|
---|
Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20148U0111997-06-17017 June 1997 Confirmatory Survey of Group E Effluent Discharge Pathway Areas Fsv Nuclear Station Platteville,Co ML20133D7661996-09-16016 September 1996 Confirmatory Survey Plan for Fsv Nuclear Station Decommissioning Project ML20129A4621996-09-11011 September 1996 Rev 0 to Fsv Decommissioning Project Final Survey Requirements for Liquid Effluent Pathway ML20100L3581996-02-22022 February 1996 Proposed Tech Specs,Submitting Corrected Version of Plant Decommissioning TS Updated to Reflect All Approved Amends ML20097C2601996-01-17017 January 1996 Confirmatory Survey Activities Plan for Fsv Nuclear Station PSC Platteville,Co ML20101F2091995-09-18018 September 1995 Issue 7 to DPP 5.4.2, Odcm ML20084B8801995-05-25025 May 1995 Rev 1 to Fsv Nuclear Station Decommissioning Project Final Survey Plan for Site Release ML20084B6881995-05-10010 May 1995 Issue 5 to Fire Protection Operability Requirements (Fpor) FPOR-7, Fire Extinguishers ML20082K2461995-04-14014 April 1995 Proposed Decommissioning Tech Specs Administrative Control 5.3.1,reflecting Organizational Changes That Impact Membership of Decommissioning Safety Review Committee ML20082T2151995-04-12012 April 1995 Issue 7 to Fire Protection Operability Requirements (Fpor) FPOR-12, Fire Detectors ML20082B9411995-03-17017 March 1995 Confirmatory Survey Plan for Repower Area,Fort St Vrain, Platteville,Co ML20082C0801995-03-16016 March 1995 Proposed Confirmatory Survey Plan for Repower Area,Fort St Vrain,Platteville,Co ML20082B9821995-03-15015 March 1995 Instrumentation Comparison Plan Between Orise & Fort St Vrain ML20086S2471995-02-0909 February 1995 Decommissioning Plan for Fort St Vrain Nuclear Generating Station ML20077C7171994-11-30030 November 1994 Issue 9 to FPOR-14, Fire Protection Operability Requirements ML20078C0641994-10-12012 October 1994 Revised Fire Protection Operability Requirements,Including Issue 21 to Depp Table of Contents,Issue 2 to FPOR-22 & Issue 3 to FPOR-23 ML20081J7951994-09-15015 September 1994 Issue 5 to DPP 5.4.2, Odcm ML20063M1551994-02-17017 February 1994 Rev 0 to Fsv Nuclear Station Decommissioning Project Final Survey Plan for Site Release ML20057A6151993-08-30030 August 1993 Issue 2 to FPOR-23, Fire Water Makeup Sys ML17291B3261993-05-18018 May 1993 Proposed TS Section 2.2 Re Activated Graphite Blocks,Section 2.4 Re Channel Calibr & SR 3.2.1 Re Verification of Reactor Bldg Pressure & SR 3.2.2 Re Verification of Pressure Drop Across Each HEPA Filter ML20036A8241993-05-0707 May 1993 Proposed TS 4.3 Re Prestressed Concrete Reactor Vessel Water Leakage Protection ML20118B2141992-09-25025 September 1992 Proposed Decommissioning Tech Specs Replacing Radiation Safety with Nuclear Safety, Revising Applicability Requirements for Specs Dealing W/Reactor Bldg Confinement Integrity & Clarifying Items Re Unreviewed Safety Questions ML20114D6871992-09-0101 September 1992 Tritium Leach Test on H-327 Graphite ML20096H1961992-05-19019 May 1992 Decommissioning TS Deleting Section 4.2.15 Re LCO 4.2.15 Covering Pcrv Cooling Water Sys Temps ML20095B0951992-04-14014 April 1992 Proposed Tech Specs Re Organization,Review & audit-administrative Controls ML20094L2831992-03-19019 March 1992 Proposed Tech Specs Re Controls & Limits Appropriate for Decommissioning ML20086C5301991-11-15015 November 1991 Proposed Tech Spec Limiting Condition for Operation 4.2.15 Re Pcrv Cooling Water Sys Temps ML20079M4261991-10-11011 October 1991 Revised Abnormal Operating Procedures,Reflecting Deletion of Issue 9 of EP Class ML20091D7631991-10-11011 October 1991 Proposed,Revised Limiting Condition for Operation 4.2.15 Re Prestressed Concrete Reactor Vessel Cooling Water Sys Temp ML20082L9311991-08-30030 August 1991 Proposed Tech Specs Re Decommissioning ML20082H8851991-08-16016 August 1991 Issue 2 to Abnormal Operating Procedure AOP-I-2, Chemical, Petroleum & Hazardous Waste Spill Response ML20091C4141991-08-0202 August 1991 Issue 58 to Abnormal Operating Procedure AOP-L, Loss of Instrument Air Header ML20024H3341991-05-10010 May 1991 Nonproprietary Rev 2 to FSV-P-SCP-100, Fort St Vrain Initial Radiological Site Characterization Program Program Description ML20072V5291991-04-12012 April 1991 Revised Defueling Emergency Response Plan,Including Section 1 Definitions,Section 2 Scope & Applicability,Section 3 Summary of Fsv Derp,Section 4 Emergency Classifications & Section 5 Emergency Organization ML20070V6871991-03-20020 March 1991 Issue 55 to Abnormal Operating Procedure AOP-R, Loss of Access to Control Room ML20072S0521991-03-15015 March 1991 Public Version of Revised Crisis Mgt Implementing Procedures,Including Rev 9 to CMIP-11, Classification of Emergency for McGuire Nuclear Station & Rev 11 to CMIP-12, Classification of Emergency for Oconee Nuclear Station ML20066J1171991-02-15015 February 1991 Issue 56 to Intro Section of Abnormal Operating Procedure (Aop),Issue 58 of AOP-A,Issue 58 to AOP-B,Issue 56 of AOP D-1 & Issue 2 of RERP-TRANSPORTATION ML20066A3781990-12-21021 December 1990 Proposed Decommissioning Tech Specs Re Reactor Bldg Integrity,Reactor Bldg Ventilation Exhaust Sys,Radiation Monitoring Instrumentation & Pcrv Shielding Water Tritium Concentration ML20059L5891990-09-14014 September 1990 Proposed Tech Specs Changing Design Features Section 6.1 to Permit Removal of CRD & Orifice Assemblies from Core Regions Defueled in Support of Plant Closure Activities ML20058N1071990-08-10010 August 1990 Issue 56 to AOP-I, Discussion of Fire ML20042F3151990-04-26026 April 1990 Proposed Tech Specs Re Defueling ML20034C7851990-04-25025 April 1990 Issue 57 to Abnormal Operating Procedure AOP-EP Q, Steam Leak or Inadvertent Lifting of Steam Relief Valve ML20034C7781990-04-25025 April 1990 Issue 57 to Abnormal Operating Procedure AOP-H-2, Abnormal Radioactive Gas Release from Plant ML20034C7831990-04-19019 April 1990 Issue 56 to Abnormal Operating Procedure AOP-N, Loss of Instrument Bus ML20034C7761990-04-19019 April 1990 Issue 55 to Abnormal Operating Procedure AOP D-1, Single Circulator Trip ML20034C7771990-04-19019 April 1990 Issue 57 to Abnormal Operating Procedure AOP-H-1, Abnormal Radioactive Liquid Waste from Plant ML20034C7841990-04-19019 April 1990 Issue 57 to Abnormal Operating Procedure AOP-P, Loss of DC Bus ML20034C7801990-04-19019 April 1990 Issue 59 to Abnormal Operating Procedure AOP-K-1, Environ Disturbances - Earthquake ML20034C7821990-04-19019 April 1990 Issue 57 to Abnormal Operating Procedure AOP-L, Loss of Instrument Air Header ML20034C7791990-04-19019 April 1990 Issue 57 to Abnormal Operating Procedure AOP-H-3, High Activity in Plant 1997-06-17
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20148U0111997-06-17017 June 1997 Confirmatory Survey of Group E Effluent Discharge Pathway Areas Fsv Nuclear Station Platteville,Co ML20133D7661996-09-16016 September 1996 Confirmatory Survey Plan for Fsv Nuclear Station Decommissioning Project ML20129A4621996-09-11011 September 1996 Rev 0 to Fsv Decommissioning Project Final Survey Requirements for Liquid Effluent Pathway ML20097C2601996-01-17017 January 1996 Confirmatory Survey Activities Plan for Fsv Nuclear Station PSC Platteville,Co ML20101F2091995-09-18018 September 1995 Issue 7 to DPP 5.4.2, Odcm ML20084B8801995-05-25025 May 1995 Rev 1 to Fsv Nuclear Station Decommissioning Project Final Survey Plan for Site Release ML20084B6881995-05-10010 May 1995 Issue 5 to Fire Protection Operability Requirements (Fpor) FPOR-7, Fire Extinguishers ML20082T2151995-04-12012 April 1995 Issue 7 to Fire Protection Operability Requirements (Fpor) FPOR-12, Fire Detectors ML20082B9411995-03-17017 March 1995 Confirmatory Survey Plan for Repower Area,Fort St Vrain, Platteville,Co ML20082C0801995-03-16016 March 1995 Proposed Confirmatory Survey Plan for Repower Area,Fort St Vrain,Platteville,Co ML20082B9821995-03-15015 March 1995 Instrumentation Comparison Plan Between Orise & Fort St Vrain ML20086S2471995-02-0909 February 1995 Decommissioning Plan for Fort St Vrain Nuclear Generating Station ML20077C7171994-11-30030 November 1994 Issue 9 to FPOR-14, Fire Protection Operability Requirements ML20078C0641994-10-12012 October 1994 Revised Fire Protection Operability Requirements,Including Issue 21 to Depp Table of Contents,Issue 2 to FPOR-22 & Issue 3 to FPOR-23 ML20081J7951994-09-15015 September 1994 Issue 5 to DPP 5.4.2, Odcm ML20063M1551994-02-17017 February 1994 Rev 0 to Fsv Nuclear Station Decommissioning Project Final Survey Plan for Site Release ML20057A6151993-08-30030 August 1993 Issue 2 to FPOR-23, Fire Water Makeup Sys ML20079M4261991-10-11011 October 1991 Revised Abnormal Operating Procedures,Reflecting Deletion of Issue 9 of EP Class ML20082H8851991-08-16016 August 1991 Issue 2 to Abnormal Operating Procedure AOP-I-2, Chemical, Petroleum & Hazardous Waste Spill Response ML20091C4141991-08-0202 August 1991 Issue 58 to Abnormal Operating Procedure AOP-L, Loss of Instrument Air Header ML20024H3341991-05-10010 May 1991 Nonproprietary Rev 2 to FSV-P-SCP-100, Fort St Vrain Initial Radiological Site Characterization Program Program Description ML20072V5291991-04-12012 April 1991 Revised Defueling Emergency Response Plan,Including Section 1 Definitions,Section 2 Scope & Applicability,Section 3 Summary of Fsv Derp,Section 4 Emergency Classifications & Section 5 Emergency Organization ML20070V6871991-03-20020 March 1991 Issue 55 to Abnormal Operating Procedure AOP-R, Loss of Access to Control Room ML20072S0521991-03-15015 March 1991 Public Version of Revised Crisis Mgt Implementing Procedures,Including Rev 9 to CMIP-11, Classification of Emergency for McGuire Nuclear Station & Rev 11 to CMIP-12, Classification of Emergency for Oconee Nuclear Station ML20066J1171991-02-15015 February 1991 Issue 56 to Intro Section of Abnormal Operating Procedure (Aop),Issue 58 of AOP-A,Issue 58 to AOP-B,Issue 56 of AOP D-1 & Issue 2 of RERP-TRANSPORTATION ML20058N1071990-08-10010 August 1990 Issue 56 to AOP-I, Discussion of Fire ML20034C7781990-04-25025 April 1990 Issue 57 to Abnormal Operating Procedure AOP-H-2, Abnormal Radioactive Gas Release from Plant ML20034C7851990-04-25025 April 1990 Issue 57 to Abnormal Operating Procedure AOP-EP Q, Steam Leak or Inadvertent Lifting of Steam Relief Valve ML20034C7841990-04-19019 April 1990 Issue 57 to Abnormal Operating Procedure AOP-P, Loss of DC Bus ML20034C7751990-04-19019 April 1990 Issue 57 to Abnormal Operating Procedure AOP-B, Reactor Scram ML20034C7771990-04-19019 April 1990 Issue 57 to Abnormal Operating Procedure AOP-H-1, Abnormal Radioactive Liquid Waste from Plant ML20034C7761990-04-19019 April 1990 Issue 55 to Abnormal Operating Procedure AOP D-1, Single Circulator Trip ML20034C7801990-04-19019 April 1990 Issue 59 to Abnormal Operating Procedure AOP-K-1, Environ Disturbances - Earthquake ML20034C7831990-04-19019 April 1990 Issue 56 to Abnormal Operating Procedure AOP-N, Loss of Instrument Bus ML20034C7791990-04-19019 April 1990 Issue 57 to Abnormal Operating Procedure AOP-H-3, High Activity in Plant ML20034C7821990-04-19019 April 1990 Issue 57 to Abnormal Operating Procedure AOP-L, Loss of Instrument Air Header ML20154M4361988-09-0909 September 1988 Rev a to EE-FP-0005, Evaluation of Cable Trays Outside of Congested Cable Area ML20154L8751988-05-26026 May 1988 Simulation Facility Program Plan ML20148Q4681988-03-31031 March 1988 Rev 2 to Guidance for Development of Simulation Facility to Meet Requirements of 10CFR55.45 ML20154L8911988-03-31031 March 1988 Rev 2 to Guidance for Development of Simulation Facility to Meet Requirements of 10CFR55.45 ML20150E3141988-03-18018 March 1988 Issue 1 to Procedure SR 5.4.1.3.8.abcd-R1, Steam Line Rupture Detection/Isolation Sys (Slrdis) Calibr & Testing for Panel I-93543 ML20150E2901987-12-31031 December 1987 Issue 5 to Procedure SR 5.3.4b1-A Loop I Shutdown Cooling Power Operated Valve Test ML20238E3541987-08-0707 August 1987 Rev a to EE-ISI-002, Condensate Line Erosion Insp Program ML20236N8681987-08-0505 August 1987 Exercise Manual Fort St Vrain Nuclear Generating Station Nrc/Fema Graded Exercise 870805 ML20235Y7861987-07-29029 July 1987 Issue 2 to MAP-4, Maint Dept Personnel Experience, Qualification & Training Requirements ML20237J6921987-06-0909 June 1987 Issue 6 to MQCIM-1, Maint QC Insp Program. Annotated Page to Rev 4 to Updated FSAR Encl ML20235Y7731987-05-25025 May 1987 Training Mgt Procedure Index ML20237J7151987-05-0101 May 1987 Issue 12 to Q-18, QA Monitoring & Audit Program ML20215H9731987-04-30030 April 1987 Revised Buckle Users Manual:Creep Collapse of Thin-Walled Circular Cylindrical Shells Subj to Radial Pressure & Thermal Gradients ML20215H6101987-04-10010 April 1987 Program Plan for Integrated Validation of NUREG-0737 Initiatives 1997-06-17
[Table view] |
Text
,
-.1 AOP-P Issue 57.
Public -
- FORT-ST VRAIN NUCLEAR GENERATINQ STATION Page 1-of-2 z-TIT E LO S OF A B'
0edN l
AUTHQlZEO
'i BY
< A A NA
@,C PORC 8 7 7 APR 111990
[#7'V" q q gw DCCF
\\
NUMBER (S) 4O'- OI 44 -
- Al
-i
- t O
t l
FT. ST. VRAIN I
NON-CONTROLLED COPY VERIFY ISSUE STATUS I
WITH SITE DOCUMENT CONTROL CENTER PRIOR TO USE O..
9005100050 900427
{
DR ADOCK 050 7
' FORM (D)372 22 3842 --
I*.
l.
~AOD-P
~ Issue 57:
3-Pubile
- FORT ST.- VRAIN NUCLEAR GENERATING STATIO4d9e.2 of 2 service
Pusuc sanvoca cOasPANY OF COLORADO :
O
.'(P)
LOSS OF A DC BUS SYMPTOM-ACTION MATRIX l
l l
i l
' SYMPTOMS l
li i
l l-1 I
.'l l
ACTIONS:
l-1.1 1
1.2 i
j l
l DC Bus Undervoltage l DC Bus Undervolt' age
.l l I-06F.2-5 BUS 1 l I-06F 2-5'-
BUS 2-l~
I l-(EI-92220) l (EI-92221):
I I
I
'l
'I I
1 I
I l OPERATOR ACTION
,l
-l l
l-I l.2.1 I
l l
l Dispatch operator to l
'l l
1 l reclose supply breaker l XX l
XX l
l l to affected. bus
-l l
l
.I I
I I
i l. 2.2.
-1 l
-l l I_F the affected DC Bus) l l
l cannot be reenergized.1 l
l-
,9 1
l THEN transfer the DC l l
j.
l feeds to the non-l XX XX
.l XX XXL l
.l affected bus at the l'
_l
-l:
l local transfer switch l l
l l (see Table P.5) l I
j, I
I I
l I
I l-l l
l l 2.3 l
l l
l Refer to Table P.4, l_
l 1l l " Loss of DC Bus" for i XX XX l
XX-XX l
I the effect of a loss l 1
l-l to each bus l
l-l I
I I
l l
FORM (D)T12 22 3643 i
.-.--..i-...
l, A0P APP P' Issue 57' h Public -
FORT ST. VRAIN NUCLEAR GENERATING STATIOlijage 1 of 2 V07 Service
- Pusuc ssRvecs COMPANY OF COL.ORADO fy.
.U INTRODUCTION Two separate 125 Volt D.C. busses provide operating power to the following:
a.
4160 and 480 Volt switchgear and main control room. panels.
.b.
Two instrument power inverters.
c.
Emergency hydrogen seal oil pump.
f d.
Turbine generator emergency bearing oil pump EHC supply, e.
Boiler feed pumps emergency lube oil pump. BFP tripping capability, SV7, MSC, and recire. valves, f.
Circulating water pumps discharge valves, g.
Various control relays.and emergency. lighting.
h.
Turbine - Generator _EHC System.
i.
Generator and transformer protection lockout relays.
- ~ A j.
Undervoltage relays.
U k.
Auto start prohibit and tripping relays (loss of outside-power).
I +
l 1.
Main steam electromatic relief valves, m.
Fire alarms (I-06).
The 125 Volt D.C. Busses receive their power from two 480 Volt A.C; Essential Busses via battery chargers, which provide the O.C. supply l plus charging the station batteries. They also supply three instrument busses through DC-AC inverters.
I O
V i-ronutoisn zz aua
j.
-AOP APP P=
Issue 57
'A Public FORT ST..VRAIN NUCLEAR GENERATING STATIOAage 2 of 2.
W Service
DISCUSSION OF SYMPTOMS.
SYMPTOMS 1.1 D.C. Bus Undervoltage BUS 1 1-06 F 2-5 (EI-92220h 1
1.2 D.C. Bus Undervoltage BUS 2 1-06 F 2-5 (El-92221),
i D.C. Bus 1 and D.C. Bus 2 undervoltage conditions will be alarmed on I-06F 2-5.
This alarm is common for both Bus 1 and Bus 2..
By observing the voltmeters on 1-06 El-92220 (Bus 1) and EI-92221 (Bus 2) the operator may readily identify the faulty bus.
1
~ OPERATOR ACTION j
i l
2.1 Dispatch operator to reclose supply breaker to affected l
bus.
1 If a momentary fault has caused the supply breaker to-trip, it may be possible to reenergize the bus by i
reciosing the supply breaker. The D.C. Bus 1 and Bus 2 supply breakers are located in the Auxiliary Electric Equipment Room. No attempt should be made to use the bus tie until it is determined that the bus is free of faults.
I 2.2 IF the affected D.C. bus cannot be reenergized THEN transfer the O.C. feeds to the non-a_ffected bus at the local transfer switches (see Table P.5).
The 4160 Volt switchgear and main control boards are-supplied from 125V D.C. Bus 1 and Bus 2.
One of these busses is either a main or alternate source of power.
In the event of a failure of the main source of power, the alternate source may be selected. Equipment for which transfer capability is provided is listed in Table P-5.
l 2.3 Refer to Table p.4, " Loss of D.C. Bus" for effect of loss of effected bus.
Table P.4 shows the effect of a loss of a D.C. Bus on plant equiptrent. It also lists the main and alternate t
sources of D.C.' power for the switchgear and control.
panels.
e 1
FORM (DI272 22 3643
a l.
AOP Table P.42 Issue 57-Public FORT-ST. VRAIN NUCLEAR GENERATING STATIOdage 1 of 2 SOfVICO'-
Pusuc sanvoca COMPANY OF COILORADO.
TABLF P.4 LOSS OF D.C. BUS l.
I EFFECT OF LOSS l
_EFFECT 0F LOSS l
'l,
l FUNCTION l
0F D.C. BUS 1 l
OF D.C. BUS 2 l
NOTES-l-
l l
l l
l 1l i
1 I
i-ISWITCH YARD l Switching capabilityl0ne of~two trip l
l l
l impaired. One of Icoils lost. Switch-l l
l Itwo trip coils lost.ling-voltage-is sup-l _
1 l
l Pull main supply qplied from D.C.
l l.
l-Ifuse block in "A" l Bus 1.
l l
l l panel, close tie l
l l-
-l l breaker in "B" panell l
l l
land "A" panel. '
I I
l-1 I
I I
I l
1 l
I l
14160 V BUSES ILose all switching INo'effect,L4160 l
l l
lon 4160 Busses IBusses, res., aux.
l l
l lincluding res, aux land unit aux', trans.1 l
l land unit aux trans.lNormal feed is from'l l
l l switching. This is ID.C. Bus 1.
l l
l l normal supply.
I l
l 1
-l Throw switch to D.C.l l
l l
l Bus-2 in I-15 and l
l l
l l4160 busses.
I l
=l l
1 I
l
_l l-1 I
I i
1480 V BUSES INone-Auto transfer lNone-Auto transfer I l'
l lto DC Bus 2 Ito DC Bus 1 l
l 1
I I
I I
l-I-
l IDIESEL GEN.
lD-G start and ID-G start and l
l l
lswi n hing cap. Lost 1 switching cap. Lost l-1 l
Ito D-G Set "1A".
ito D-G Set "1B".
l l
l l
l I
1.
l1 I.
l l
l l INSTRUMENT'BUSiloss of Inverter ILoss of Inverter I
1 l
lsupply, transfer to Isupply, transfer to l l
l
-lInstrument Power IInstrument Power l
l l
l Transformer 1 ITransformer 2 l
l l
I I
I I
I l
1 I
l l DATA. LOGGER INo effect-l Loss of' inverter, I
I l
l lautomatic transfer I l.
l I
lto AC backup.
l l
I I
l I
'l 1
i FORM (ol 372 22 + 3643
a l-A0P Table P.4' Issue 57
A Pubilk
- FORT ST. VRAIN NUCLEAR' GENERATING STATIO@ age 2' of. 2
%F Service *:
pusuc sanwes COMPANY OF COLORADO I
TABLE P,4
\\
LOSS OF 0.C. BUS l
l EFFECT OF LOSS l-EFFECT OF LOSS l-l l
FUNCTION
- l' 0F 0.C. BUS 1
- l OF D.C. BUS l NOTES l
l l
l-l I
1 1
I
. I i
l CONTROL BOARDS lSee listing cf ISee listing of I
l l
'lcontrol board feeds.'l control board feeds l l
t l
l Table P.6
. l Table P,6 l'.
.l 1
l l
1 I
- l
-l l'l l
l
. All l
. l-ILOSS OF INo effect. All lNo effect.
1480 VOLT ESS. lundervoltage relays -lundervoltage relays l l
1 l POWER RELAYS lwill remain operable lwill remain operablel l
l ldue to auto switch-ldue to auto switch-l l
l1) Degraded ling of DC supply on.ling of DC supply on'-l l.
l l
Voltage la loss of a DC Bus. la loss of a DC Bus. I l
l 1
. I l'
I l2) ATO l
l
' I I
I l
I l.
-l
\\
l I
I l
1:
l I
l l
l l3) Loss of I
l l
'l l
Voltage - l l
l
'l l
DG Start, l
l l
l l
Load Shed, I l
l l
l and Sequen-l l
l l
l cing l
l l-1 I
I I
I I
I l4). Loss of I
l
- l l
I Voltage - l l-l l
Reactor l-l l
l l
Scram l
l l
j l
i I
I I
i
%/ ~
FORM (D)372-22 3643 m-
.a w
w q
b r a-
)
Ji.
l-AOP Table: P.5 ~
2-Issue 57 Pubil3 FORT ST. VRAIN NUCLEAfi FENERATING STATIOM981 Of I
~
Le~
$9FVIC9' Pusuc senvoca COMPANY OF COLORADO
~
i TABLE P.5
(
LISTING OF' PREFERRED D.C. BUS f
' PREFERRED BUS EQUIPMENT D.C. BUS 1 D.C. BUS 2
-Main. control Board I-05 X
Main-Control Board I-15
-X j
Term & Aux Riy. Cab I-63 X
Term. & Aux R1y. Cab I-64 X
Term. & Aux R1y Cab I-66 X
480 Volt Bus 1 X
480 Volt Bus 2 X
480 Volt Bus 3 X
480 Volt Bus 4 X
480 Volt Bus 5 X
480 Volt Bus 6 X
480 Volt Bus 7 X
t i
4160 Volt Bus 1 X
4160 Volt Bus 2 X
4160 Volt Bus 3 X
f 4 :.
4 L
V,0 i
Y
?
FORM (ol372 22-3643 2
i s
(
y vu
.w-,
AOP Table'P.6-f*
l?
-Issue 57-A Public.
FORT ST. VRAIN NUCLEAR GENERATING [S(ATIONPage l'of 3-i
%)F Service
- Pusuc sanvece comeAmy or cotonAoo
(y V-TABLE P.6
'125V D.C. FEEDS VIA MAIN CONTROL BOXRDS AND AUXILIARY RELAY CABINETS
+
1-05 (TRANSFER SWITCH) ll FROM DRAWINGS.E-1333 and E-1334 1.-
Relief Valve PV-22167 Loop l' 3
2.
Relief Valve'PV-22168, Loop 2 3.
I-70 Alarm Bell l
I-06 125V D.C.
FROM DRAWINGS E-1377 AND E-1351 l
BUS 1 l
BUS 2 l
l 1-1 I
I i
l Alarm Horn I^ Low air pressure alarm l l
l-(deluge' systems for' l-
! pg l~MCC breaker position
-l main, aux, and reserve-I-
"V l lights i transformers, l-l l
l I Fire Alarms l
l Fire Ala,rms' l
- I.
J l Turb lube oil reservoir lP-3101 lube oil reservoirl
[
l Lube oil storage rm I
l.
l Helium Cire turntable lH. seal oil unit l_
l l Aux bir l
l g
~
I P-3103 Lube oil reservoirl l
t s
t'
\\
,, t37 a
6 t
I
. FORMIDI372 22 3643
~.
~.
-l
,AOP Table P.6 Issue 57
' A Public-FORT ST.'VRAIN NUCLEAR GENERATING STATIOM99 2 Of 3 107 Service
O TABLE P.'6 125V D.C. FEEDS VIA MAIN CONTROL BOARDS AND AUXILIARY RELAY 1ABINE'fS i
1-15 (TRANSFER SWITCH) j FROM DRAWING E-1392 1.
Res Aux Transformer Trip Relays 86 RT.
2.
Gen & Trans Aux Tripping Relays 86 GTI.
3.
Res-Aux Deluge Valves 86 RTD.
4.
Main & Unit Aux Deluge Valves 86 MVD.
5.
Unit Aux. Trip Relay 86TI (XRA-92128).
6.
Gen 1 Aux Tripping Relay 86 GI (XPA-92122),
d 7.
-Gen Di N Aux Trip R1y 86 DID (XRA-92121)..
8.
Fire Protection Sys Riser VA Alm Cbts.
9.
Main Trans Aux'Rly CR-9213.
.i 10.
Fire Protection Sys. Deluge Valves for Main Unit, Aux & Reserve Aux Deluge Valves.
11.
Unit Aux Trans Seal-In R1ys.
i i
Not on the transfei switch are the auto start prohibit and tripping relays which actuate on loss of 480 Volt j
Essential Bus.
-l I-63 (TRANSFER SWITCH)
FROM DRAWING E-1478 i
1.
4160 V Bus-1, 2 & 3 Undervoltage T
Rly Dev 127-1, 2 &'3.
2.
Rx. Pl. Ventilation System j
'Rx Pl.. Chilled Water Selector 3.
Cire. Wtr. Make-Up Pump 1A Power =
for TR-4101 to HV-4108-4.
Cire. Wtr. Make-up Pump 1B Power for TR-4103 to HV-4110 5.
BFPT 1A Trip Signal Relay CR-3108 6.
125V D.C. 1A Undervoltage Relay 7.
Turb Bldg HVAC Sys Panel I-7503X i
i O
i FORM (Dl372 22 3643
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- ll A0P Teble P.6 Issue 57 Public -
FORT ST. VRAIN NUCLEAR GENERATING STATIO$ge 3 of 3 SOfVICO'
' PusuC sanVICE CONIPANY OF COLORADO TABLE P.6 n
125V D.C. FEEDS VIA MAIN CONTROL' BOARDS AND AUXILIARY RELAY CABINETS I-64 1.
Rx Pl. Ventilation System-Chilled Water Selector 2.
BFPT 1C Trip Signal Rly'. CR-3109 i
1 1-66 (TRANSFER SWITCH)
FROM DRAWING E-1509 1.
Rx. Pl. Ventilation. System j
Chilled Water Selector 2.
CO Alarm System 2
3.
Rx. Pl. Exhaust Filter 1A (F-7301)- Fire Protection System-4.
Rx Pl. Exhaust Filter 1B (F-7302) Fire Protection System-5.
Rx. Pl. Exhaust Filter 1C (F 73025) Fire Protection System 6.
Fire Extinguishing Sys 45 (DG's) 7.
Feed to Rx Pl.-HVAC Pnl-(I-7301)
-l 8.
Feed to Cont. RM HVAC Pn1 I-7501X i
1-09 Q25V D.C.-BUS.}
2.
Main Generator RTO Tempe-ature Readout.
j 1.
Annunciator Feeds to I-09 & Chemical Building,
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