Text

Forwards Issue 59 to AOP-K-1, Environ Disturbances - Earthquake
	ML20043A949
Person / Time
Site:	Fort Saint Vrain
Issue date:	05/11/1990
From:	Fuller C; PUBLIC SERVICE CO. OF COLORADO
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	P-90154, NUDOCS 9005230333
	Download: ML20043A949 (4)
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PM bWiDe i

.Publ c Service *

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P.o. Boa 840 l

Denver,Co 80201 OMO

-j 16805 WCR 191/2. Platteville, Colorado 80651 I

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May 11, 1990

-Fort St. Vrain Unit No. 1 P-90154 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop P1-37 Washington, D.C.

20555 DOCKET NO: 50-267

SUBJECT:

ABNORMAL OPERATING PROCEDURE DISTRIBUTION-Gentlemen:

We are transmitting herein the following:

Issue 59 of AOP-K-1 Two copies of this procedure have also been transmitted to Region IV, i

Emergency Response Coordinator, in accordance with 10CFR50.54(q)

(Reference P-90155).

Inaccordancewith10CFR50.54(q),we'havedeterminedthatthechanges in this issue do not decrease the effectiveness of the Fort St. Vrain Emergency Plans-and the plans, as changed, continue to meet the intent of-10CFR50.47(b) and 10CFR50 Appendix E.

k hiW p

J 9005230}33 900512 pp PDR ADUCK 05000267 l

P PDC i

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a P-90154 Page 2 May 11, 1990 If difficulties or questions arise in filing this procedure, please contact Mr. M. H. Holmes at (303) 480-6960.

Sincerely, Mdce~

Charles H. Fuller Manager, Nuclear Production Fort St. Vrain Nuclear Generating Station CHF/bj Attachment cc: Robert Farrell Senior Resident Inspector Fort St. Vrain Renee Millison Senior Emergency Planning Specialist Fort St. Vrain 1

j i

r.

-Y Page 1 of 2 Public FORT ST. VRAIN NUCLEAM GENERATING STATION Service

Pusue samnea comePANY OF COLORADO 04/25/90 0

ABNORMAL OPERATING PROCEDURES ISSUE EFFECTIVE "

NO.

SUBJECT NUMBER DATE INTRO Abnormal Operating Procedures Introduction 55 04-19-90 A

Moisture In-Leakage 57 04-19-90 B

Reactor Scram 57 04-19-90 B-2 DELETED 01-09-88 C

Loop Shutdown 57-Last 03-28-t,0 D-1 Single Circulator Trip 55 04-19-90 D-2 Three Circulator Trips 54-Last 03-21-90 E

Abnormal Reactor Power Change 56-Last 03-28-90 F-1 Main Turbine Emergencies 58-Last 03-28-90 F-2 Low Condenser Vacuum Turbine Trip 55-Last 03-28-90 F-3 Loss.of Outside Power and Turbine Trip 55-Last 03-28-90 F-4 Loss of Outside Power and Turbine Trip with Failure of One Diesel Generator Set to Start 55-Last 03-28-90' G

Loss of Active Core Cooling 56-Last 03-28-90 H-1 Abnormal Radioactive Liquid Waste From Plant 57 04-19-90 l H-2 Abnormal Radioactive Gas Release l

From Plant 57 04-25-90 H-3 High Activity in the Plant 57 04-19-90 I

Discussion of Fire 55 06-30-89 J

DELETED 05-14-82 K-1 Environmental Disturbances - Earthquake 59 04-19-90 K-2 Environmental Disturbances - Tornado 56 04-19-90 1

FORM (D1372 22 3843

Page 2 of 2 l

t 0Pubil3 FORT ST. VRAIN NUCLEAR GENERATING STATION

,, c, Service

Pusuc senvece conneAmy or colorado 04/25/90 l

9:

e ABNORMAL OPERATING PROCEDURES I

ISSUE EFFECTIVE NO.

SUBJECT NUMBER DATE i

l

?

L Loss of an Instrument Air Header 57 04-19,

M Loss of Hydraulic Power 56-Last 03-21-90 N

Loss of an Instrument Bus 56 04-19-90 l

P Loss of a D.C. Bus 57' 04-19-90 lQ Steam Leak or Inadvertent l

Lifting of Steam Relief Valve 57-Last 04-25-90 R

Loss of Access to Control

. 06-30-89 i

Room 54 S

Loss of HVAC to 480 Volt Switchgear Room 54-Last'03-28-90 CLASS Event and Emergency Classification Overview 7

07-26-89 l

l t

R L

FORMiDI772 :'2 3643 l

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AOP-K-1

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l' Issue 59 u

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Pub llC FORT ST. VRAIN NUCLEAR GENERATING STATION age 1 of 3 P

. $9fVICO' Pusuc sanvoca comePAssy or coLonADO.

O TITLE:

ENVIRONMENTAL DISTURBANCES - EARTHOUAKE RESPONSIBLE $ f. Jllu1 A FOR

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AUTH IZED

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BY

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w l jew PORC 8 7 7 APR 1 i 1990 E'ir'E "'s.e DCCF NUMBER (SF hO-Ol@

O Il FT ST. VRIIN NON-CONTROLLED COPY VERIFY JSSUE STATUS WITH SITE DOCUMENT CONTROL CENTER PRIOR TO USE O

FORM 10)372 22 3642

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AOP-R-1 I

assue 59 Pege 2 of" 3 IK-11 ENVIROceMENTAL OfSTURBANCES - EARTHQUARE SYMPTOM-ACTtool MATRIX i

I 1

SYMPTOMS l

I I

I i

1.1 l

1.2 l

1.3 1

1.4 1

1.5 l

1.6 l

l l

ABNORMAL I-SEISMIC 1

LESS THAN IGREATER TNAM ORIGREATER THAM ORI EARTHQUAftE I

I ACTIONS I

BUILDING I

' RECORDER l

0.059 IEQUAL TO 0.05g IEQUAL TO O.10g I IIIOUCED 10FC I

1 I

VIBRATIONS I OPERATE ALARM l CROUSIO I BUT LESS THAR I GROUOIO I

I I

l l

I-06E, 5-5 l ACCELERATf088 I 0.109 l ACCELERAftoss l l

t i

i 1

1 I

I I

l i

I I

I i

lOPIRATOR ACTfDNS I

I l

l l

I l

3 I

I I

I 2.1 I

I I

I I Ensure Derueling i

XX l

l I

l XX I

I I activities terminated.

I I

i l

I I

i I

I i 1 2.2 I

I I

I I Monitor Critical Safety I

XX l

l l

l XX 1

I l Functions per EOP's I

I l

l l

I I

I l l 2.3 I

I I

I I Verify authenticity, ir I

XX l

l l

I desired, by confirming l

'I I

l i

I I

i seismoscope motion i

I I

J l

l I

I I

I I 2.4 I

I I

I i

i Process a l s acceterograph i I

XX l

1 l

l t

I photographs as soon as i

I I

i i

i possible i

I I

I i

i l

I I

I 2.5 I

i I

I I

I I Concurrently, monitor corel i

I i

l l

I I critical sarety runctions l I

I I

I i and complete, within (1) I l

XX XX 1

XX XX i

XX XX l

I i one hour, inspection of' I

I I

l piping downstream or i

I i

l 1

I I

l valves listed in Tables IAl l

I I

I

)

l l ami 1B I

I I

f f

I I

I i

1 I

I l 2. 6 -

1 I

I I

I l Complete 'Jithin (2) two l

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i I piping /,6 itream of' l

l l

l

~l XX XX l

1 1 hours1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , inspection of' I

i XX XX XX XX l

XX XX l

i I

I a

I vasves

.ed in Tabte iC 1-1 I

I I

I i

l I

I i

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AOP-M I Isave 59 Pege 3 of" 3 (K-18 ElfVIROINGEllTAL DISTURBA80CES - EARTHQUAKE SYMPTOM-ACT1081 MATRIX I

I l

SV19PTOMS I

=

l l

t I

i 1.1 1

1.2 1

1.3 1

1.4 8

1.5 l

- 1. 6 I

I I

ABMORMAL

.I SEISMIC l

LESS THAft IGREATER THAft ORIGREATER THA88 ORI EARTHOUAKE I

-l ACTIONS l

BUILDING l

RECORDER I

O.059 IEQUAL TO O.059 IEQUAL TO O.109 l ff000CEO SOFC I

I l

VfBRATIO91S l OPERATE ALARM i GROUfeO I BUT LESS TMA88 I GitOUete I

I l

l l

l-06E, 5-5 i ACCELERAT1088 i O.10g

$ ACCELERAT1085 I I

I I

l l

I I

=

I I 2.7 I

I I

I visuasey inspect ase Classi i

I I

XX i

Xx I

xX i

i I piping and equipment f'ori i

1 I

I i

I

$ feaks i

3 I

l l

3 l

i I

I I

I I I OPERAl lON. ACi l O9CS l

I I

i l

l l

l l 2.8 I

I I

l Complete within a 2fs hour l l

l l

I l

I I period, a visual inspec-l 1

XX XX l

XX XX 1

XX XX l

XX XX

{

l i tion of those valves l

I l

l 1

I I

I listed in Tables 2A, 28 l

l l

l 1

l l

1'and 2C l

l I

I I

l l

I I

6

l AOP APP K-1 Issue 59

~

age 1 of 32 Public FORT ST. VRAIN NUCLEAR GENERATING STATION

$9tVIC9' Pusuc stavoca COMPANY OF COLORADO

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INTRODUCTION Earthquakes with an accel'eration in excess of 0.05g horizontal could result in damage to plant equipment which would be required for continued safe operation of the plant.

Earthquakes with an acceleration in excess of 0.10g horizontal could result in damage to essential plant equipment which would be required for safe shutdown and cooldown. Thus, in the event of an earthquake, immediate action to determine its magnitude and assess its effects on plant equipment i

is appropriate.

DISCUSSION OF. SYMPTOMS 1.1 Abnormal Building Vibrations.

An earthquake of the magnitude required to damage plant equipment will almost certainly be noticed by station personnel. Additionally, smaller tremors may be noted by plant personnel, requiring further investigation at the discretion of the Shift Supervisor.

1.2 Seismic Recorder Operate Alarm.

Action of the seismic recorders is initiated by an lO l

b) acceleration of 0.01g. When the recorders are started by such an acceleration, the Seismic Recorder Operate Alarm is sounded in the control room.

l The accelerograph indications will not be readily l

available to the operator immediately. The accelerograph.

trace must move quickly to record the rapid vibrations of an earthquake.

It is therefore impractical for the trace to run continuously. Thus, the seismoscope recorder trace is recorded by a photograph process that must be developed by the I&C Department to be visible for interpretation by the operator of the magnitude of the earthquake.

1.3 Less Than 0.05g Ground Acceleration If developed film indicates horizontal ground acceleration less than 0.05g damage to equipment is not likely.

Systems / components may be checked for any visual damage, at the discretion of the Shift Supervisor.

1.4 Greater Than Or Equal To 0.05g But less Than 0.10g.

If developed film indicates horizontal ground acceleration greater than, or. equal to, 0.05g, but less-than 0.10g equipment required for continued operation may be damaged.

FORM (D)372 22 3643

j A0P APP'K-1 Issue 59 age 2 of 12 4

Pubil3 FORT ST. VRAIN NUCLEAR CENERATING STATION

$9FVlCO' Pusuc sanvoca cONIPANY OF COLORADO l

> b) l G

1.5 Greater Then Or Ecual To 0.100 Ground Acceleration i

l If developed film indicates horizontal ground acceleration

.i l

greater than, or equal to, 0.10g design limits may have been exceeded. All Class I structures, systems and 1

components are designed to withstand an earthquake of 0.10g horizontal acceleration at the site. When an earthquake of this magnitude occurs, it is important that equipment be carefully inspected, as design limits may be exceeded.-

.j I

1.6 Earthouake Induced 10FC A major earthquake could result in an interruption of forced cooling..

DISCUSSION OF OPERATOR ACTION

)

l 2.1 Ensure Defueling activities terminated i

Verify Defueling activities terminated until all follow up I

l activities complete.

1 2.2 Monitor Critical Safety Functions Per E0P's.

L l

Monitor critical safety functions per E0P's and perform l

l any required steps per E0P's.

j l

2.3 Verify authenticity of alarm by visual examination of

{

seismoscope class.

If authenticity of recorder operation is. questioned, the smoked glass of the seismoscope may be examined to see-if motion was recorded.

l 2.4 Process all accelerograph photographs as soon as possible.

[

1 l

If the seismic recorder operates, indicating acceleration equal to, or greater than 0.01g, process all accelerograph photographs as soon as possible.

If the. acceleration indicated is greater than 0.109, follow-up actions will be l

in accordance with symptom 1.5.

If the seismoscope on Level 1 of the Reactor Building indicated equal to, or greater than 0.05g, but less than 0.10g, follow-up actions shall be in accordance with symptom 1.4.

t r

V j

FORM (o)372 22 3t43 i

f 2-.

l

-AO.P APP K-1 Issue 59 Page 3 of 12 Public FORT ST. VRAIN NUCLEAR GENERATIN3 STATION Serv lCe*

Pusuc sanvecs COMPANY OF COLORADO

^

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l 2.5 Concurrently. Monitor Critical Safety Functions per E0P's l

and complete within one hour,_ inspection of piping down stream of valves listed in Tables 1A and IB.

This step is intended to provide a check list of major plant parameters.

This step is also intended to provide a rapid verification of the integrity of piping downstream of boundary valves.

Should the integrity be breached, valve operation would be required to stop leakage into the reactor building sump or into the turbine building as quickly as possible.

l Complete within_two hours inspection of piping down stream of valves listed in Table 1C.

Verification of piping integrity is required so that-corrective measures may be initiated should gross _ leakage be observed. One Table is provided:

For the reactor j

building.

NOTE:

If during the damage inspection it is determined that fire water must be utilized, proceed to initiate fire water to the circulator (s) and steam I

generators per E0p-2 and E0P-3.

O This is intended to provide the assistance of all personnel available in preparation for initiating fire water. After conditions have stabilized, the damage inspection must then be completed, 1

~

l 2.7 Visually inspect all C1 ass I piping and equipment for leaks.

If seismoscopes and accelerograph photographs _ indicate that a greater than, or equal to, 0.05g horizontal ground acceleration had occurred, visually inspect all Class I 1

piping ano equipment for leaks, j

Equipment required for continued operation may be damaged by acceleration of this magnitude. An inspection to determine the condition of the plant is appropriate, Leakage of pressure boundary components is the most likely form of damage.

l 2.8 Complete with a 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period a visual inspection of those valves listed in Tables 2A, 28, and 2C.

=

An overall plant inspection is necessary to identify and isolate leakage from sources of lesser consequence than those listed in the Tables.

g

'N) j, FORM (D)372 22 3843 t

l

'AOP APP K-1 Issue 59 age 4 of 32 PyhllC FORT ST. VRAIN NUCLEAR CENERATING STATION

$9rVIC9' Pusuc sanvu:s comPAmy or COLORADO l

("3 k)

TABLE 1A REACTOR BUILDING I:

i MUST BE COMPLETED WITHIN 1 HOUR lSequencel Valve l

Service / Location l Conditions. f or l Position l l

l l

l Operation l Required l' I

l

_,l BUBW system in-l I

l l

l Close l ll 1

1 HV-21143 l Fire water to BUBW l

l l coolers /RB 4740' approx-l operable or l

l l

l limately.I' above floor i leakage l

l l

l IE. of E-2106 l

l l

1 1

I l

ll 2

lHV-21142-415ervice water supply to l BUBW system in-l Close l'

t l

l IBUBW coolers /RB 4740' l operable or l

l l

lapproximately 3' above l 1eakage l

l l

l floor. W. of E-2106 l

l 1

I.

I l.

l I

ll 3

lHV-21142-2l Service water, return l BUBW system in-l Close l l

l jfrom BVBW coolers / RB l operable or l

l 1

l 14740'/4756' NE of E-2106l 1eakage 1.

l I

l l

l ll 4

l V-46819 IFire water to noriaal or l Condensate l Closed l 1

l l

lemergency bearing water I storage supply l l

1-n l

l l makeup pumps /RB 4740' NWl unavailable.

l l

4 l

l lof trap drain tank, l

l l

k}

l l

lT-2101, overhead l

l l

l 1

I I

l l

ll 5

l V-46281 if.W., to helium transfer l Leakage to/

l Close l l

l l compressor /RB 4740' S.

l from transfer l l

l l

lof transfer compressor. l compressor or l l

c l

l l

l if not requiredl l

l I

l l

v FORM (Ot372 22 3843

]

l AOP APP K-1

.t Issue 59 age 5 of 12 Public FORT ST. VRAIN NUCLEAR GENERATING STATION

$9fVlCO' Pusuc sanvoca COMPANY OF CCLORADO O

TABLE 1A REACTOR BUILDING MUST BE COMPLETED WITHIN 1 HOUR lSequencel Valve l

Service / Location l Conditions for l Position l l

l l

l Operation l Required l I

I 1

l 1

l ll 6

l V-46174Fl Service water to nitro-l Leakage in sup-l Close l l

l l gen pressuri:ation com-l ply / return nit-l l

l l

l pressor seal cooler /RB l rogen pressuri-l l

I l

14756' above E-4702, West l zation compres-l l<

l l valve I sors or comp-l l

i l

l l ressors not re-l l

i l

l l quired.-

l l~

l l

I I

I l

ll 7

l V-45115 l Firewater to Reactor l Leakage of fire l Close l l

l

! Building and Access Bay /l water in reac-l l

i l

l-RB 4791/ front of elev-l tor building ori l

l l

l

- ator.

l access bay areal l

l l

l.

l

[

L END OF TABLE 1A o

I l

i 6

i f

h O,-

(

)

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FORM 101372 22 31s43 f

F l

AOP APP K-1 Issue 59 i

age 6 of 12 Public FORT ST. VRAIN NUCLEAR GENERATING STATON

$8fVlCe*

Pusuc saavecs cOnePARfY OF COLOP. ADO TABLE IB TURBINE BUILOING MUST BE COMPLETED WITHIN 1 HOUR 15equencel Valve l

Service / Location l Conditions for l Position l l

l l

l Operation i Required l I

I I

I i

1 l V-45113 l Firewater to plant from l Leakage of fire-l Close l l

l IM ng header /T.B. 4791' Iwater downstreaml l

l l

N. of door #3 (W. of Buslof valve in tur-l I

l l

60uct Cooling Unit) lbine building l

l-1 l

l l

l 2

I V-45109 l Aux. Boiler and Hydrogen l Leakage of fire-I Close l l

l l Seal Oil area /T.B. 4791'lwater in aux.

l l

loutside N. door to Main-l boiler, hydrogent l

l l

Itenance Shop l seal oil.or l

l l

lother turbine

-l l

l l

l l building areas l l

l I

l l

~

l I

l 3

l V-4542 l Fire water riser column l Leakage on riser l Close 1.

l l

lG-3/T.B. 4791' at G-3 land access con-l l

l l

l column (E. of TMCC-1F) ltrol area i

l I

l l

l I

4 l V-4526 l Fire water to reactor lLeakage of fire l Close I O

l l

lbuilding and access bay /lwater in reactorl-l l

l lT.B. 4791' W. of 4B0 V lbuilding or l

l l

l Iroom (E. of Col. G-4) laccess bay areas l l

l l

I l

l l

l 5

i V-42397 l Service water booster l Reactor building l Close l l

l l pump supply (HVAC)/ T.B.lHVAC not re-l l

l l

l4791' at J wall west of-Iquired or leak--

l I

i lelevator lage downstream l

l l

l 6

l V-4525 l Firewater to emergency lEmergency cond-l Closed l l

l lcond. header /T.B. 4791' lensate supply l-l-

)

i lW. of 4B0 volt room lunavailable l

l l

l(header inoper-l l

l l

1 lable), and feed-l I

l i

l Iwater and steam i l

l l

l linoperable 1

I I

l l Tire water to access 1

l l

l 7

l V-4553 I

ILeakage of fire l Close l l

l Icontrol bay (G-5)/T.B.

Iwater in riser l l

l l

l4791' directly E. of 1C l column G-5 l

l l

l linstrument air com-l l

l l

l Iressor l

l l

I l

i I

I I

O J

FORM (D)372 22 3M3

I.'*

l AOP APP K-1 Issue 59

9' 0

Pubile FORT ST. VRAIN NUCLEAR GENERATING STATION SerVlCO' Puaue sanylca cosePANY OF COLORADO TABLE IB TURBINE BUILDING MUST BE COMPLETED WITHIN 1 HOUR lSequencel Valve l

Service / Location l Conditions for l Position l l

l' l

l Operation l Required l l

l l

1 l

l l

6 l

V-4589 l Firewater to BFP's and ILeakage of fire l Close l

l l

Iturbine b1dg. area /T.B. l water in BFP's i l

l l

14791' E. of IC instru-larea or other

.l I

l l

l ment air compressor l turbine buildingl I

l' l

I larea l

l l

1 I

___ I I

I 1

9 l V-45223 IFirewater to emergency lFeedwater, steaml Closed l l

l jfeedwater header /T.B.

land emergency l

l j

l l

14791' N. & W. of 1C BFP Icondensate sup-l l

l l

.l overhead l ply unavailable,l l

l l

l l header inoper-l l

l l

l lable and spool l

l l

Ipiece installed.l l

1 I

I I

1 1

10 l

V-4594 l Backup cooling BFP lube ICooling not re-l Close l

i l

I joil and EHC heat exchan-l quired for BFP'sl 1

I I

Iger/T.B. 4791' S & W of IEHC or leakage l l

O l

i 11C BFP l

l l

i l

11 l V-4256 lBFP IC lube oil cooler / lBFP 1C inoper-l Close I l

i IT.B. 4791' W. & S. of lable, not re-l l

l l

11C BFP Iquired,or l

l l

l leakage I

.l 1

I 1.

'l l

l l

12 l

V-4264 IBFP 1A lube oil cooler / IBFP 1A inoper-l.

Close j l

l IT.B. 4791' N. wall of lable, not re-l l

l l

lD/G room.

Iquired,or l

l l

l leakage i

l I

I I

I END OF TABLE IB i

O FORMtDl372 22 3843

l' AOP app K-1 Issue 59 Pub llC FORT ST. VRAIN NUCLEAR GENERATING STATION "9'

WF Service

Pusuc senvoca'cONIPAM OF COLORADO em jv)

\\

TABLE IC REACTOR BUILDING MUST BE COMPLETED WITHIN 2 HOURS JSequencel Valve l

Service / Location l Conditions for l Position l l

l l

l Operation l Required l l

1 I

l l

1 l V-461535 l Service water supply andl l

l l

l l return hydraulic power l l

l l

l lunits/

l l

l lRB 4740'above LP 2, l Leakage on cool-l Close. l l

l l power unit ling System 91 l

l l

approximately 15' l

l l

l l V-461555 IRB-4740' above LP 2, l Leakage on cool-l Close l l

l l power unit 1ing System 91 l

l l

approximately 15'

- l l

l l V-461536 lRB 4740' above LP 1, Leakage on cool-l Close l l

l l power unit ling System 91 l

l l

approximately 15' l

l l

3 l

l V-461557 IRB 4740' above LP 1, l Leakage on cool-l-Close l l

l l power unit ling System 91 l

l l

approximately 15' l

l l

l 1

l l

l 2

l V-461514 (Service water from nit-l Leakage in re-l Close l (q

l l

lrogen pressurization l turn / supply nit-l l

j l

U l

l l compressor seal cooler / lrogen pressuri-L l

l l

lR.B. 4756' above E-4702,lzation comp-1 l

l l

l East valve.

Iressors or com-l 1

l l pressors not re-1 l

j l

l quired..

l l

l.

l l

4 3

l V-46612 IS.W. return from nitro, Leakage to/from l Ciose l-i l

igen recondenser chiller /l nitrogen recon-l l

I l

IR.B. 4791' through door [ denser chiller l l

l l

lunder stairs to 4801' lor if not l

l l

Irequired.

l l

l-I-V-46338 IService water from e d __l I

l l

- l Leakage to/from l Close l l

4 i

l l

lium transfer compressor l transfer com--

l l

lRV 4740' S. or Trans.

. jpressor or if.

l 1-l l

l Comp.

lnot required.

I l

l I

l l

l END OF TABLE IC O

O I

FORMIDl372 22 3M3

7 l

AOP APP K-1 Issue 59

9' ' U Public FORT ST. VRAIN NUCLEAR GENERATING STATION

$9tYlC9' Pusuc sanvecs comePANY OF COLORADO TT TABLE 2A REACTOR BUILDING MUST BE COMPLETED WITHIN 24 HOURS lSequencel Valve l

Service / Location l Conditions for l Position l l

l l

l l-Operation l Required l l

1 l

1 I

I I

l 1

lHV-21252-5lP-2105 makeup suction / lAs required to-l Check l

l l

lR.B.- 4756' E. of P-2105 1 provide makeup l Position l I

l l-l l

. I l

2 lHV-21252-1lP-2105 suction from LP l L.P. Separator-l Close ]

l l

l separator /R.B. 4756' NW lsystem inoper-l l

l l

lof P-2105

lable, I

l l

1 l

l-l 3

l TV-4637 l5 W., control for LP 1

!If temperature I Close - l l

l lPCRV Cooling /R.B. 4756' Icontrol is lost.l Control l-I l

lNi corner of System 46 l lon Bypass l l

l lheat exchanger l

l V-46151 l

I I

l l

.I I

l.

4 lTV-4637-1 IS.W. control for LP 1 lIf temperature l Close - l l

l

-lPCRV Cooling /R.B. 4756'. leontrol is lost.] Control l

I l

lNE corner of System 46 'l lon Bypass l l

l lheat exchanger l

l V-46151 l

l h

l 5

V-21667 Concensate quench water L.P. separator Close 7

U l

l Ito LP separator /RB 4756'l system inoper-l l.

l l

lin front of LP separatorlable l

l l

l 1

I I

l l

6 I V-21730 l Bearing water removal llT3eparator l-Close I l

l l pump discharge /RB 4771' land /or bearing l l

l l

lN. wall, West of l water removal l

l l

lRT-6212/6213 l pumps inoperable'

-l L

l l_TV-4638 l l

1 i

I 7

l IS.W., control for LP 2 lIf temperature l Close - I I

l lPCRV Cooling /R.B. 4771' icontrol is lost IControl oni l

l lNE corner of heat 1

l Bypass l l

l l exchanger.

I I V-46152 l l

1 -

I

'l i

8 ITV-4638-1 l EW., control for LP 2 Ilf temperaiure i I

r

~

l Close - l l

l lPCRV Cooling /R.B. 4771' l control is. lost iControl en)

[

l l

lNE corner of heat l

l Bypass-l l

l l exchanger.

l l

V-46152 l 1

1 I

I I

l END OF TABLE 2A A

h FORM (D)372 22 3043 s

t 4

l-AOP APP K-1 I

Issue 59 "9'

U Public FORT ST. VRAIN NUCLEAR GENERATfNG STATION

$9fVIC9' Pusuc sanVICE OOIWPANY OF COLORADO l

TT TABLE 2B TURBINE BUILDING MUST BE COMPLETED WITHIN 24 HOURS ISequencel Valve l

Service / Location l Conditions for l Position l l

l l

l Operation l Required l l

l l

1 i V-9232 l1 solation LS-92206-3 D/Gl Leakage of fuel l Close i l

l l1A day tank / day tank N. l oil l

l l

l land middle valve l

l I

I l

l l

-l 2

l V-9220 l1 solation LS-92207-3 D/Gl Leakage of fuel-l Close l l

l l1B day tank / day tank N. l oil I

l l

l lend middle valve l

l l

I l

1 l

l I

1 3

l V-46614 l Service water booster l Chiller not l

Close l

ll l

l pump supply T.B. 4791' l required or j

l ll l

labove booster pumps S.

l leakage l

l.

l l

lvall of lube oil storage l l

l l

l Iroom l

l l

i l

l l

l 4

l V-4236 lS.W. inlet to E-5109sX/ IEHC inoperable. l Close l l

l lT.B. 4791' above EHC inot required, orl l

(s l

l lunit South l leakage l

l I

l l

1

[

s 1

5 l V-4229 l5.W. inlet to E-5109X/ IEHC inoperable, l Close I l

l l

lT.B. 4791' above EHC lnot required, orl l

l l

lunit North l leakage l

l l

l 6

l V-42390 l Gland seal 'o P-3201 lP-3201 inoper-l Close l t

l l

l(Ht. #5 drain pump)/T.B.lable, not re-I l-l I

l4791' N. of P-3201 Iquired or leak-1 l

l l

l lage' l

l I

l l

l 7

lV-31232;1EFWsupplytoM.S.de-lBFP's inoperablel Close l l

l lsuperheaters/T.B 4791' lor leakage down-l l

l l

IN & W of IC BFP l stream l

l l

l 1

1 I

I l

8 l HV-31191 lCond, to emergency con-l Emergency con-l Closed l l

l ldensate header /T.B.

Idensate supply l l

I I

14791' W. of IC BFP, lunavailable, l'

l l

l loverhead l(header inoper-l l-l l

l lable) or supply l l

1 l

l l

l leakage l

l i

l l

l I

i n

f FORM (01372 22 3643

l AOP APP K-1 Issue 59 "9'

O PyhllC FORT ST. VRAIN NUCLEAR GENERAThNG STATION

%F Service

Pusuc senvics conseamy or cotonApo l

nib)

TABLE 2B TURBINE BUILDING MUST BE COMPLETED WITHIN 24 HOURS l

lSequencel Valve l

Service / Location l Concitions_for l Position l l

l l

'l Operation l Required-1 l

l l

~l l

9

.I HV-31122-l Fire water to emergency l Emergency con-l Close l l

l lcond. header /T.B. 4791' ldensate supply l l

l l

lW. of IC BFP, overhead l unavailable.

l l

l l(header inoper-l l

l l

l lable) and feed-l 1

I I

l l water and' steam l l

l l

l l inoperable l

l I

l l

'l l

10 l

V-4239 lBFP IB lube oil cooler / lBFP IB inoper-l Close l l

l lT.B. 4791' W. of IB BFP lable, not re-l l

l l

1 l quired or leak-1 I

I l

l lage l

l l

11 l__ V-4234 ISW to E-3304X anc Sample l Sample cooling l Close l l

l l Cooling /T.B. 4791' W. ofinot required or l l

l l

l1B BFP, overhead l leakage l.

rm I

I I

I i

i 12 1 V-42817 lFervice water to Aux.

JAux. BFP's in-l L

l l

l lBFP seals /TB 4791' W & Sloperable, not l

l l

l lof 1A BFP l required,or-l 1

l l

l l leakage-l l

l i

I I

t

^

END OF TABLE 2B i

I i

- t 5

O-1 FORM (D)372..*2 3643 w

e

4, 4[

A0P APP K-1

.I Issue 59 i

A Public FORT ST. VRAIN NUCLEAR GENERATING STATION "9' VGF Service

Pusuc senvece comeAm or cotonApo j

TABLE 2C CIRCULATING WATER BASIN PIT MUST BE COMPLETED WITHIN 24 HOURS l

lSequencel Valve l

Sequence / Location l Conditions for l Position l l

l l

l Operation l Required l l

l l

l l.

1 1

i V-41903

[ Circulating water makeup l All conditions l Close l

.I i

lto blowdown /CW in pit, I

.l l

l l

l bottom and to right of l

l l

i l

I lladder l

l l

2 l V-4130 l Firewater pit to. circ-l Circulating l

Close l-l l

lulating water / south of l water pit in-l l

l l

l door to firewater pump l operable l

l I

I lhouse l

l l'

I I

l l

l 3

l V-4132 l Firewater pit to circ-l Circulati_ng l

Cioss l

I l

lulating water / north of l water pit in-l l

l l

-l door to firewater pump ~l operable-l l

l I

lhouse l

l l

I l

l l

l

,l.

j i

END OF TABLE 2C t

I l

l k

FORM (D)372 22 3843

ML20043A949

Text

SUBJECT:

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