DOP 6900-11,Revision 2, Station Battery Isolation & Return to Normal for Discharge Testing U2 125 Vdc Battery.ML17174A584 |
Person / Time |
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Site: |
Dresden ![Constellation icon.png](/w/images/b/be/Constellation_icon.png) |
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Issue date: |
08/31/1979 |
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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: |
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References |
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6900-11, NUDOCS 8012160532 |
Download: ML17174A584 (6) |
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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
. ~- >..
OOP 6900-ll STATION BATlt::RY ISOIAfION /\ND RETURN Revision 2
,. :il~;;:,1.1,0RilAL FOR DISCHARGE TESflNG U2 125 voe *BATTERY ,,u~us t 1979
- .** . TI1e purpose. of this procedure is to* provide the stP.ps ncccssa ry
- to isolate. the U2 l25VOC hattery for the battery Jischarge test and then*r,eturnthe U2 l25VDC battery to n*onnal *
. B.
-.:...-:~ --*--** . *:--
- l. DOS 6900-2 (Station Battery Capacity Test).*
- 2. D(lP 8300_;6 (Battery Discharge Test - load box connection)
- 3. * . l 2E2322
- t.
- PREREQUIS !TES Notify the Shift Supervisor and the U2 operator of the intendon
- ta isolate the U2 l*25VDC batter)'. * *
.. D*. *, PRECAUTIONS * . *':
- 1.. :*125 VDC Reactor Bldg Distribution Panel No. 2.
. 4
<, :~ * .
2~ ~< 4160V. Sw- Gr Bus 21 *
- /*~i?
- r. 41. GOV .Sw Gr Bus
~ ., . )
22 *.
. :* ~* : .~
- 5~ .**:4J60V $~'.~Gr. Bus 24. *:..
6.*":
- 7~ ** . 480V Sw Gr *Bus 26*. * ...*.'
- 9. .*
'?Mca
.. *.* .. o~c. *Bus *
..... *~...- *i* '.*:*.,. t(1 ~ :'
(
APPROVED 8012160(~, SEPl l '79 1
-~-......... .;~* ~* . *. . n n_~.R. ._
DOP 6900.- 11
~
- 11. PJant Sirens *
. 12;' Coii1puter Room .Test Bench.
13~. **Gen. & Trans. Relaying and Metering Panel 902-29.
- 14. Gen. H2 & Stator Cooling Panel 2252-7. *
.
- 15~ fi l~e P;-otect ion Sys tern CO 2 ca bi net.
16~
- Trans.* Fire Prot. Pnl & Rx FeE<ll'<'ater pump (\'/tr spray).*
- 17. Gen. Field A.C.B. & Volt Reg. Cabinet 2252-6.
- 18. Escape 1 ighting turbine room.
- 19. Escape Lighting Control Room *
- 20. Escape Lighting Rad\'1aste Building.
- 21. Turbine EHC Cabinet 902-31 ~
- 22. Panel 902-39.
, 23. * . Aux. Elect. Equip. Roan Panel 902-32 *
. 24~ ** H Storage Bank Control Pane) 923-1.
- ; 25. Master Station Supervisory Cabinet.
>: 26. Auto Blowdown Panel 902-32.
- 27~ .. ** -~dwaste Control Panel 2223-4.
- \.2a:::\\ .Trans. Fire Prot. Pnl & H2 Seal Oil Unit Cont. Pnl (Wtr* . *
t \' :_;:*.
- 29. Flo\,/ Reg Station 480V MCC Mn Ckt Bkr.
30..
sy;tem Panel 902...:1 s. . '.
31~'.< Annunc. Input Relay Ca bi net 902-34.
<~~:~J. \;svoc Supply to Res. B~s No. 3. . ..
.. 33. ***1isvoc ... _,:':;>-! * . **
Res. Bus No. 2.
\... . APPROVED SEPl 179
--- .. ~-*-----~~-- -
DOP .6900- l J Revision 2 E~ .. Lir11'JATlONS AND ACTIONS
- --*-****-*--~.;,.-:-"""-*
. F.* *'PROCEDURE.
---***--******-=:--"-.-* ~-
.. l ..* V~ri-fy. tha*t~the .U3125 VOC b.Jttery is supplying its nonnal
- Verify U1at the U3 125 voe battery churger is chJ1~ing the U3
.... . . 125 voe battery.
- ... 3. . (a}* CLOSE breaker C.:.l (Turbine Building Main Bus #2 to Turbine Building Reserve .Bus #2) as noted on Figure l.
Ope. ra tor
- - - - - - - - Date- - - - - - - - * ~ **
(b} OPEN breaker. B-1 (U2 l.25VDC Batter~ and Charger Feed * **
to Main Bus #2) as note~ on Figure l. .*." **
~ ..:. .
Operator -~-----'------
Date- - - - - - - -
(c) bPEN breaker B-3 (U2 charger to Battery} as noted '*;*" ..
on Figure 1 ~
- Operator_ _ _ _ _ _ _ Date_ _ _ _ _ _ __ .* .;' .*'
- (d} *Verify. that breaker B-2 (U 2A charger to batte.ry} *
.as noted ?n Figure l is OPEN.
BACK TO NORMAL *
- 4. * (a) CLOSE brea.ker B-3 (U2 Charger to Battery) as noted//>* .': .
. .. ~
- Operator
Date.--------------
.ft>}. CLOSE breaker B-l (U2 125VDC battery and Charger Feed'... :.
- , . *
- to f.ta in Bus)* as noted on Figure .l. * . .; * *
- .* Yt,!j~ ** Operator Date_ _ _ _ _ _ __
- <,~{.':/cbH} QPEN breaker C-1 *(Turbine Building rtain Bus #2 to Turbine
.. ..., Bujldi11g Reserve Bus #2) .as noted on Figure 1.* . * * ** *
. **:*(,~~* **:* ,. ':it;_ I -~,~.*.".*.~.f,:~,J'. _t.*, ,_,*.',"* ~*~¥-.1,'.'.*.- =.~.!* *.* ',,!***.' ".' ,*
.. >/i~F .. op;g,v.-a~tor_*:_*_..._,.*------Date_._._ _ _ _ _ __
(
APPROVED
-.*~;.-**~*-.* _._ __ .*:
SEPl l '79 3
DOP 6900-11 Revision 2 G. CHECKLISTS
- 1.
- 2. Figure 2
. H. TECHNICAL SPECIFICATION REFERENCES
_3.9.A.5
- 3. 9 ._B:; 3..
'.l' .
. *4~9. B~ F .
4*_9 .~.2 .
4.9.B.J.
(
\
. **< *~;
APPR0\/£0
. SEPl 1'79 "n c::. R~
TURBINE BUILDING 1~~ VD~ * . TRIBUTiON PANEL #2 and 24/48 VDC SW CENTERS 2.A and 2B . . ' ..
.~ .
. 24/48VDC .
. SWl7CH A . C." E CE "'"ER
. l_,.*125VDC*. l l25V.DC. Turb. a*rag _ .. * ***'r:u*rb.*B1.dg Neutron.** . .**.:-::*
MaTn:Bus. 2*aatte-ry Main B.us* .::aatter:.Y-*
- MaiihBus: Monitors ...11 * .. -..; .. *:;:*:
.. _1*-:***:*. N*o~. 2 to **and* C.harger No *. 2 *to *
- aw Turb;: Bldg* Feed to*- Turb *.Bld#q
Res. Bus Turb. Bldg Res. **Sus 2 * .Res. Bus#2
.......,....___..__ _....., a in Bus. I 7.. *12svoc No. 2 2. 2.12svoc i
-*- -- -"MTa~rl*n~_.:_BuB_.sldg. . Turb. Bldg. j 12SVDC Res. BJs N_o. 2 to. Main Bus No. 2 to
,,* R'.eactor Bl g Dlstri.butio Reactor Bld
~*. .
Dlstr. Pnl. Panel Distr" PnL No. 2 I 3, I 2 . 12 5VD cl 1-2=-------i 24/48VOC Turb. Bldg I Dis tr. Res. Distr.l 24/48VDC 3 ~ 2 Panel Panel No. 2 pistribution
'. Spare 125VDC Spare Pane 1 I 2A_ Charger !
i to U2 Battery . i I
..C0 . ~.... -0
-0 4
Spare 3
l 25VDC
.UJ ..... ::u 2 Charger
to U2
.CJ ..
... *:)
1--o*~*~*---~~-~*........--...;~----..,_;___;.*~---~~.~:~----.;..~~.-
.. ~.+
. . *.~---~.- ..~.~--------+i :::0 0 (J *o.
- Jl C° .
- J 0
.. I*
rv;;;
FIGURE 1.
z ..
'* DOP 6900-11.
.,'. *;: .. ( ,, . Revision 2 n:*.a'°"OC Tl.lfl'I *t.OG
.~~s*au:s.. ...... ,1111 T"r',.,CAl o,.:
HEOS TO '.*
fHOS ro
.CV'S' . .,,:;R )1
<tlllY 'SYllG'I Jt A,_0 ::J A.Jilt~,,
.~ s...~ :n ...,,.on ""°" S°"'CA
..,.D Zf n
Cu Cu Link Link
.. r,rPICA\. oo l!lOs'.'TQ.
- . . u*v.swc;111 r. ....,.Cl >1*.
- T"l1CAL Cl fEl'"i TO 4C.VS',_~ ..
_,.,,""'CAM 1l. :.* . *.~ .
440Vsm;*a.
.. , *. fill 11.DG l'1'C .
nc
'{
,-..,.P<.AL c* Jll05 T"'t'PtC,\.Of tllOS
. TO*C.Y SR'CA ~*
- " .... ]!t~}ftL;,.;,'a~i C".I U'IC.
.... O-S1WWA19
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f"f'l(.AL. ::>*fl I OS ro*~Y s~ ..
y
.. 9"' ** ,, *<***nvr.t: ~*'""
. A .. 0...0VS...c;JlfiJ'9 *
..* SS'b.~'79 12&-Vdc SYSTEM
.*..-~
__. ---:.-*-.__-----~---*
- . _~
- ~~*::..~~~l~~i~~i:t;.1:~?,~~~- Floure 2