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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 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 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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l' . 3 Interface Requiremonta The standard design of the A!WR is based on certain assumptions concerning the desis bases which shall be eet by the COL applicant in designing the portion ]
d th offsita power systea in his acope, as defined in subsection 8.2.1.1.
fl.a w dasigr tm s e s assunptions are listed here which the COL applicant shall fT c e ! M
,;) ~he offsite system shi.11 consist of a minimum of two independent offsite transmission circuits from the trancmission network.
(2) Voltage variations of the oftalte transmission network shall be no more than plus or minus 101 of nominal value during steady state t,peration.
- 3) The normal steady state frequsney et the off61te transmission network shall W within plus or minus 2 hertz of 60 hertz during recoverable periods of svstem ins t.abi li t y wi Trm ettsite transmission circuits from the transmission network through and in.luding the main step-up power and reserve auxiliary transformers shall be sized to supply their load requirements, during all design operating moves, of their respective Class lE divisions and non-Class lE load groups.
C'>, The impedances of the main step up power and reserve auxiliary transformers
- c. hall be compatible with the interrupting capability of the plant's circuit nr o rru;st ing devices ;
it ihe independonce at offsite transmission power, instrumentat.Lon,=and control c!tcuits shall be compatible with the portion of the offsite trur.smiss on power, instrumentation, and control circuits within GE's design scupe
('i 'nnt r uaentation and cont rol system loads shall be compatible with the rpecits and capability design requirement: of DC systems within GE's
.n 6n 5cePe K '.onu ptuxi Des !gn (1 'altage variations of the offsite transmission network are no more than plus er minus 10% of nominal value during steady state operation.
(2) :ne norral steacy state frequency of the offsite transmission network are a thin plus or minus 2 hertz of 60 hertz during recoverable periods of sestum innrabilits t
c . \ wa \e5 \enerd2 / 8D4825. .to tro vertwr it,, 1993 _ . _ _ --- _ - . . . _ . _ - _ _ _ _ _ - - . _ _ _ _ - .
.:+ir-L.i, :
4
- Note
- the following boxes encircle two different options for Item (3). The NRC is requested to review bcth options in preparation for further discussion with GE.} -,,
--- c==m -- =
l_ .
!3) Separation betwem th< main and reserve offsite circuits in Sreater than ths height of any component (1 e., transmission lines or tie lines, towers, or o tt uc tu r s ) whose f ail ure could otherwisc jeopardise both This aeparntion criteria also applies to the following:
y offsite circuits 0
Circuits on the righ voltage side o f th r. main power step up transformer
[Y separated f rom c i cuits on the low voltage side of the reserve auxiliary trarasfo' mer . and
[
Circuits on the hiyh voltage side of the reserve auxiliary transformer separated f roa c'. rc uits or, the low voltage side of the main power step-up transformar.
.n-- . - - . .- ==~
!31 Goparation between the main and reserve affaite circuits (e.g. the l trar.smission lines, tic l i n e r. , switching stations., transformers, bus ducts p a w s. r and instrusentation and control cableo), is greater t.han the hei5 ht j of any component which could cause loss of both off site circuits up to the
- -o tnt at which the cottponent can no longer affect both circuits.
L_..-___...-._ ~_ -
(4- T r.c ma!n power switching station are separated by a minimum of 15.24m from
- be tererve powel switching station. (Note
- the switching' stations may be in the same switchyard or separated switchyards provided the required m i ni mun- separation is maintained.)
(S) '"h e r e s e rv e auxilinry transformer is separated by a minimum of IS.24m from the unit auxiliary transformerb and the main step-up power transformer. In addition, the cair: neep up power nnd reserve auxiliary transformers are ptovidui with separato oil collection pits and drains to a safe disposal n:oo, and arti provided with fire protection deluge systems as specified in s e c t i or: 4A 4.6 (6; lustrumentation and control circuits of the main power offsite circuit i( ., normal proferred offsite circuit) are separated from the instrurrentation and control circuits for the reserve power circuit (i.e.,
n'rcrnnte preferred offsite circuit) in the sace manner as the separation
- vr the offaite power feeder
~
- he site specific configuration of the incoming transmission lines are ane;yr.d to annurc t h s. : the expected availability of the offsite power is as good as the as amptions made in performing the plant probability risk analysis (see item bi 2 of Table 8.2-1. and Chapter 19).
+
- i; W u nherD2/ ASLE25.wp n uev 16, 1993 w A 3w- a.- --e-E ' * + - -n-e
.. - t: j 4f
$. 8 ? Th o f f r i t e transmission lines f r u.n the transmission network to the ex i ; t:i n g stations de not have a common takeoff structure or use common c
'.tucturco for support
'4' The ti I I':e s frou, th., nnin step-up power and reserve auxiliary
- anniu mers to thet: switching stations do not have a common takeoff
.iu. m - o r ut.e cocumcn structures for support.
.' :.e two effsite circut*s from the transmission network are designed to e .nialze t l.e i r s irr ui taneous loss as a result of failure of any transmission
+e.er rossing lIne. single breaker, av .hgear bus, or cable.
- 1 ne offsit.n circuito nie designed in act.srdance with industry recommended
- n: rice ir. order to c;inimize the likelihoed that they will fail while
-p .. r e t ' y under the e r.vi t onme n t al conditions (such as, wind, ice, snow, t si t :.1 : .p . t e mp.,; n , u r e vartations. or flood) to which they are rubject.
,' bynteci stadies are pectormed to dcmnnatrate that the offsite transmission r e t <n ri sil. not degrace be ow n icvel consistent with the availability mals af the plant as a resule of contingencies such as loss of any of the ,
c11 ewing elements Nuclear power generating unit, largest generating unit, ws t critical t rans:nission ci rcui t or intertie, or largest load.
ils ightning arresters nic piovided for each phase of all tie lines connecting th., plant electrical svstems to the switchyard and transmission network.
"hese arresters are connected to the high-voltage terminals of the main >
rep up poset and r e r.c rve auxiliary transformers. Transformers are also
+nunded (lo :'h e main step-up powet and the reserve auxiliary tranuformers are designed l-a.a.t th. i c qu i r e c.c n t s of ANSI Standard C57 12.00 (Referen a 8.2-2), j
. c r.o : r. ; F c q u i r c::.e n t s, for L.1 quid-Immersed Distribution, Power and Regulating rnn,toraer,
- t. ircuit breakers and disconnect switchca are sized and designed in ecordsnce with thc latest revision of ANS1 Standard C37.06 (Reference
, J-l , Frcferred Ratings and Related Capabilities for AC High-Voltage
- eicu W e nb i s R eed on a Syuare trical Current Basis. All circuit breakers ne purchased new (1 e. not refurbished used ones) in accordance with ewiutton o f t.T,c : n f n rma t i on No t ic e 88-46 (see Question /P.esponne 435.56 in
.ection 20 3 RA1 r'
.' . be ma in ;+we t switching starinn hnr, nr icast two full caparity main buses
, tanged such that An'. incaming or u going trnnnmission line can be switched without e.ffecting anothe: line; Any single cit eult breaker can-be isolated f or tunintenance without E
interruprir.g r.ervice to any circuit; and Fnuits of n single ronin bus are isolated without interrupting service to i any circuit.
L
.i m c.,et' no\ w o 2/823&oM w ao we r 4, 1993
. . ..w :- 's ! ! d f;*
.- 4 kl7The main power . transformer consists of three normally energized m!ngic phane transformern with an additional installed spare. Provisions sre made to peruit connecting and energizing the spare transformer in no core than 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> following a failure of one of the normally ensrgized t r annf ortne rs .
- i. l S Ftcvisions are made to synchronize the unit through the main poser usit'hing station's circuit breakers.
- 10 til i slay schemes used for protection of the offsite power circuits and the switching station's equipment include primary and backup protection isatures. All breakers are equipped with dual trip coils. Each protection ircuit which supplies a trip signal is connected to a separate trip coil.
All equipment and eshling nasociated with primary and backup protection lrcuits are physically separated from each other.
(/U he DC power needed tc operate primary and backup protection and control maipment of the offsite power system is supplied from two separate
.. itching station batteries located in each switching station, each with n
- nttery charger fed from a separate AC bus. Each battery is capable of supplying the DC power required for normal operation of the switching
-tation's equipment Each charger is capable of supplying the required aads wnile recharging its bartery.
(7; Ao rtdandant low vcitsgr AC power supply systems are provided to supply AC e r.v a r to tha switching station's auxiliary loadn. Each system is supplied from saparate, independent AC buses The capacity of each system is n
2 equate to meet the AC power requirements for normal operation of the es t e c h i rig 9 t a t i on ' s equipment.
(2; tech transformer has primary and backup protective devices. DC power to the rimary and backup devices is supplied from separate non Class lE DC
.rorens.
(7' he calculated rated conditions for the main stop up power transformer in
'500 mVA at a powet factor of 0.9 and a voltage of 26.325 kV plus or minus C1 The main stop up powar transformer and high voltage circuit has d fic ien t impedance to limit the primary side maximum available fault trent contribution from the system to that required by the main generator tput circuit breaker as defined in 8.2.1.2.
I2c ~te affsite transmisnian circuits from the transmission network throuSh and
.nc luding the main step-up power and reserve auxiliary transformers are
, ired to supply their load requirements, during all design operating modes, 4 thait respective Class lE divisions and non Class lE load groups.
(2' ;Le impedances of the main step-up power transformer and reserve auxiliary a snsformet are competible with the interrupting capability of the plant's ircuit interrupting de'.tces e n e c ht s ewv:32/82M825. wp nevevec* 16. 1W 3 4-r
, . ., i!!!5 -i," ?
r N
- i 2 b 'ihe offsite transrcission circuits from the transminolon network through and
'.ncluding the main step up power and reserve auxiliary transformers are cesigned and coat,tructed to withstand the mechanical and thermal stresses
' t c:z t he worst case faulta.
- 1 ' ~he caleeluted rated conditions for the r e a c rve auxi.inry transformer is cln at u 0.9 power factor. LThen coordinated with the desi n5 of the reserve auxiliary transformer, the offsite transmission system circuit.
suprorts a maximus allowab'lo voltage dip of 20% duri+ig the starting of
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< TRANS,4CTION REPORT-) i l - . 4, ,-
11-16-1993(TUE) 23:20 't e
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3 t r, *;it T i t1C t511I&;Iora 5r' TION PG; DURAT IOr6 t10DE RESULT- l;
. 1 1:-15 23: 1 ~' 4AE 925 1193 6 ~0*O2'48" tORti . E - OK i t
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