DOP 6900-13,Revision 1, Station Battery Isolation & Return to Normal for Discharge Testing U3 250 Vdc Battery.| ML17174A590 |
| Person / Time |
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| Site: |
Dresden  |
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| Issue date: |
07/31/1979 |
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| From: |
COMMONWEALTH EDISON CO. |
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| To: |
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| Shared Package |
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| ML17174A578 |
List: |
|---|
| References |
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| 6900-13, NUDOCS 8012160539 |
| Download: ML17174A590 (5) |
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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20211C3311999-04-30030 April 1999
Rev 2.0 to Generic ODCM for Dresden,Quad Cities,Zion, Lasalle,Byron & Braidwood
ML20205A0871999-03-22022 March 1999
Revs to Odcm,Including Rev 2.0 to Chapter 10, Radioactive Effluent Treatment & Monitoring & Rev 1.9 to Chapter 12, Radiological Effluent Technical Stds (Rets)
ML20199E0361999-01-12012 January 1999
Proposed Tech Specs Section 3.10, Fuel Handling & Storage, Eliminating Reference to Initiation of Generating Station EP Action That Is Incorrect & Not Part of Reason for Min FSP Water Level TS
ML20196F6451998-11-30030 November 1998
Proposed Tech Specs 3/4.1.A,3/4.10.B & 3/4.12.B,proposing Changes to Relocate Requirement to Remove RPS Shorting Links Which Enable non-coincident Scram for Neutron Instrumentation,To Licensee Controlled Document
ML20237A8651998-08-0707 August 1998
Qualified Unit 1 Supervisor Initial & Continuing Training Program
ML20151S2691998-07-31031 July 1998
Rev 1.8 to Chapter 12 of Dresden Station Odcm
ML20217N9331998-04-30030 April 1998
Rev 1.7 to Chapter 12 of Dresden Station Odcm
ML20216H4321997-12-31031 December 1997
Revs to OCDM for Braidwood,Including Rev 1.8 to Chapter 10, Rev 1.9 to Chapter 11,rev 2 to Chapter 12 & Rev 2 to App F
ML20216H8551997-12-31031 December 1997
Revs to OCDM for Dresden Station,Including Rev 1.9 to Chapter 10,rev 1.3 to Chapter 11,rev 1.6 to Chapter 12 & Rev 1.1 to App F
ML20198M2491997-12-18018 December 1997
Revs to Ocdm,Including Rev 1.3 to Chapter 11, Radiologicial Environ Monitoring Program & Rev 1.6 to Chapter 12, Radiological Effluent Technical Stds (Rets)
ML20216H8241997-10-31031 October 1997
Revs to OCDM for Byron Station,Including Rev 1.3 to Chapter 10,rev 1.5 to Chapters 11 & 12 & Rev 1.3 to App F
ML20216H9041997-10-31031 October 1997
Revs to OCDM for Zion Station,Including Rev 1.9 to Chapter 10,rev 1.1 to Chapter 11,rev 1.9 to Chapter 12 & Rev 1.1 to App F
ML20198P1601997-10-20020 October 1997
Rev 1.5 to Odcm,Chapter 12
ML20212A2941997-10-0202 October 1997
Rev 56 to Dresden Nuclear Power Plant for Insertion in NRC Security Plan.Rev Withheld
ML20216C6381997-08-29029 August 1997
Proposed Tech Specs,Incorporating New Siemens' Methodologies That Will Enhance Operational Flexibility & Reducing Likelihood of Future Plant Derates
ML20196G8781997-07-18018 July 1997
Proposed Tech Specs,Meeting Administrative Commitment Resulting from from Plant TS Improvement Program
ML20148K6141997-06-0505 June 1997
Proposed Tech Specs,Updating Revised TS to Format Consistent W/Recently Approved TS Upgrade for DNP & Proposed Other Miscellaneous Changes Re Decommissioning Status of Unit 1
ML20141A6411997-05-31031 May 1997
Rev 1.4,Chapter 12 to Radiological Effluent Technical Stds (RETS) of ODCM
ML20216H8691997-03-31031 March 1997
Revs to OCDM for LaSalle Station,Including Rev 1.8 to Chapter 10,rev 1.9 to Chapter 11,rev 1.8 to Chapter 12 & Rev 1.7 to App F
ML17187A7991997-02-17017 February 1997
Proposed Tech Specs 3/4.7.K & 3/4.8.C Re Issues Resulting from Comeds Efforts to Reconstitute Design Basis of Chrs
ML20137C0011997-01-31031 January 1997
Odcm,Dresden Annex Revs 1.9 to Chapter 10, Radioactive Effluent Treatment & Monitoring, 1.2 to Chapter 11, Radiological Environ Monitoring Program & 1.3 to Chapter 12, Radiological Effluent Technical Standards
ML20135B0581996-11-25025 November 1996
Proposed Tech Specs,Submitting Update to Administrative Controls Section of TS Which Reflects Transition of Overall Corporate Responsibility for Storage of Spent Nuclear Fuel
ML20129F3231996-10-23023 October 1996
Proposed Tech Specs Replacing All Existing Pages of Unit 1 TS
ML20129C2391996-10-16016 October 1996
Proposed Tech Specs for Dresden 2 & 3 & Quad Cities 1 & 2, marked-up to Show Transition Verbiage
ML20129D3981996-09-20020 September 1996
Proposed Tech Specs 3/4.6.K,updating Pressure-Temp Curves to 22 Effective Full Power Yrs & TS Bases
ML20216H8841996-06-30030 June 1996
Revs to ODCM for Quad Cities,Including Rev 1.8 to Chapters 10,11,12 & App F
ML20113B6001996-06-20020 June 1996
Proposed Tech Specs,Incorporating New NRC Approved Thermal Limit Licensing Methodology in List of Approved Methodologies Used in Establishing Thermal Limits in Cycle Specific COLR & Change to Fuel Assembly Design Features
ML20112E6341996-05-22022 May 1996
Proposed Tech Specs Requesting Emergency Amend to License DPR-25 Temporarily Modifying Description of Certain Corner Room Steel Supports to Match Current Configuration Until Mod During Next Refueling Outage
ML20086D4741995-06-30030 June 1995
Proposed Tech Specs Re TS Upgrade Program for Dresden Units 2 & 3 & Quad Cities Units 1 & 2
ML20092C8091995-05-12012 May 1995
Rev 2, Shroud Repairs Program for Dresden Units 2 & 3, Back-up Calculations for RPV Stress Rept Number 25A5691, May 1995
ML20087H8651995-05-0202 May 1995
Proposed Tech Specs Re TS Upgrade Program Section 3/4.10
ML20085M6171994-07-31031 July 1994
Rev 1.1 to Chapter 12, Radioactive Effluent Technical Stds of Dresden ODCM
ML20063F9011994-01-31031 January 1994
Rev 1.0 to Chapters 10,11,12 & App F to Odcm,Dresden Station Units 2 & 3
ML17179B0931993-09-10010 September 1993
Rev 2 to Dresden Station 3rd Interval IST Plan, Sections 2,13 & 14,pages 2-1,13-1 to 13-4 & 14-40,respectively
ML20058E8751993-09-0303 September 1993
Revised AOP-6.3, Loss of RHR Shutdown Cooling
ML20058E8351993-06-10010 June 1993
Revised AOP-7.4, Control Room Inaccessibility
ML20127D0691992-12-30030 December 1992
Corporate Emergency Response Organization Required Reading Package 92-11
ML20125D6381992-12-0808 December 1992
Proposed Tech Specs 3/4.1 Re Reactor Protection Sys
ML20058E8681992-09-29029 September 1992
Rev 56A to AOP 1BOA PRI-5, Control Room Inaccessibility Unit 1
ML20106A6221992-09-15015 September 1992
Proposed TS 2.0, Safety Limits & Limiting Safety Sys Settings & 3/4.11, Power Distribution Limits
ML20081M1251992-08-31031 August 1992
Rev 17 to Procedure Dgp 03-04 Control Rod Movements
ML20099D7791992-07-29029 July 1992
Proposed Tech Specs Sections 1.0, Definitions, 3/4.0, Applicability & 3/4.3, Reactivity
ML20096F1161992-04-24024 April 1992
Proposed Ts,Changing OL Section 2.G Re Reporting Requirements
ML20081M1851992-01-31031 January 1992
Rev 17 to Procedure DAP 07-02, Conduct of Shift Operations
ML20081M1611991-11-20020 November 1991
Rev 0 to Procedure DAP 14-4, Control Rod Sequences
ML20058E8761991-11-18018 November 1991
Rev 56 to AOP Bwoa PRI-10, Loss of Rh Cooling Unit 1
ML20081M0311991-11-15015 November 1991
Rev 2 to Procedure Doa 0300-12, Mispositioned Control Rod (W-2,W-3)
ML20081M1721991-08-31031 August 1991
Rev 15 to Procedure DAP 07-01, Operations Dept Organization
ML20081M1401991-05-17017 May 1991
Rev 6 to Procedure DOP 0400-02, Control Rod Minimizer
ML20081M1971990-08-30030 August 1990
Rev 9 to Procedure DAP 07-05, Operating Logs & Records
1999-04-30
[Table view]
Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20211C3311999-04-30030 April 1999
Rev 2.0 to Generic ODCM for Dresden,Quad Cities,Zion, Lasalle,Byron & Braidwood
ML20205A0871999-03-22022 March 1999
Revs to Odcm,Including Rev 2.0 to Chapter 10, Radioactive Effluent Treatment & Monitoring & Rev 1.9 to Chapter 12, Radiological Effluent Technical Stds (Rets)
ML20237A8651998-08-0707 August 1998
Qualified Unit 1 Supervisor Initial & Continuing Training Program
ML20151S2691998-07-31031 July 1998
Rev 1.8 to Chapter 12 of Dresden Station Odcm
ML20217N9331998-04-30030 April 1998
Rev 1.7 to Chapter 12 of Dresden Station Odcm
ML20216H8551997-12-31031 December 1997
Revs to OCDM for Dresden Station,Including Rev 1.9 to Chapter 10,rev 1.3 to Chapter 11,rev 1.6 to Chapter 12 & Rev 1.1 to App F
ML20216H4321997-12-31031 December 1997
Revs to OCDM for Braidwood,Including Rev 1.8 to Chapter 10, Rev 1.9 to Chapter 11,rev 2 to Chapter 12 & Rev 2 to App F
ML20198M2491997-12-18018 December 1997
Revs to Ocdm,Including Rev 1.3 to Chapter 11, Radiologicial Environ Monitoring Program & Rev 1.6 to Chapter 12, Radiological Effluent Technical Stds (Rets)
ML20216H9041997-10-31031 October 1997
Revs to OCDM for Zion Station,Including Rev 1.9 to Chapter 10,rev 1.1 to Chapter 11,rev 1.9 to Chapter 12 & Rev 1.1 to App F
ML20216H8241997-10-31031 October 1997
Revs to OCDM for Byron Station,Including Rev 1.3 to Chapter 10,rev 1.5 to Chapters 11 & 12 & Rev 1.3 to App F
ML20198P1601997-10-20020 October 1997
Rev 1.5 to Odcm,Chapter 12
ML20212A2941997-10-0202 October 1997
Rev 56 to Dresden Nuclear Power Plant for Insertion in NRC Security Plan.Rev Withheld
ML20141A6411997-05-31031 May 1997
Rev 1.4,Chapter 12 to Radiological Effluent Technical Stds (RETS) of ODCM
ML20216H8691997-03-31031 March 1997
Revs to OCDM for LaSalle Station,Including Rev 1.8 to Chapter 10,rev 1.9 to Chapter 11,rev 1.8 to Chapter 12 & Rev 1.7 to App F
ML20137C0011997-01-31031 January 1997
Odcm,Dresden Annex Revs 1.9 to Chapter 10, Radioactive Effluent Treatment & Monitoring, 1.2 to Chapter 11, Radiological Environ Monitoring Program & 1.3 to Chapter 12, Radiological Effluent Technical Standards
ML20216H8841996-06-30030 June 1996
Revs to ODCM for Quad Cities,Including Rev 1.8 to Chapters 10,11,12 & App F
ML20092C8091995-05-12012 May 1995
Rev 2, Shroud Repairs Program for Dresden Units 2 & 3, Back-up Calculations for RPV Stress Rept Number 25A5691, May 1995
ML20085M6171994-07-31031 July 1994
Rev 1.1 to Chapter 12, Radioactive Effluent Technical Stds of Dresden ODCM
ML20063F9011994-01-31031 January 1994
Rev 1.0 to Chapters 10,11,12 & App F to Odcm,Dresden Station Units 2 & 3
ML17179B0931993-09-10010 September 1993
Rev 2 to Dresden Station 3rd Interval IST Plan, Sections 2,13 & 14,pages 2-1,13-1 to 13-4 & 14-40,respectively
ML20058E8751993-09-0303 September 1993
Revised AOP-6.3, Loss of RHR Shutdown Cooling
ML20058E8351993-06-10010 June 1993
Revised AOP-7.4, Control Room Inaccessibility
ML20127D0691992-12-30030 December 1992
Corporate Emergency Response Organization Required Reading Package 92-11
ML20058E8681992-09-29029 September 1992
Rev 56A to AOP 1BOA PRI-5, Control Room Inaccessibility Unit 1
ML20081M1251992-08-31031 August 1992
Rev 17 to Procedure Dgp 03-04 Control Rod Movements
ML20081M1851992-01-31031 January 1992
Rev 17 to Procedure DAP 07-02, Conduct of Shift Operations
ML20081M1611991-11-20020 November 1991
Rev 0 to Procedure DAP 14-4, Control Rod Sequences
ML20058E8761991-11-18018 November 1991
Rev 56 to AOP Bwoa PRI-10, Loss of Rh Cooling Unit 1
ML20081M0311991-11-15015 November 1991
Rev 2 to Procedure Doa 0300-12, Mispositioned Control Rod (W-2,W-3)
ML20081M1721991-08-31031 August 1991
Rev 15 to Procedure DAP 07-01, Operations Dept Organization
ML20081M1401991-05-17017 May 1991
Rev 6 to Procedure DOP 0400-02, Control Rod Minimizer
ML20081M1971990-08-30030 August 1990
Rev 9 to Procedure DAP 07-05, Operating Logs & Records
ML20058E8601990-04-30030 April 1990
Rev 55 to AOP 1BOA PRI-10, Loss of Rh Cooling Unit 1
ML20055C3401990-02-13013 February 1990
Revised Dssp Procedures,Consisting of Rev 2 to Dssp 100-B, Rev 2 to Dssp 100-B1 & Rev 3 to Dssp 100-A2/B2
ML20245L7651989-08-0707 August 1989
Rev 0 to Offsite Dose Calculation Manual
ML20150C1171988-02-29029 February 1988
Rev 1 to Dresden Nuclear Power Station Process Control Program
ML20237J8081987-08-31031 August 1987
Rev 0 to Emergency Plan Implementing Procedure EPIP 200-T4, Containment Radiation Time Dependent Correction Factors
ML20235S3091987-07-31031 July 1987
Rev 0 to NSHP-RP Guidance 1100-2, Radiation Chemistry Foremen Shift Coverage
ML20203L3551986-04-30030 April 1986
Rev 0 to Comm Ed Training Program Description for Station Control Room Engineer/Shift Technical Advisor
ML20205C8311986-04-30030 April 1986
Rev 11A to Offsite Dose Calculation Manual
ML20099D0241984-09-30030 September 1984
Rev 7 to Dts 1600-7, Unit 2/3 Integrated Primary Containment Leak Rate Test
ML20090H7611984-03-31031 March 1984
Procedure INPO 84-010(NUTAC), Vendor Equipment Technical Info Program
ML20070J0071982-10-0101 October 1982
IE Bulletin 79-14 & Tap Piping Evaluation,Quad Cities Units 1 & 2 & Dresden Units 2 & 3, Revision 0
ML20070H9951982-09-30030 September 1982
EDS-NUTECH Interface Control Instructions, Revision 0
ML20199E3821982-07-0707 July 1982
Rev 0 to Emergency Plan Implementing Procedure EPIP 500-9, Operational Check of Notification Phone List
ML20062B4351982-07-0707 July 1982
Public Version of Revision 2 to Emergency Plan Implementing Procedure EPIP 100-C7, Security Director & Revision 0 to EPIP 500-9, Operational Check of Notification Phone List
ML20062B1761982-06-30030 June 1982
Public Version of Revision 2 to Emergency Plan Implementing Procedure EPIP 100-C8, Rad/Chem Director. Revised Index of Station Group Director Duties Encl
ML20054J8691982-06-0202 June 1982
Public Version of Revised Generating Station Emergency Plan Environ Director Emergency Plan Implementing Procedures, Including Revision 2 to Procedure ED-3 Re Demand Polling of Meteorological Data
ML20054H1521982-05-28028 May 1982
Public Version of Generating Stations Emergency Plan Telephone Directory
ML20054H4291982-05-28028 May 1982
Public Version of Generating Stations Emergency Plan Telephone Directory
1999-04-30
[Table view] |
Text
. . . . . . llOl' 6900-13 sf11.*1*1.c. 1J !)!\'((fl\.Y I~ilJIAl'iON ,\'.;!) Hi*:t'll!<N TO ;*:o:m ..\L Rv *,1 i :d. on 1 I-OR 1nsr.:!/\.l\t;E Tl*:s:r ll~G 113 :~~:,o VDC BATTERY .l11ly 1979
~:.1. :**: ...:...:; :~* .
'rJic flll'Cf~il::'C nf f'his p1.'t)*C'~*l*n'c *is t.o 1*.,1*uv:i.dc tl1e srr:.ps *::*c<':;*;:;;:y to_.'i~;oL1tc thc* lJ3 250 VDC h:1tt*~1y r.,.r t!1c h:1tU*1y di:;cli.:1q~c i:>>*:;t ;*,nd
- .then rct11i-n t11c ll3 7.50 VllC hattr:1~y to no~*1q:1l.
. ..4. . .. ..
.
- . 'of .... --:: ...- - - - * : * -.... - -
- . * . :"_h D05 6900-2 (St;1ti.on B:.1ttc*i:y C:1 11:*icity Ti~:>t).
- ;'.2~:';;*: i):1r i::noo *6 (Bat t1:ry l1:i.:;ch;iq3e Ti*:; ts - load box c.-111ill.~<:ti.cin)
J. r2i::2321
~J 4,
<: 12E3055 r *
- c. .PRE.RE,QUlSITES
. **...* Not:i,fy the Shift Supervisor and the U3 Operator of the iritentiori
.to i~olate the U3 250VDC battery.
D. . PRECAUTIONS *
~. *pb~erve norm~! radiological precautions.
2, Wear proper safety .-ip.parel whlle in::;t;:illing and removing
E. LIMITATIONS AND LIMITATIONS
- 1. Non*e *
.F~ . PROCEDURE L * >VeJ:'ify that the U2 250 VDC battery is supp.lying its nonnal
- 2. .. Ver:ify that the U2 250 VDC battery charger is charging the V2 250 VDC battery.
- 3. **Verify that copper bus links are available for Reactor *.
_ ~~uildirig 250 VD~ ~CC No. 3 *(See operating engineer for:*
- , *.-~*c:opper. links). *
BATTERY ISOLATION
). Verify breaker. E-1 (Turbine Building 250 VDC MCC No. 3 **
- I,*: t,f':,:*t-q~\ 11 ~~ict:Q.i:i. Bllilding 250 VDC MCC No. 3). is open as noted on
.f'gtire 2. *
. Qperat51r---'------------ Date_ _ _"'-----_,..;.-
APPROVE[)
1 AUG2 3'79
DOP 0 1J00-13 P.1*:vi,;i.on 1 (b) T.1~stnl l t 1 10 coppl':r Ti 11ks in Re:; cl 1Jr P.1d.lrVi np, ?'..iO VDC
- 1 <.:c f:o. 3 to Turhi11e f:11ildin_ri_J.~O v6c ).;*i*:-c-*No-.- 3-:1-s
- ,)**~) t-C~.f .. o_fi_Fig u*re** :2 *.~*:-* -** *------**-* **-.****--*. -------- ... --- ---*******-- *-* . ******* ..... **--
01H~r:1tor: __ .. ***--**-- **--*-*****-- -*- D;1te (c) CLOSE hreaker E-l (T11*i'hi.11e 811i.icli;1g 250 VJ)C Ml~C No. 3 to -Ren ct or n1ri*l di ng____i5"()- \Ti-JC . . ;:ji~C ... tJo ~- **3; ----* * -*-**** **------ *--* ----
-*----* -*** * ** ---******--** .. __ ?___ ***-*-****-*--**-***-*-** **-****-*-
Opr.: 01 tor .. -****---*-*-*- ___ *--*** *-*--*-*-*- .D<1 t e (d) Oi'FN bn*i!kt~r A-*l. (113- /.'.iO VDCP.:1tt**cy ;11HI Ck1ri_;1~r Ft*Pd
. 1.0 T11rhinc !luil d i~;*g--/5o \iijc... i~<:c *:};o:*-3y ~~s *1;-;t_*(~;1 **0n *--
- t:;iii-1~r*e-T.--- ** -** -*-**--*-***** --** *---- **- --*-*****---
Operat~r_____________ Date (e) OPEN hrc:iker A-J _(!_1_~ __ 259 VDC TL-i.t tery C:l~1_:~E_ to U3 7.50 VDC Battery) as noted on figure 1.
Operat<?.r_*-----*- Date
- 5. *Verify that breaker 11.-2 (2/3. charger to B;1ttery) is OPEN as hoted in Figure I.
BACK TO NORMAL 6~ (a) CLOSE breaker A-3 (UJ 7.50 VDC Battery Charger to U3 250 VDC Battery) as noted on Figure 1.
Date (b) . CLOSE breaker A-1 (UJ 250 VDC 13att<.!ry and Charger Feed to Turbine Building 250 VDC MCC No. 3) as noted on Figure 1.
(c) OPEN breaker E-1 _(Turhine Building 250 VDC MCC No. 3 to Reactor Building 250 VDC MCC No. 3) as noted on Figure 1.
Oper~t~r---~----- Date_ _ _ _ _ _ _ _ __
(d) Remove two copper links in Reactor Building 250 VDC MCC No. 3 to Turhine Building 250 VDC MCC no. 3 as noted on Figure 2.
Operat_or--------- Date_ _ _ _ _ _ _ _ __
.. A*
\.. .
APPROVED.
AUG2 379 2
. *" * - - - - * - - * .. **:..;..,1..*......... _*"*** .
DOP 6900-13 Rcvtsion 1 G. Cll r:'.CKLT STS I. Fi.eure 1
- 1. 3.9.A.5.
- 2. 3.9.B.3
- 3. 4.9.B.l
- 4. 4.9.B.2
- 5. . 4.9.B.3 .
APPROVED.
AUG23'79
- ~- -*--- .~-~ *-- ------ 3 o.o.s.R. *
- ........--***'I .. *.r:.u.**--**~-******-'.-**---.i-*. . ~*~- --~: *-----* . . . _ .................... -~ *- -**-**
. 1 UNIT 3 TURBINE BUILDING 250VDC MOTOR CONTROL CENTER #3 A B c D I
E F G !; H l J I i 1 250 voe I Z50 VUC 1 1 1 250 voe l i '
l :l .; l I
U3 Battery Battery I I
I '
Turb. Bldg :
and Charger Charger \.\CC No. 3 !
Feed to Con.tro 1 - to Reactor ! i Turb. Bldg .- i MCC No. 3 Bldg. MCC No. 3
~ . . I j.
i r
I i
.\' ~I !
i .
2 2
! i 2 2 2 2 25G v~-
IJ \,
I Turb. 0 l cig
iI MCC
'.:o No.* 3 :
- <.ec:c::or I
I 3idg MCC :
2 250 voe 2 I I 1-io. 2 :
i 2/3 Charger Spare I I I !
to Ul.
Battery Ii . '
I l'
3 '
3 Charger 3 3 3 3 i3 I3 .
I to U3 Spare Spare Spare I Spare i j
i Spare .Space Battery I! : .
..I I i I I l
Vl 0
~ r ] i -
0
\..0
~
I ! 0 0 I
... *~ I I ::J 0
... ~- . ... . *. i I
. .. I I i .. . . ~W J
Figure
I ~
480V sur-,** . 4f;OV SUPPLY . :
ff!OM M.c.c. ROM M.c.c. 29-2
<8-LY F'R0-38-2
.., ':,_ 'f.
'L---"'r I
250 v.o.c.
BATIEnY l 0@~A~T~*~R~*
~rr *I I lCHGR 2/c.x..J_ _
fV'. .f'A'.
\:..J_\:.::.J_.._
1' w c;. Ci\
~--U-N-IT_3_.~...*r-.-u_N_1r_2_ _ _ __,!~'-~~~~--_.
N.O. i N.C ..
~
. b . . .
TURB. Bµ>G 250 t
v.o.c; r
, N.C.
M.C.C. t\0.3.. y
) A_:l -
. . l I .
TURB BLOG N.C. } ..
? 4'.50 V.D.C. :.*.. c.t. :iv.2 f
( .*.--.~
i . b *
.);
N.Q. )H~ . N.Ct.._)J--2 --------.-!--- ~~C. _2)
.Q 0 )
c;. .
.:!...)
~
- _1-.._
N.O ">I
-~
~l. .*~* T~YP.IC.
1:.,J i . ~yp*cA: h l* ' . ,/
. -' . AL . *' . - \:::J T'.?.c;.. L " ....... ~r . . -- . .
- n. I * * *""h
- I TYPICAL . ),, *OF l.~OTOR :,*.. Q.V .. : A. : -Cc.cJ-eu ~;-i SOL~(-; S: ce ~2
~ 1oca ted o OF .. 0 ~on r.1.0.v. . ~ .. ~ FEE;:JS FEE;)S. : i\eactor ;J,GS ~;::;, 570').
~ south s id~ 1 FEE~S A cu . *
°LI~~ Y...,, nEACiU~ 8~DG1;0.2 ~ __<,./l FEEDS *
~ . U3 Reactor:: ) . . . . REf,CTOR 13LOG ~ LINKS . 2~:i v.;:i.c. 1.~.c.c.
~ (E~'.dho*)euf £;voi;*"U~s 1
__o.._,..,_~,_
X) 3A i ~' <~ii~T ~ lB BUS 28
- 6) LJ BUS .._r SPLIT
- 6) 6\
9 ...._;;)
8 6,
~*-)
2A Ji ~
I ETC ETC A .
11 1:....J. "LJ
- TYPICAL TYPICAL TYPICAL.. TYPiC.\L TYP:C:..L.
0 7Y?.C;"-._
OF MOTOR - M.O.V. M.O.V. M.0.V. M.O.V.
FEEDS FEEDS OF ,'.1.~TCR FEEDS FEEDS F~EOS
~-"\'.)
-;o o* . 250.Vdc SYSTEM
~ ~
- 0 tO \3
-~-- .
Figure 2