $18,750.0 19P40 Evaluation of Potential Modifications to the ABWM Design - Amendment 31 l
e
- y ~l zusa nov. s ABWR suedandsannyanswainneperr Table 19P-7 Summary of Results ..
Cost (K)/ Person-Momiestion Sievert Averted ,
- l 7a. Drywell Head Flooding $ 166,700 13a. Reactor Building Sprays $ 588,200 l
- j. 11a. ATWS Sized Vent $ @-1,000,00o '
3d. Improved Bottom Penetration Design $ 1,315,800 l
l 2b. Improved Depressurization $ (5,417.30G-l,4 25joo o
- 96. Alternate Pump Power Source $_ d,735,100% 1,750,00 o l
l 1c. Improved Maintenance Procedures / Manuals $ (1829,800]- t, 86 F,Fo o l 2a. Passive High Pressure System $ C2,515,80@- j2 52,7, Sc o l 1a. Severe Accident EPGs $ (3,983,4001-4;000,000 10a. Dedicated DC Power Supply $ 4,347,800 l
3a. Larger Volume Containment . $ 5,333,300 l
l I b. Computer Aided instrumentation $ [000,003-5,9 9 G,000 l
2c, Suppression Pool Jockey Pump $ 4 213,00b gj p goj oo, j 2d. Safety Related Condensate Storage Tank $ 10,000,000 l
l 9a. Steam Driven Turbine Generator $ (T1,472,60ll- l(,52.7,5 o o Sa. Low Flow Filtered Vent $ 21,428,600 l
l 8a. Additional Service Water Pump $ (17,500,00E-37 j 473,8o C
'E C'."'.' L,,.i "x: ":n rr ' ! ' 2,5 ^^.^^^ t, -
l l 3b. Increased Containment Pressure Capacity $ do,000,00b7;Scojo00 l 3c. Improved Vacuum Breakers S (332,900,00b 7,SO j 000j oo. ,
l 14a. Flooded Rubbis Bed $ 1,875,000,000 OK 4a. Larger Volume Suppression Pool $ 4,000,000,000 l
f Evolustion of Potential Modincstions to the ABWR Design - Amendment 35 19P 31/32