Text

Issue 59 to Abnormal Operating Procedure AOP-K-1, Environ Disturbances - Earthquake
	ML20034C780
Person / Time
Site:	Fort Saint Vrain
Issue date:	04/19/1990
From:	; PUBLIC SERVICE CO. OF COLORADO
To:	;
Shared Package
ML20034C092	List: ML20034C091; ML20034C775; ML20034C776; ML20034C777; ML20034C778; ML20034C779; ML20034C780; ML20034C782; ML20034C783; ML20034C784; ML20034C785;
References
	AOP-K-1, NUDOCS 9005100040
	Download: ML20034C780 (18)
	v • d • e

.

.I AOP-K ~y J

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Issue 59

-(

Public

. FORT ST. VRAIN NUCLEAR QENERATING STATION Page 1 of 3

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_. O TITLE:

ENVIRONMENTAL DISTURBANCES - EARTHQUAKE.

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Issue 59 Page 2 00 3 (K-1) 1s.gylRO90 MENTAL DISTORBANCIS - EARTHQUAKE SYMPTOM-ACTION MATRIX lI.

SYMPTOMS l

H h

1.1 1

1.2 1.3 1

1.4 a

1.5 l

1.6 l

ll ABNORMAL i

SEISMIC LESS THAN IGREATER THAN ORIGREATER THAN ORl EARTHQUAKE I

l 1

ACTIONS I

BUILDING I

RECORDER O.05g IEQUAL TO O.05g IEQUAL TO O.10g I INDUCED IOFC l

l l

VIBRAT80NS OPERATE ALARM GROUNO l BUT LESS THAN I GROURD

, i l

l l

l-06E, 5-5 ACCELERATION l 0.10g i ACCELERATION i l

I I

I l

l l

t l OPFRATOR ACTIONS l

I l

l l

l I

1-1 I

I l

l l

l

'l i

I

. _1.

I Ensure Derueling i-l ~ )DC '*;

I XX l

l i

I XX l

2.1 I

l l

l activities terminated.

l I

I I

l l

t l

i I

I I

l l 2.2 I

l XX l

l I l

l XX l

l Monitor Critical ' Safety rol XX I

I l

l l

.l

~'

ronct ions. per EO,P's b

'~l i

i i

I l

1 I

I I

l l

2.3 3

z--

- l l

Veri fy authentici ty - ir,

.I4. )O(

l l

XX l

l l

l-l r

I I

l l

l desired, by confirming.

t I "-

4 I+-

- i l

l l

l l seismoscope motion

<, l l

l 1

1 I

l-l l 2.4

,a

. l:

-?

I l

l I

I i

l l Process all accelerograph si; l

XX l

l l

I l

l l

'l l

l photographs as soon-as ' I

s l

l l

1

-l l

"; I i

l l~

l l

I "c

l possible

', J l

I e.

l I

i l

1

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( 2.5 L: ch l l Concu r ren t ly, mon i to r co re l /~, D !

l-I l.

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.I

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critical sarety runctions I ~f I

I i

l l

l

' and complete, within (1) l J, I

XX XX l

XX.

XX l

XX XX l

l' one hour, inspection or i

j l

l l

l l valves listed in Tables IAI l

1-

-l l

l l

l piping downstream of-'

-~s f -

l and is i

I i-1-

, l

-l l

l l

1 I

I I

I

'l i

I I

-l l

l Complete within.(2) two I

l l-l l

1-I I 2.6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ,. inspection or I

XX XX l : XX XX l

XX

)O(

l XX~

XX l.

l piping downstream of L

l i

1.

l l

valves listed in Table IC I l'

l l

l I

i l

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l AOP-K-1 issue 59 Page 3 of 3 (K-1)

ENVIRONMENTAL DISTURBA.1CLS - EARTHQUAKE SYMPIOM-ACT ION MATRIX l

l l

SYMPTOMS l

l 1.1 1

1.2 1

1.3 1

1.4 5

1.5 l

1.6 i

ABNORMAL l

SEISMIC l

LESS THAN ICREATER THAN ORIGREATER THAN ORl EARTHQUAKE i

ACTIONS BUILDING l

RECORDER l

0.059

'IEQUAL TO O.05g IEQUAL TO O.109 I INDUCED IOFC 1

i VIBRATIONS l OPERATE ALARM l CROUNO l BUT LESS THAN ]

GROUND '

I i

i I

8-06E, 5-5 l ACCELERATION l 0.109 l ACCELERATION l l

L i

l I

i i

l' I

I I

1 I

I I

2.7 I

l l

l Visually inspect all Class l

l l

XX l

l piping and equipment for.

I I

l l

l leaks l

I l

l l

t I

i l'

1 I

l IOPERAllON ACTIONS L

I-l l

l' I

I l

l l l~2.8 1

l~

I l'

Complete within a 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months i period, a visual inspec-l XX XX - I XX XX 1

XX XX i

XX XX 1

-l tion of those valves l

l l

1-listed in Tables 2A, 28 - 1 I

l l

'l I 'and 2c

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I AOP app'K-li lssue 59 "9' b OI OPublic FORT ST. VRAIN NUCLEAR GENERATING STATION Service

PUBUC SERVICE COMPANY OF COLORADO

-INTRODUCTION Earthquakes with an accelera' tion in excess of 0.05 _ horizontal could 9

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 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 1

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

1 The accelerograph indications will not be readily 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 9

If developed film indicates horizontal ground acceleration I

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.

O FORM (D)T12 22 3643

L - '-.

- l-AOP APP K-1 Issue 59 i

Public FORT ST. VRAIN NUCLEAR GENERATING STATION "9'

$9fVICO' Pusuc sanvoca COMPANY OF COLORADO 1.5 Greater Then Or Equal To 0.10g Ground Acceleration i

If developed film indicates horizontal ground acceleration greater than, or equal-to, 0.10g-design limits may have been exceeded. All Class I structures, systems and i

components are designed to withstand an earthquake 1of 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.

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

1 DISCUSSION OF OPERATOR ACTION l

2.1 Ensure Defueling activities terminated l

Verify Defueling activities terminated until all follow up l

l-activities complete, i

l 2.2 Monitor Critical Safety Functions Per E0P's.

{

O-l Monitor critical safety functions per E0P's and-perform l

any required steps per EOP's.

l 2.3 Verify authenticity of alarm by visual examination of 4

seismoscope glass.

If authenticity of recorder operation is questioned, the smoked glass of the seismoscope may be examined.to see if 1

. motion was recorded, i

l 2.4 Process all accelerograph photographs as soon as possible.

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'O.10g, follow-up actions will be 4

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.

i O

FORM (D)372-22 3643

l A0P APP K-1 Issue 59 age 3 of M OPublic FORT ST. VRAIN NUCLEAR GENERATING STATION Service

Pusue senvice COMPANY OF COLORADO l

2.5 Concurrently, Monitor Critical Safety Functions Per E0P's I

and complete within one hour, inspection of piping down stream of valves listed in Tables lA and 18.

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, i

2.6 Complete within two hours inspection of piping down stream f,

of valves listed in Table IC.

Verification of piping integrity is required so that corrective measures may be initiated should gross leakage j

be observed. One Table is provided:

For the reactor 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 l

generators per E0P-2 and E0P-3.

Ol 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.

l l

2.7 Visually inspect all Class I piping and equipment for leaks.

l If seismoscopes and accelerograph photographs indicate j

that a greater than, or equal to, 0.05g horizontal ground

)

acceleration had occurred, visually inspect all Class I l

piping and equipment for leaks.

I Equipment required for continued operation may be damaged by acceleration of this magnitude. An inspection to j'

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, 2B, and 2C.

An overall plant inspection is necessary to identify and i

isolate leakage from sources of lesser consequence than those listed in the Tables.

O FORM (D) 372 - 22 3643

i 1.

' A0Pl APP K-1 Issue 59-age 4 of 12 APublic FORT ST. VRAIN NUCLEAR GENERATING STATION s-W Service * -

Pusuc sanwen couramy or cotonAoo O

TABLE 1A REACTOR BUILDING MUST BE COMPLETED WITHIN 1 HOUR L

lSequencel Valve-l-

Service / Location' l Condhions for l-Position l l,

I l

l l-

.0peration

. l_ Required ~l

(

l l

l l:

E

.l l 1

i HV-21143 l Fire water to BUBW l Bb8W system in-l Close l l

l l

l coolers /RB 4740'1 approx-l. operable or l

l.

~

l l

limately Iabove floor l leakage l

-l l

l

.l lE. of E-2106 l

l' l

l 1

lHV-21142-4l Service water supply to-llBUBW system in-l l

]

Close-l ll 2

L l

l lBUBW coolers /RB 4740' l operable or I

I-l l

l

.lapproximately 3' above l leakage l

l l

l l floor, W. of E-2106 l

l l

l

-l I

i l l 3

IHV-21142-2l Service water, return l BUBW system in-l Close. l I

l' lfrom.BUBW coolers / RB l operable or' l

l l_

l l

l4740'/4756' NE of E-21061 leakage l

-l l

l I

l l

1 ll 4

l V-46819 IFire water to normal or--l Condensate l

Closed l l

l l emergency bearing water,I storage supply l l

A l

l l makeup pumps /RB 4740' NWl unavailable.

l; l

l l

lof trap drain tank, l

l l

1 l

l lT-2101, overhead l

l _.

.I i

l l

l-l 5

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

l Close j; l

l l compressor /RB 4740' S.

I from transfer-l l

l l

l lof transfer compressor. I compressor or l l

l l

l l if not requiredi

'l 1

I l

l l'

l 1

I l

t I

i i

lV.

FORM (D)772 22 3643

~

m,

-y

l A0P APP K '-

1ssue 59, Public FORT ST.'VRAIN NUCLEAR GENERATING STATION fage 5 of 12 OService*

" pusue sanvice COMPANY OF COLORADO TABLE 1A REACTOR BUILDING MUST BE COMPLETED WITHIN-1 HOUR' lSequencel Valve-l Service / Location i Conditions for l Position.l I.

l l

-1 Operation' l Required l 1

I I

l-ll 6

l V-461744 IService water to nitro-l Leakage in sup-l Close l l

l l gen pressurization com-l ply / return nit-l-l-

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

l l

14756' above E-4702, Westl zation compres-l l

l 1

l valve i sors or comp-l 1.-

I l

l

.I ressors not re-l 1:

I l-I l quired; I

l j

l i

I I

i

-l

.i i

ll 7

I V-45115 [ Firewater to Reactor

.I Leakage of firel Close I

i l

IBuilding_and Access Bay /l. water in reac-l l

l l-lRB 4791/ front of elev-l_ tor building ori l.

I i

lator.

I access bay areal l

l l

1 I

l 1

END OF TABLE 1A e!

1 1

g FORMt01372 22 3643

t l

AOP APP K-1 Issue 59 i

age 6 of 12 PyhllC FORT ST. VRAIN NUCLEAR GENERATING STATION Service

pusuc senvece comemy or coumADO

~'

e(v)

TABLE IB TURBINE BUILDING MUST BE COMPLETED WITPIN 1 HOUR j

l lSequencel Valve l

Service / Location l Conditions for l Position l l

l l

l Operation i Required l I

I I

t l

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

l-l ring header /T.B. 4791' Iwaterdownstreaml l

l l

l' l

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

l l

l Duct Cooling Unit)-

-lbine building l

l t

l l

__l l

I l _45109 l Aux, Boiler and Hydrogenlleakage of fire-l Close l t

i 2

l V-I l

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

l l

l i

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

l l

ltenance Shop l seal oil or l

l l

lother turbine l

l i

l l

l l building' areas

-l l

l l

l 1

3 l V-4542 l Fire water riser column l Leakage on riser l Close l l

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

l l

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

l 1

I I

l l

l

-/m l

4 l V-4526 l Fire water to reactor l Leakage of fire l Close l

(

l l

l building and access bay /l water in reactori l

l l

IT.B. 4791' W. of 480 V lbuilding or l

t l

l l room (E. of Col. G-4) l access bay areas l l

l i

l l

l l-l l

5 l V-42397 lScrvice 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 l

l l

l l elevator age downstream l l

l l

1

_I l

l

. Emergency cond-l Closed l l

l 6

l V-4525 l Firewater to emergency l

l l

icond. header /T,B. 4791' lensate supply l

l l

lW. of 480 volt room l unavailable l

.l l

l l

l l(header inoper-l-l I

l l

lable), and feed-l l

l.

l l

l water and steam l l

l l

l linoperable-l l

l l

l 1

_ _l l

I l

7 l V-4553 l Fire water to access ILeakage of fire l Close I i

l l

l control bay (C-5)/T.B.

l water in riser l l

l l

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

l l

l l instrument air com-l l

l l

l Iressor l

l l

I l

l l

e-v-

=

1

,o-oi m. o. -

l AOP APP K-1 Issue 59 FORT ST. VRAIN NUCLEAR CENERATING STATION "I'

l OPubilC

$9fVICO' Pusuc unWca comerANY or COLORADO

'i TABLE IB TURBINE BUILDING MUST BE COMPLETED WITHIN 1 HOUR i

i ISequencel Valve l

Service / Location l Conditions for l Position l l

l l

l Operation l Required I L_

l i

l I

l 8

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

l l turbine bldg. area /T.B. l water in BFP's I i

l l

l 14791' E. of it instru-larea or other l

I l

l l ment air compressor l turbine building l 1

l l

l l area l

l I

I I

I l

l l

9 l V-45223 IFirewater to emergency lFeedwater, steam l Closed I

-i l

l lfeedwater header /T.B.

land emergency l

l I

l l4791' N. & W. of IC BFP l condensate sup-1 l

l l

l overhead l ply unavailable,l l

l l

l lheader inoper-l l

l l

lable and spool l

l I

l l

l l piece installed.l l

l i

l l

I 10 l V-4594 IBackup cooling BFP lube ICooling not re-l Close l l

l loil and EHC heat exchan-lquired for BFP'sl l

l l

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

l l

l2c $"

l l

l G.

I 11 l

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

I lT.B. 4791' W. & S. of lable, not re-1 I

l l

l1C BFP l quired, or l

l I

I l

lleakage l

l I

I I

l l

l-l l

12 l

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

l l

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

l l

l 10/G room.

l quired, or l

l l

l leakage l

l l

I I

I i

l END OF TABLE IB O

FORM (D)372 22 3843

('

1 I

AOP APP K-1 Issue 59 "9'

O PubllC FORT ST, VRAIN NUCLEAR GENERATING STATION s

187 Service

Pusue sanwce COMPANY OF COLORADO TABLE 10 REACTOR BUILDING MUST BE COMPLETED WITHIN 2 HOURS ISequencel Valve 4

Service / Location l Conditions for j Position l I

l 1

l Operation l Required l l

1 1

I I

i 1

1 1

l V-461535 l Service water supply andl I

l-l l

Ireturn hydraulic power I i

l l

l l units /

l l

1 l

l lRB 4740'above LP 2, l Leakage on cool-1 Close l l

l lpower unit ling System 91 l

l l

1 l

approximately 15' l

l l

l l V-461555 lRB 4740' above LP 2, lleakage on cool-l Close l l

l l power unit ling System 91 l

l l

approximasely 15' l

1 l

l V-461536 lRB 4740' above LP 1, 1,eakage on taol-j Close 1 l

l l power unit ling System si l

l m

l I

l approximately 15' l

l.

l l

l l V-461557 lRB 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 l.

l l

l-l l

2 l V-461514 IService water from nit-l Leakage in re-l Close i O

l l

lrogen pressuri:ation l turn / supply nit-l i

l l

icompressor seal cooler / lrogen pressuri-l l

l l

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

l l

lEast valve.

I ressors or com-l l

1 l

l l

l pressors not re-l J

l l

l quired.

j' l

I I

l l

l 3

l V-46612 IS.W. return from nitro-l Leakage to/from~.]

Cicse l l

l Igen recondenser chiller /Initrogen recon- [

l l

l lR.B. 4791' through door Idenser chiller 1 l

l l

lunder stairs to 4801' lor if not l

I I

trequired.

.l l

l l

4 l V-46338 l$ervice water from hel-l Leakage to/from l Close l l

l lium transfer compressor l transfer com-l l

l I

lr:V 4740' S. or Trans.

lpressor or if 1

I I

l l Comp.

Inot required.

I l

l l

I l __. _.

l 1

END OF TABLE IC

. [

O FORIA(D)372 22 3643 i

l ADP APP K-1 155ue'59

9' ' O O$9fVIC9' PubilC FORT ST. VMA'W NUCLEAR GENERATING STATION Pusuc senwca COMPANY or coLonApo TABLE 2A REACTOR BUILDING MUST BE COMPLETED WITHIN 24 HOUR $

lSequencel' Valve l

Service / Location l ' Conditions for l Position l' I

i j

l Operation

1. Required.I I

1

.i i

l

_I

+

1 1

lHV-21252-5lP-2105 makeup suction / lAs required to -1 Check l

J l

. IR.'B. 4750' E. of P-2105 l provide makeup

-) Position i l

J l

lTV f1252-1lF2TDTEiion f rom LP 'lll.P. Separator I

I 7 1

Close 1 1

2.

l l

1 separator /R.B. 4756' NW lsyntem inoper-1 l

r l

l lof P-2106

.l abl e,

i I

i~

1 1

I 1

I l

3 I TV-46ff'15.W. control for LP 1 Ilf temperature j CloATI l

l lPCitV Cooling /R.B. 4756' l control is lost.'l Control' I I

l lNE corner of System 46 l lon Bypass 1 1

I theat exchanger l ~

l V-46151 l

l l

lT~llTV-4617 T~1 -

1~~tiose - l 1

lS.W. control for LP 1 lIf temperature l 1

l lPCRV Cooling /R.B. 4756' icontrol is lost.l Control i

1 l

lNE corner of System 46 I Jon Bypass I I

l lheat exchangar I

i V-46151 l

l~ Close l

I I

i

~

1 l

5 l V-21867 lConcensate quench water ILP. separator l

j l

l Ito LP separator /RB 4756' system inoper-1 J

W.

l l

.in front of LP separator able l

'i 1

__l (Bearing water removal ILP Separator l

Close i I

l

'l l

6 l V-21730 l.

I lpump discharge /RB 4771' land /or bearing l l

l l

lN. wall, West of Iwater removal l

l l

1 lRT-6212/6213 Ipumps inoperablel l

l l

l-l

~

l l

l 7

l TV-4638 lS.W., control for LP 2 Ilf temperature -l Close - l I

l lPCRV Cooling /R.B. 4771' icontrol is lost l Control onl.

l l

l lNE corner of heat j

j Bypass l l

1 l exchanger.

I I V-46152 1 I

l I

I l-1 i

I 8

lTF4638-1 l5.W., control for LP 2 IIf temperature l Close - l 1

l lPCRV Cooling /R.B. 4771' l control is lost IControl onl l

l l

lNE corner of heat i

i Bypass l l

l l exchanger.

l l

V-46152 I l

I l

l I

l END OF TABLE 2A I

i 9;

FORM (ol372 22-3643

l AOP APP K-1 Issue 59 FORT ST. VRAIN NUCLEAR GENERATING STATION "9' 0Public

$0rVICO' Pusuc sanVM:s comePANY or cotonApo TABLE 2B TURBINE BUILDING MUST BE COMPLETED WITHIN 24 HOURS lSequencel Valve l

Service / Location l Conditions for l Position l l

l l

l Operation l Required l l

l l

l' l

l l

1 l V-9232 l Isolation LS-92206-3 D/Gl Leakage of fuel l Close l l

l 11A day tank / day tank N. loil 1

l l

l land middle valve l

l l

I l

l 2

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

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

l

.I l

lend middle valve l

l l

l 1

l 3

l V-46614 IService water booster IChiller not l

Close l ll l

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

l ll l

labove booster pumps S.

lleakage l

l l

l l wall of lube oil storagel l

l l

l Iroom l

l l

l l-l 4

l V-4236 IS.W. inlet to E-51095X/ IEHC inoperable,1 Close 1 l

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

lunit South l leakage l

l O

1 l

l l

l 5

l V-4229 IS.W. inlet to E-5109x/ lEHC inoperable. l Close l l

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

l l

lunit North l leakage l

l l

l I

I I

l l

6 l V-42390 l Gland seal to P-3201 lP-3201 inoper-l Close l l

l l(Ht. #5 drain pump)/T.B.lable, te,. re-l l

l 14791' N. of P-3201 Iquired or leak-l l

1 I

l lage' l

l l

I_

l I

I l

l 7

l v-31232 lEFW supply to M.S. de-lBFP's inoperable l Close l l

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

l l

lN & W of IC BFP lstream i

I I

I l

l l

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

l ldensate header /T.B.

Idensate supply ]

l l

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

l l

I l

l overhead l(headerinoper-l l

l l

lable) or supply l l

l l

l lleakage l

l l

l O

romimm.n me

=

+

l AOP APP K-1 Issue 59 39' OPublic FORT ST. VRAIN NUCLEAR CENERATING STATION Service

Pusuc senvece comeAmy or cotonAno TABLE 2B TURBINE BUILDING MUST BE COMPLETED WITHIN 24 HOURS j$equencel Valve l

Service / Location l Conditions for l Position l l

l l

l Operation i Required l I~

I l

l I

I l

9 l HV-31122 l Fire water to emergency l Emergency con-Close l l

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

l l

lW. of IC BFP, overhead l unavailable, I

l l

l

.l l(header inoper-l l

l l

l' lable) and feed-l l

i l

l l

l water and steam l l

-]

l l

l l inoperable l

l l-1 I

lBFP IB lube oil cooler / lBFP IB inoper-l l

l l

Close l l

10 l V-4239 l

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

l l

l Iquired or leak-l l

1 I

I lage l

l l

l 1

l l

11 l V-4234 ISW to E-3304X and Samnlel Sample cooling l Close l J

l l

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

l l

llB BFP, overhead lleakage l

i l

l l

12 l V-42B17 IService water to Aux.

l Aux. BFP's in-l Close l-l l

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

I l

lof 1A BFP l required, or l

l l

l lleakage

-l l

I i

l l

END OF TABLE 2B v

t e

6 9

l 9

FORM (D)372 22 3643

~

I AOP APP K-I e

Issue 59 Public FORT ST. VRAIN NUCLEAR GENERATING STATION "9'

$9fVICO' Pusuc sanvecs COMPANY OF COLORADO O

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

Sequence / Location l Conditions for l Position l l

l l

Operation l Required l l

l l

1 l V-41903 l Circulating water makeup l All conditions l Close l l

l lto blowdown /CW in pit, I

l l

l bottom and to right of I l

l l

l l ladder l

l l

l-I

__l 1

I I

l 2

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

Close l l

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

l l

Idoor to firewater pump i operable l

l l

l lhouse l

l l

l 3

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

Close l l

1

-julating water / north of I water pit in-l l

l l

l door to firewater pump-l operable

[

]

l l

lhouse l

l l

I I

l

_l O

e~o or 1^e'e 2c l

O s

FORM (ol372 22 3e43

'i

_i

e e

AOP-M-1 i

tssue 59 Page 2 of 3 (K-1)

ENVIRONMENTALDISTURBANCES - EARTHQUAME SYMPTOM-ACTION MATRIX 1

I l

SrMPTOMS l

I l

l t

1.1 1

1.2 l

1.3 l

1.4 5

1.5 l

1.6 I

l l

ABNORMAL i

SESSMIC I

LESS THAN IGREATER THAN ORIGREATER THAN ORI EARTHQUAKE I

I ACTIONS l

BUILDING I

RECORDER l

0.05g IEQUAL TO O.05g frQUAL TO O.10g i IMOUCED IOFC l

l 1

VfBRATIONS.I OPERATE ALARM i GROUND I BUT LESS THAN I CROUMD l

l l

l 1

1-06E, 5-5 i ACCELERATION l G.109 i ACCELERATION I I

I i

i i

l I

i i

i I

i 1

I I

i l

10P{RATOR ACT IONS I

I l

l 8

I i

- pDr l

l l

a l, e ueling activities l

XX l

XX i

l l

l XX l

l l terminated.

I I

l l

1 I

I I

I l

I i 1 2.2 l

l l

l l Moni tor Critica l Safety I

XX l

l l

l XX l

l l ronctions per EOP's l

l l

l 3

I I

I l 2.3 I

i 1

I I

i ;

Verify authenticity, ir 1

XX i

XX l

l 1

1 l

l desired, by confirming l

I l

l l

ll seismoscope motion l

l l

l 1

1 I

i I

i i

i 1 2.4 l

1 i

I i

l Process all accelerograph l I

XX l

l l

l photgraphs as soon as I

l l

l possible l

l l

1 1

I I

H 2.5 I

I i

1 I

I l

Concu r rent ly, monitor corel I

I I

l l

l critical safety functions 1 I

l l

l ill and complete, within (1) l l

XX XX l

l l one hour, inspection of I

l l

l 8

l l

l piping downstream or i

l l

l valves listed in Tables IAl l

l l

l l and 18 1

I l

l l

l 1

I I

I l

l l

l 1 2.6 I

I I

I i

l l

l Complete within (2) two I

i l

l l

l hours, inspection of I

l XX XX l

XX

- XX 1

XX XX l

XX XX.

l 1

l piping downstream or I

i l

l l

l valves listed in table IC 1 l

1 I

I I

i 1

I i

1 9

O e..

n 3

p.

v v

l AOP-K-1 Issue 59 Page 3 of' 3 (K-1)

ENVIRONMENTAL DISTURBANQE.S - EARTHQUAKE SYMPTOM-ACTION MATRIX I

I l

SYMPTOMS I

I I

l i

1.1 1

1.2 l

1.3 1

1.4

- 1 1.5 1

1.6 I

I I

ABKORMAL i

SEISMIC l

LESS THAN IGREATER THAM ORIGREATER TMAN ORI EARTHQUAKE I

l ACTIONS I

BGlLDING l

RECORDER 1

0.05g IEQUAL TO O.05g IEQUAL TO 0,109 l INDUCED IOFC 1

- 1 I

VIBRATIONS I OPERA'E ALARM l GROUNO 1 BUT LESS THAM ~ i GROlMID l

l l

l-06E, 5-S l ACCELERATION I O.109 l ACCELERATION I I

f l

I

(

l l

I I

l l 2.7 l

1 I

I I

I Visua'ly inspect all Classt I

I XX l

XX l

I I p i p e ng a nd equ i pmerit fort i

I

(

l i

I I leaks I

I i

l I

I I

I IOPERATION ACTIONS l

1 l

I i

-l l

l l-^2.8 l

l l

I

{

l Complete within a 2t hour l l

1 I

I I

l l pe riod, a v i sua l inspec-1 I

XX XX l

XX XX i

XX XX l

i I tion or those valves l

l 1

I I

I listed in Tables 2A, 2B I

i I

l l

1 and 2C 1

1 I

I I

I l

1 I

I l_

l I

(

l 1

M 9

e e9

--p+.

,9 y

3 y

~

-g y-g p-"

g-p%-

=v--g

-q w

g s-

%r,vg=*-a---,++eyq

-+3,-ww

+a%--

,4p,.-

y+

l AOP APP K-1 Issue 59 e

age 2 of 12 OPubllC FORT ST. VRAIN NUCLEAR CENERATING STATION service

PusuC saRVDCa COMPANY OF COLORADO 1.5 Greater Then Or Ecual To 0.100 Ground Acceleration If developed film indicates horizontal ground acceleration greater than, or equal to, 0.10g design limits may have been. exceeded. All Class I structures, systems and 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.

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

DISCUSSION OF OPERATOR ACTION Guswa-l 2.1

n'4 Defueling activities terminated l

Verify Defueling activities terminated until all follow up l

activities complete.

I 2.2 Monitor Critical Safety Functions Per E0P's.

l Monitor critical safety functions per E0P's and perform l

any required steps per E0P's, i

2.3 Verify authenticity of alarm by visual examination of seismoscope glass.

If au~thenticity of recorder operation is questioned, the i

moked glass of the seismoscope may be' examined to see if mtion was recorded.

l 2.4 Process all accelerogranh photocraphs as soon as possible.

i 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 0.10g, follow-up actions will be 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.

O FORM ID)372. 2 3843

!

ML20034C780

Text

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