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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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GENuclearEnergy C+neralDectric Company 175 Curtner Avenue. San Jose. CA 95125 May 28,1993 Docket No. STN 52-001 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 - Chapter 8 Modifications
Dear Chet:
Enclosed are SSAR markups to Chapter 8 material that resulted from the GE/NRC conference call on May 27,1993. The following items are addressed:
Confirmatory Items 8.s3.3.10-1,8.3.8.6-1, and 8.3.8.7-1 Please send copies of this transmittal to John Knox and Dale Thatcher.
Sincerely, brJNF _;
Jack Fox -
Advanced Reactor Programs cc: Bob Strong (GE)
Norman Fletcher (DOE) t I
- 030041
}f0 ga6oMi un%2 si A
1
~
(see 8.3.4.15). The ABWR therefore exceeds the requirements of the policyisge. t h e r- beh dt N r
@ y y 9ifl " 5 to .<clo r el C n tend [cr ike frofr&ta 8.3.2 DC Power Systems ,3 g fever 595 e"Sf ancI E<f orf me n t 89 l M'" # # "
8.3.2.1 Description ( C5 tkA' Sf*"d'"d' jI,
\,NrHe A 60r7 fu II3 meeis +he V N 'e"it
- ~ ~ ~ - - -
8.3.2 1.1 General Systems A DC power system is provided for switchgear control, control power, instrumentation, critical motors and emergency lighting in control rooms, switchgear rooms and fuel handling areas. Four independent Class 1E 125 Vdc divisions, three independent non-Class lE 125 Vdc load groups and one non-Class 1E 250 Vdc computer and motor power supply are provided. See Figures 8.3-4 for the single lines.
Each battery is separately housed in a ventilated room apart from its charger and distribution panels. Each battery feeds a de_ distribution switchgear panel which in turn feeds local distribution panels and de motor control centers. An emergency eye wash is supplied in each battery room.
All batteries are sized so that required loads will not exceed warranted capacity at end-of-installed-life with 100 percent design demand.
The capacity of each of the four redundant Class 1E battery chargers is based on the largest combined demands of the various continuous steady-state loads, plus charging capacity to restore the battery from the design minimum charge state to the fully charged state within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (per technical ,
specifications), regardless of the status of the plant during which these q' 1 demands occur fsee o.3.J.. M u h p lh8.3.2.1.1.1 Class 1E 125 Vdc System hMA <<h C I
@f >I The 125 Vdc system provides a reliable control and switching power source for the Class 1E systems.
Each 125 Vdc battery is provided with a charger, and a standby charger shared by two divisions, each of which is' capable of recharging its battery from a discharged state to a fully charged state while handling the normal, steady-state de load.
Batteries are sized for the de load in accordance with IEEE Standard 485.
The batteries are installed in accordance with industry recommended practice as defined in IEEE 484, and meet the recommendations of Section 5 of IEEE 946 (see 8.3.4.32).
In accordance with this standards, each of the four Class 1E 125-volt batteries:
- 1) is capable of starting and operating its required steady state and transient loads, c:\ow62\ch8/ch8 draft.wp March 30, 1993 .
.xv
n N
MARK-UPjTEXT INSERTS
[ ,
INSERT Ah (NRC request to close iter.j 8.3. 3.14-1 per 5-24-93 phone c 1) l There are three automatic switching modes for the CVCF power supplies, any j of which may be initiated manually. First, the frequency of t e output of the inverter is normally synchronized with the input ac power. the frequency of ,
the inpu: power goes out of range, thfpowersupplyswitc s over to internal synchronization to restore the frequenpy of its output, witching back to ,
external synchronization is automatic pnd occurs if th frequency of the ac power has been restored and maintained} for approxima ly 60 seconds.
The second switching mhde is from tc to de f the power source, If the i voltage of the input ac poweiN is less than 88% f the rated voltage, the input is switched to the de power supply. Tfeinpq.. is switched back to the ac power after a confirmation period of approximate 1 60 seconds.
The third switching mode is betwe'bphe inverter and the voltage regulating tran g r ymewhich receives power froftbe same bus as the primary source. If any of the conditions listed below cur '
voltage regulating trasfErnierr- - d, the power supply is switched to the /
~
(a) Output voltage out of rati by mc re than s or minus 10 per cent (b) Output frequency out of ing by more than pl%s or minus 3 per cent (c) High temperature ins de of panel
, (d) Loss of control wer po/supply /
/ /.
(e) Commutation/fa'ilure
/ '
(f) Over-current of smoothing condenser j
(g) Loss of' control power for gate circuit (b) Incoming MCCB trip \
N\
(i) Cooling fan trip \ ,
\!
s/INSERT AC (NRC request to close item 8k.3.8.6-1 per 5-27-93 phone call) ,5 / i
./
The battery chargers are designed to prevent the ac power supply from becoming a load on the battery. They also have provisions to isolate transients from the ac system from affecting the de system; and conversely, j provisions to isolate transients from the de system from affecting the ac ;
system. The battery charger system is sized in accordance with the guidelines '
of IEEE 946. The design of the de system includes the capability to J periodically verify the required capacity for each of the battery charger power !
supplies (see 8.3.4.35). l macnw \
the remaining ac power divisions. The plant design and circuit layout from
~
these de systems provide physical separation of the equipment, cabling and instrumentation essential to plant safety.
Each division of the system is located in an area separated physically from other divisions. All the components of Class 1E 125 Vdc systems are housed in Seismic Category I structures.
8.3.2.1.3.1 125 Vdc Systems Configuration Figure 8.3-4 shows the overall 125 Vdc system provided for Class 1E Divisions I, II, III and IV. One divisional battery charger is used to supply each divisional de distribution panel bus and its associated battery. The divisional battery charger is normally fed from its divisional 480V MCC bus, with no automatic interconnection or transfer between buses. Also, there are no manual interconnections between de divisions except those involving the standby battery chargers, as described below.
Each Class 1E 125 Vdc battery is provided with a charger, and a standby charger shared by two divisions, each of which is capable of recharging its battery from a discharged state to a fully charged state while handling the normal, steady-state de load. Cross connection between two divisions through a standby charger is prevented by at least two interlocked breakers, kept normally open, in series in each potential cross-connect path. (See Figure 8.3 4 and Subsection 8.3.4.18.)
The maximum equalizing charge voltage for Class 1E batteries is 140 Vdc.
The de system minimum discharge voltage at the end of the discharge period is 1.75 Vdc per cell (105 v lts for the battery). The operating voltage range of Class 1E de loads is 100 to 140V.
As egeneselrequiremenesEhebatterieshavesufficient stored energy to -
operate connected Class 1E loads continuously for at least two hours without it i c recharginL_/fhe DivisionfYbattery wh'fdh~controTf E RCIC system is
~
~
rsufFeient for eisht hours durine dation bl*ckout>G DurEs~~.12qve,nt]L g ,_ _
._ D also ex2$Ed the
,} wtimes e mthese the batteries load reductions d i" -- _
are available (See Subsection 19E.2.1.2.2). Each distribution circuit is capable of transmitting sufficient energy to start and operate all Jaguirap_.1nads in that circuit.
g3flN QA &pK f h, Co*f A 1 ad capacity ina ysis has been performed based on IEEE 485-1978, and _
j submitted on the docket for estimated Class 1E de battery loads as of September, 1989. A final analysis will be performed when specific battery.
parameters are known (see 8.3.4.6).
An initial composite test of onsite ac and de power systems is called for as a prerequisite to initial fuel loading. This test will verify that each battery capacity is sufficient to satisfy a safety load demand profile under the conditions of a LOCA and loss of preferred power.
Thereafter, periodic capacity tests may be conducted in accordance with IEEE Std 450. These tests will ensure that the battery has the capacity to continue to meet safety load demands. ,
c:\ow62\ch8/ch8 draft.wp m ch 30, 1993 __ _ _ _ _
l l
hg-g'
, N UP N NSERTS- -
A capacity and voltage drop analysis will be performed in accordance with IEEE 79 141 to assure that power sources and distribution equipment will be capable of transmitting sufficient energy to start and operate all required-loads for all (0[/l '
plant conditions. ;
Q _ - . . - - . - _
's INShTS (87 CONF) $
'3
/
/
(7) The \bos s tie arrangment, /and the capacityiand capability of the CTG,j 's i
designebsuch that the time to place the,CTQ on line to feed any pne train ofshutdowngads ( fe., includes manual'conhection to any one Class lE '
bus) shall be w{thi 10 minutes. i INSERT T (87 CONF / 1.155, Sect. 3.3.5 assessment)\
/ \ ; N ,
ThereliabilityjdtheCTG'shquidmeet or exceed 95 perc t; as determined in ,
NSAC-108 or egntvalent methodhlogy.
\ i s '
\accordancewit INS-ERT U 7 CONF - RG 1.155, Sect. }.3.5 asses ment)
N j \
\
N /
- 6. TE - tric Power Research Institute, "Re ility of Emergency hfiesel G 2hrators at U. S . NuclearJouar--Ph ,
NSAC-lO8,SeptemberII86.
\
.X s WSERT V (6'6 CONF) s /
Light. fixtures 13 safety areas a seismica ly support , an are design d with appropriate grids \pr diffusers such that b oken materia ill be contai ed and
/
/ willnotbecomeahjardto rsonnel or s fety equipment' ring or.follod ng a l seismic event.
INSERT U (Needed to ack ITAAC)**
\ x Displays provide in the Mai Control R m R) consist of (but are t necessarily lir ted to) the fo lowing: Ma Generator output voltage, . peres, ;
watts, VARS .r power factor), ec ; nc , nd synchronization; also, distributio system medium voltag h(M/ swit.chgear voltages, feeder and 1 ad 7 amperes, d circuit breaker positihar.
Manua controls are provided in the'M R or the Main Generator output circuit breaker, the medium voltage (M/C)/switchg k feeder circuit breakers, and load circuit breakers to power centers or! motor c6ntrol centers. ,
i i
f P
JghW6rishyp ,
ayjf,~]993'~
s r
1 i
ABWR is designed in accordance with all criteria. Any exceptions or j clarifica.tions are so noted. ;
(1) General Design Criteria (CDC):
i (a) Criteria: CDCs 2, 4, 17, and 18. ,
(b) Conformance: The de power system is in compliance with these GDCs .
The GDCs are generically addressed in Subsection 3.1.2.
(2) Regulatory Guides (RGs):
(a) RC 1.6 - Independence Between Redundant Standby (Onsite) Power Sources and Between Their Distribution Systems s
lbd (b) RG 1.32 - Criteria for Safety-R tad Electric Power Systems for N' , eid) - Nuclear Power P1 ,
h tovea$elSeit8H15 f j 1# + Fuses cannot be periodica11* tested4 and are exempt fro such i irements per Section 4.' EEE 741.
(c) RC 1.47 - Bypassed and Inoperable Status Indication for Nuclear
'((
V Power Plant Safety Systems -
(d) RG 1.63 - Electric Penetration Assemblies in Containment Structures '
for Light-Water-Cooled Nuclear Power Plants (e) RG 1.75 - Physical Independenes of Electric Systems i The DC emergency standby lighting system circuits up to the lighting l fixtures are Class 1E associated and are routed in seismic Category I raceways. However, the lighting fixtures themselves are not seismically qualified, but are seismically supported. This is acceptable to the Class 1E power supply because of over-current ,
protective device coordination. The cables and circuits from the power source to the lighting fixtures are Class 1E associated. The bulbs cannot be seismically qualified. This is why the circuits are ;
Class IE associated. The bulbs can only fail open and therefore do
+
not represent a hazard to the Class 1E power sources.
Besides the emergency lighting circuits, any other associated ;
circuits added beyond the certified design must be specifically identified and justified. Associated circuits are defined in Section ;
5.5.1 of IEEE 384-1981, with the clarification for Items (3) and (4) l that non-Class 1E circuits being in an enclosed raceway without the ,
required physical separation or barriers between the enclosed raceway and the Class 1E or associated cables makes the circuits (related to the non-Class 1E cable in the enclosed raceway) associated circuits.. l (f) RG 1.106 - Thermal Overload Protection for Electric Motors on Motor-Operated Valves Safety functions which are required to go to completion for safety have their thermal overload protection devices in force during normal l c:\ow62\ch8/chSdraft.wp March 30, 1993 45-
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MARK-UP TEXT INSERTS f!S h E (35 CONF) '
N j(5) Other'Cniteria p/
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IEEE 741\- andard fit Criteria for the Protection of C)tss lE Power Systems l(a) and Equipmenth Nuclear Power Gene:ating Stations"f
/ '
The ABWR fully meet the requirements of this standard.
/ i INSERT F (35 CONF) \
(5) Other Criteria /
(a) IEEE 946 - " Recommended Practice for bbe Design of Safety-Related DC ,
1 AuxiliaryPowerSystemsforNuc)earPowkGeneratingStations" l The ABWR fully meets the requ rements of th etandard.
j t INSERT G (65 CONF) /
/
This equipment is des >Igned and qualified to survive the comb sed effects of temperature, humidJty, radiation, and other conditions related ith a LOCA or other design-basisi event environment at the end of their qualifi and/or /
design life. j INSERT H, (43 CONF)
These/ overload bypasses meet the requirements of IEEE 603, and are capabl of/
l being periodically tested (see 8.3.4.24). ,/
INSERT I (71 CONF) -
1__ 7 _ ___. - - - - -
Section 5.2 of IEEE 308 is addressed for the ABWR as follows:
Those portions of the Class 1E power system that are required to support safety systems in the performance of their safety functions meet the requirements of ,
IEEE 603. In addition, those other normal components, equipment, and systems (that is, overload devices, protective relaying, etc) within the Class 1E power j - -
j, system that have no direct safety function and are only provided to increase l[
the availability or reliability of the Class 1E power system meet those j\ql~ ,
requirements of IEEE 603 which assure that thoce components, equipment, and / ;
systems do not degrade the Class 1E power system below an acceptable. level.
l However, such elements are not required to meet criteria as defined in IEEE 603 /
for: operating bypass, maintenance bypass, and bypass indication."
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