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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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. GE Nuclear Energy
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May 14,1993 Docket No. STN 52-001
(
l Chet Poslusny, Senior Project Manager i Standardization Project Directorate l
Associate Directorate for Advanced Reactors and License Renewal Office of the Nuclear Reactor Regulation
Subject:
Submittal Supporting Accelerated ABWR Review Schedule - Clarification of j SSAR Subsection 3.5.1.1
Dear Chet:
Enclosed are SSAR markups addressing the questions raised at the May 11,1993 GE/NRC conference call pertaining to Subsection 3.5.1.1, Internally-Generated Missiles (Outside Containment).
Please provide a copy of this transmittal to Butch Burton. i Sincerely, l
Y Jack Fox Advanced Reactor Programs cc- Gary Ehlert (GE) ,
Norman Fletcher (DOE) l h
l
"'0033 "
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{ 9305200028 930514 l PDR ADDCK 05200001 1 A PDR
ABM nuioars REv B Standard Plant
.y Criterion 4 of 10CFR50 Appendix A, General l 3.5 MISSILEPROTECTION l
Design Criteria for Nuclear Power Plants.
The missile protection design basis for l Seismic Category I structures, systems and Potential missiles that have been identified l components is described in this section. A are listed and discussed in later subsections.
l tabulation of safety related structures, systems,
! and components (both inside and outside After a potential missile has been containment), their location, seismic category, identified, its statistical significance is l
- and quality group classification is given in determined. A statistically significant missile Table 3.2-1. General arrangement drawings is defined as a missile which could cause showing locations of the structures, systems, and unacceptable plant consequences or violation of components are presented in Section 1.2. the guidelines of 10CFR100.
l Missiles considered are those that could The examination of potential missiles and i l
result from a plant-related failure or incident their consequences is done in the follcwing including failures within and outside of manner to determine statistically significant l containment, erwironmental-generated missiles and missiles:
site-proximity missiles. The structures, shields, and barriers that have been designed to (1) If the probability of occurrence of the ,
withstand missile effects, the possible missile missfle (P3 ) is determined to be less than l
loadings, and the procedures to which each 10' per year, the missile is dismissed l l
barrier has been designed to resist missile from further consideration because it is impact are described in detail. considered not to be statistically si g nifi c a n t. )
3.5.1 Missile Selection and Description (2) If (P 3) is found to be greater than 10 l
per year, it is examined for its probability Components and equipment are designed to have of impacting a design target (P.,).
l
- l a low potential for generation of missiles as a
- basic safety precaution. In general, the design (3) If the productj of (P3 ) and (P2 ) I' I*
1 that results in reduction of missile-generation than 10 per year, the missile is l
potential promotes the long life and usability of dismissed from further consideration.
a component and is well within permissible limits of accepted codes and standards. (4) If the product of (P ) and (P.,) is 3
greater than 10'7 per year, the misiile is l Seismic Category I structures have been examined for its damage probability (P3). l analyzed and designed to be protected against a If the combined probability (i.e.7P3 x wide spectrum of missiles. For example, failure P2 xP = P4) is less than 10' per of certain rotating or pressurized components of year, tfie missile is dismissed.
l equipment is considered to be of sufficiently high probability and to presumably lead to (5) Finally, measures are taken to design generation of missiles. However, the generation acceptabic protection against missiles with of missiles from other equipment is considered to (P,) greater than 10'# per year to be of low enough probability and is dismissed reduce (P,), (Py ), and/or (P ), so from further consideration. Tornado-generated that (P4) is less than 10'j per 3year.
missiles and' missiles resulting from activities so4 %- releAe ci -
particular to the site are also discussed in this Protection of-enential-structures, systems section. The missile protection criteria to and components is afforced by one or more of the which the plant has been analyzed comply with following practices-351 Amendment 3
4
- sutme ABWR REV B .-
Standard Plant
~#
(1) Location of the system or component in an (6) Automatic depressurization system relief f valves; .l individual missile-proof structure; i
(2) Physical separation of redundant systems or (7) Standby diesel generator system; l
i components of the system for the missile CRD scram system (hydraulic and trajectory path or calculated range; (8) l electrical); -
- (3) Provision of localized protection shields or i barriers for systems or components; (9) Fuelpoolcoohng and cleanup system; (4) Design of the particular structure or (10) Remote shutdown pancl; j component to withstand the impact of the ,
most damaging missile; (11) Reactor protection system; J i
! l l
(5) Provision of design features on the (12) All containment isolation valves; l
! potential missile source to prevent missile gencration; and/or (13) HVAC emergency chilled water system; l
(14) HVAC systems required during operation of l (6) Orientation of the potential missile source l to prevent unacceptable consequences due to items (1) through (12); and j 1 missile generation.
(15) Electrical and control systems and wiring l
)
The following criteria have been adopted to required for operation of items (1) through l
l l j provide an acceptable design basis for the (14).
1 plant's capability to withstand the statistically The following general criteria are used in ,
, significant missiles reactor building. postulated inside the the design, manufacture, and inspection of ;
j d equipment: (
I (1) No loss of containment function as a result I of missiles generated internal to (1) All pressurized equipment and sections of
]
containment. piping that may periodically become
! isolated under pressure are provided with j pressure relief valves acceptabic under
- (2) Reasonable assurance that a safe plant shut-
' down condition can be achieved and ASME Code Section III. The valves ensure
- that no pressure buildup in equipment or maintained.
piping sections exceeds the design limits (3) Offsite exposure within the 10CFR100 of the materials involved.
j j guidelines for those potential missile damage events resulting in radiation (2) Components and equipment of the various activity release. systems are designed and built to the stan-6.pd -
A dards established by the ASME Code or other
] ,
The systems requiring protection are:
equivalent industrial standard. A strin-l gent quality control program is also en-i forced during manufacture, testing, and in-i (1) Reactor coolant pressure boundary;
! (2) Residual heat removal system; (3) Volumetric and ultrasonic testing where re-s quired by code coupled with periodic inser-
- (3) High pressure core flooder system; vice inspections of materials used in com-ponents and equipment add further assurance j (4) Reactor core isolation cooling system; that any material flaws that could permit j
' the generation of missiles are detected.
(5) Reactor building cooling water system; l
I i 35-2
[ Amendment t7 i
l
! insert a
~
(4) The failure of nonsafety-related equipment, components, or .
structures whose failure could result in a missile do not
- cause the failure of more than one division of safety-related ,
equipment.
l (5) No high energy lines are located near the standby-gas treatment !
charcoal vaults, the offgas charcoal storage vault. or the spent fuel pool.
l l
l l
l l
1 I
y
ABWR n A61o u s
~
Standard Plant REV.A 3J.1.2.3 Evaluation of Potential Gravitational Missiles Inside Containment Gravitational missiles inside the containment ]
have been considered as follows. ,
Seismic Category I systems, components, and j For local shields and barriers see the response structures are not potential gravitational mis- {
to Question 410.9. site sources. )
l 3.5.1.2 Internally Generated Missiles (Inside Non-Seismic Category I items and systems Containment) inside containment are considered as Follows: l Internal missiles are those resulting from (1) Cable Tray l plant equipment failures within the contain- !
ment. Potential missile sources from both All cable trays for both Class 1E and non- l rotating equipment and pressurized components are Class IE circuits are seismically supported !
considered. whether or not a hazard potential is !
evident. j 3.5.1.2.1 Rotating Equipment (2) Conduit and Non-Safety Pipe By an analysis similar to that in Subsection .
3.5.1.1.1, it is concluded that no items of Non-Class IE conduit is seismically sup- !
rotating equipment inside the containment have ported if it is identified as a potential j the capability of becoming pr tential missiles. hazard to safety-related equipment. All i All reactor internal pumps are incapable of Nuclear Island non-safety related piping 1 achieving an overspeed condition and the motors that is identified as a potential hazard is and impellers are incapable of escaping the seismically analyzed per Subsection casing and the reactor vessel wall, respectively. 3.7.3.13.
All drywell cooler fans, re designed such (3) . Equipment for Maintenance j that their blades are incapable of leaving the ,
case. All other equipment, such as hoists, that is required during maintenance will either be i 3.5.1.2.2 Pressurized Components removed prior to operation, moved to a '
location where it is not a potential hazard Identification of potential missiles and their to safety- related equipment, or seismically consequences outside containment are specified in restrained to prevent it from becoming a Subsection 3.5.1.1.2. The same conclusions are missile. - See Sub- section 3.5.4.7 for COL drawn for pressurized components inside of con- license information.
talment. For example, the ADS accumulators are moderate energy vessels and are therefore not 3.5.1.3 Turbine Missiles considered a credible missile source. One additional item is fine motion control rod drives See Subsection 3.5.1.1.13.
(FMCRD) under the reactor vessel. The FMCRD mechanisms are not credible missiles. The FMCRD ~ -
housings are designed (Section 4.6) to prevent ,
any significant nuclear transient in the event of a drive housing break.
i I
i l
I Amendment 3.54 l
1
_ _ _ , . -- , i