ML20205C373

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Rev 2 to Steam Generator Turbine Rupture W/Loss of Reactor Coolant Saturated Recovery Desired
ML20205C373
Person / Time
Site: Millstone, Haddam Neck, 05000000
Issue date: 06/15/1988
From:
CONNECTICUT YANKEE ATOMIC POWER CO.
To:
Shared Package
ML20204H467 List: ... further results
References
EOP-35-ECA-3.2, NUDOCS 8810260473
Download: ML20205C373 (25)
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Text

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STATII)N PR0CEDURE COVER S; T

  • A. IDENTIFICATION Number: E0P 35 ECA-3.2 Rev. 2

Title:

SGTR WITH LOSS OF REACTOR COOLANT SATURATED RECCVERY DESIRED Prepared By: A. W. HORTON/J. L. BUCKINGHAM

8. REVIEW I have reviewed the above procedure and have found it to be satisfactory.

TITLE SIGNA 7'REJ DATE DEPARTMENT HEAD 2 _ ,

__ _ c, / 6 7 J C. SPECIFIC UNREVIEWED SAFETY QUESTION EVALUATION REQUIRED:

Modifies intent of procedure and changes operation of systems as described in design documents. YES ( ) NO ,[4 4

(If yes, perform written USQ determination and Safety

  • Evaluation, and contact Manager, Safety Analysis Branch to j determine need for Integrated Safety Evaluation.)

J ENVIRONMENTAL REVIEW REQUIRED (Adverse environmental impact) YES ( ) NO [g O. SPECIFIC SAFETY EVALUATION REQUIRED Affects response of safety systems, performance

cf systems which may have been credited in the safety analysis or non-credited systems which may indirectly affect safety syst2m response. YES ( ) NO (W (If yes, perform written Safety Evaluation and contact Manager, Safety Analysis Branch to determine
need for Integrated Safety Evaluation.) i E. YES f ) NO (-}- !

INTEGRATED SAFETY EVAL..UATION REQUIRQ F.

'On a6 fit 8n tote'(vTeii, wito itaPROM0URERfQUIRCSP0hSORCREVIE

~

a fEi response f must be documented in th FORJSORC6.eetine, minutes) YE3 ( @ NO ( )  !

G. 50RC APPROVAL SORC Meetit,g Number 3 -gf-/Ql H. APPROVAL AND IHPLEMENTATION The aitoched procedure is herehy approved, and effective on the date below:

' d /6((

51ation/ Service / Unit Superintendent Effective Date SF301/9/s/SES/87-12/lof1 0010260473 DR Genoo7 p ADOCM 05000213 von

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E0P 35 ECA-3.2 Page 1 '

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. Rev. 2 i

I SGTR WITH LOSS OF REACTOR COOLANT SATURATED RECOVERY DESIRED l i

Page No. Eff. Rev. (

2

) 1 - 22 l Attachment A 2 1

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, SGTR WITH LOSS OF REACTOR COOLANT EOP 35 ECA-3.2 Page 2 h SATURATED RECOVERY DESIRED Rev. 2 ,

A. PURPOSE i L

P This procedure provides actions to cool down and depressurize the RCS to cold shutdown conditions while minimizing loss of RCS inventory. .

t B. ENTRY CONDITIONS This procedure was written for Modes 1, 2 and 3, assuming RHR is not ,

in service. Using this procedure when not in these modes requires a '

step by step evaluation to determine if the required action is still applicable to current plant conditions.  !

l f This procedure is entered from i a

1) E0P 35 ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - aUBC00 LED ,

i RECOVERY DESIRED, Step 12, when RWST level is low without a . [

j corresponding increase in containment sump level.  ;

2) E0P 35 ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBC00 LED RECOVERY DESIRED, STEP 12, when ruptured SG 1evel is high and plant staff selects saturated recovery method. l 1

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STEP ACTION /tXPECTED RESPCNSE l RESPONSE NOT OSTAINED CAUTION If RWST level decreases to < 520,000 gal., the ECCS System should be aligned for cold leg recirculation using E0P 35 ES-1.3,  !

TRANSFER TO COLD LEO RECIRCULATION.  ;

NOTE

1. The first twelve steps of E0P 15 ECA-3.1, SGTR WITH LOSS OF  ;

REACTOR COOLANT - SUBC00 LED RECOVERY DESIRED, should be performed before continuing with this procedure.

2. Foldout page should be open.

1 Add makeup to RWST as necessary per OP 3304C  !

PRIMARY MAKEUP AND r CHEMICAL ADDITION l

CAUTION RCS pressure should be monitored. If RCS pressure decreases to < 300 psia (450 psia, for adverse containment) the RHR ,

pumps must be manually restarted to supply water to the RCS.

f 2 Check If RHR hucps Should [

Be Stopped [

a. Check RCS pressure s. Go to Step 3.  ;
1) Pressure > 300 paie [

(450 psia FOR AD*.'1EPSE  !

COTTAINhENT) ,.

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2) Pressure - STABLE OR INCRT,ASING r
b. STOP RHR pumps and place in A1.TTO f

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star ActioM/supscreo nesponsa nesponsa Nof osTAINEo

3 Check If SGs Are Not Faulted
a. Check pressures in all a. Verify all faulted SGs SGs - isolated unless needed for RCS cooldown
1. NO SG PRESSURE 1. Main Steam Line 1 DECREASING IN AN Isolation and I UNCONTROLLED P.ANNER Bypass Valves l l
2. NO SG COMPLETELY 2. Main Feed Line  !

DEPRESSURIZED Isolation and i l Bypass Valves j

3. Chemical Feed Lines j 4. Blowdown and Sampling Lines
5. Auxiliary Feed Lines
6. Steam Supply to TDAFW Pump  ;

l 7. SG atmospheric dump t valves  !

i i 8. Main steamline low i

point drains l 4 9. TDAFW pump low point  !

drains j i

IF NOT, THEN go to E0P j 35 L-2, "AULTF.D STEAM  ;

, GENERATOR ISOLATION,  ;

j Step 1. ,

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suin WITH Loss OF REAGTOR COOLANT EOP 35 ECA-3.2 Paga 5 SATURATED RECOVERY DESIRED Rev. 2 STEP ACTION /EXPECTIO RESPONSE RESPONet NOT OSTAINEO CAUTION The CST is an alternate water source for AFW pumps if DWST level decreases to > S0,000 gal.

4 Check intact SG Levels

a. Narrow range level a. Maintain total feed

> 4% (34% FOR flow > 525 gpm until ADVERSE CONTAINMENT) narrow range level

> 4% (34% FOR ADVERSE CONTAIEtENT) in at least one SG. l

b. Control feed flow to b. IF, narrow range level maintain narrow range level in any intact SG between 4% (34% FOR continues to increase ADVERSE CONTAINMENT) in an uncontrolled and 50% manner, THEN go to E0P 35 E-3, STEAM i GENERATOR TUBE RUPTURE, 4

O v STEP 1.

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SUIM WITH LOSS OF REACTOR COOLANT E0P 35 ECA-3.2 Paga 6 SATURATED RECOVERY DESIRED Rev. 2 cm (sitP Acilog/exPacteo assPoNSE RESPONSE NOT 09TAIMEO NOTE

1. Shutdown margin shou.1d be maintained during RCS cooldown.
2. Low steamline pressure SI signal should be blocked when PZR pressurn decreases to < 2000 psia.

5 Initiate RCS Cooldown To Cold Shutdown

a. Maintain cooldown rate in RCS cold legs < 100*F/HR
b. Use RHR System if in service
c. Dump steam to condenser c. Dump steam from intact .

from intact SG(s) SG(s) to atmosphere. E no intact SG available, THEN perform the following

1. Use faulted SG.

E

2. If necessary use ruptured SG after consulting with Directer of Station Emergency Organization (DSEO) and performance ,

of offsite releave i calculatious  :

6 Check RCE Subcooling Rased On Go to Step 20.

Core Exit Tt:s > S0 T (90*F  !

FOR ADVERSE CONTAIhW.NT) ,

7 Check If ECCS In In Service - Go to Step 16.

a. SI Pump - ANY KUNNING  !
b. Charging Pump Cold Legs Injection valves

- OPEN

- Ok -

c. RHR pumps - ANY RUNNING IN SI MODE O P50ea 1 344

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e e t suin WITM LO55 OF REAGIUR COOLANT EOP 35 ECA-3.2 Paga 7 SATURATED RECOVERY DESIRED Rev. 2

/'~ T STEP ACTION / EXPECTED RESPONSF RESPONSE NOT OSTAINED 8 Place All PZR Heater Switches In 0FF Position  :

CAUTION Voiding may occur in the RCS during RCS depressurization. This  :

I will result in a rapidly increasing PZR level.

1 9 Depressurize RCS To Refill PZR '

a. Use normal PZR spray a. Use one PZR PORV.

IF no PORV available.

THE j use auxiliary spray.  :

t

b. PZR level > 7.0% b. Continue with Step 10. ,

(50% FOR ADVERSE VKEN, level > 7.0% (50% * !

CONTAINMENT) FOR ADVERSE CONTAINMENT)

THEN do Step 9c. ,

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c. Stop RCS depressurization i

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SGTR WITH LOSS OF REACTOR COOLANT E0P 35 ECA-3.2 Pegs 8 i SATURATED RECOVERY DESIRED Rev. 2 f O

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- eTsp ACTION /tXPEC7ED RESPONSE RESPONSE NOT OSTAINEO -  !

CAUTION If seal injection had previously been lost, the affected RCP(s) should not be started prior to a status evaluation.

)

NOTE i

RCPs should be run in order of priority (2,1 THEN 3 or 4) to provide normal PZR spray. I i

10 Check If an RCP Should Be .

Started .  :

a. All RCEs - STOPPED a. STOP all but one RCP.

Go to Step 11. -

b. RCS subcooling based b. Go to Step 20.

on core exit TCs

() > 30*F (90*F FOR ADVERSE <

CONTAINMENT)

c. PZR level > 7.0% c. Return to Step 9. [

(50% FOR ADVERSE l CONTAINMENT) j

d. Try to start a RC?
1) Establish conditicos '

for starting a RCP ,

a) RPCCW to RCP t Thermal Barrier ,

ALIGNED b) di Seal Leakoff Flow -

> .2 spa c) di Seal aP) aio psid

2) START one RCP O

OP$0641 3 44

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STEP ACTIOM' EXPECTED RESPONSE RESPONGS NOT OSTAINEO '

= __

, NOTE i l

1. After stopping any Charging or SI pump, RCS pressure should ,

be allowed to stabilize or increase before stopping another l y Charging or SI pump.

2. The charging pumps and SI pumps should be stopped on i d ,

alturudte ECCS trains when possible.  !

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SATURATED RECOVERY DESIRED Rev. 2

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STEP ACTION / EXPECTED RESPONSE

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RESPONSE NO t OSTAINED l

11 Chech If One Charging Pump Should Be Stopped ,

a. Two Charging l
a. Go to Step 12.  !

pumps - RUNNING

b. Determine required RCS subcooling from table i

SI PUMP RCS SUBC00 LING (F*)  :

STATUS l

NORMAL ADVERSE  ;

NONE RUN!!ING

[

64 119 l ONE I RUNNING 48 110 .

TWO .

RUNNING 46 110 l

c. RCS subcooling based on c. IF RCS hot les core exit TCs > REQUIRED temperatures > 370'F I SUBCOOLING (345'T FOR ADVERSE  !

CONTAINMENT), THEN go to Step 20.

1 Os IF RCS hot leg temperatures < 370*F .

I (345'F FOR ADVERSE +

l  !

l CONTAINMENT) THEN START a

one RHR pump if none running. IF at least one RHR pump can NOT be 7 operated, THEN go to j q Step 20. l l d. PZR level > 7.0% (50% d. DO NOT STO? CHARGING L j FOR ADVERSE CONTAINMENT) PUMP. Return to l 4

Step 9 t

e. STOP one charging pump 1: I f

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OPSX41 344

, SGTR WITH LOSS OF REACTOR COOLANT E0P 35 ECA-3.2 Page 11 SATURATED RECOVERY DESIRED Rev. 2 r

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wTEP ACTION /EXPECTEC RESPONSE RESPONSE NOT OSTAINED 12 Check If One SI Pump Should Be Stopped

a. Any SI pump - RUNNING a. Go to Step 13.
b. Determine required RCS subcooling from table RCS SUBC00 LING (*F)

SI PUMP ONE CHARGING PUMP RUNNING NO CHARGING PUMP RUNNING STATUS NORMAL ADVERSE NORMAL ADVERSE ONE RUNNING 77 136 -- --

l no RUNNING 44 108 48 111

c. RCS subcooling based on c. IF RCC hot leg core exit TCs > REQUIRED temperatures > 370'F SUBC00 LING (345'i FOR ADVERSE CONTAINMENT) THEN go t1 Step 20.

E RCS hot leg p temperatures < 370'F (345'F FOR ADVERSE CONTAINMENT) THEN START

, one RHR pumt. if none running. E at least one RHR pump can NOT be operated, THEN, go to Step 20.

A

d. PZR level > 7.0% d. DO NOT STOP SI PUMP.

1 (50% FOR ADVERSE Return to Step 9.

CONTAINMENT)

e. Stop one SI pump
f. Return to Step 12a.

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O OP5064-1 344

, SGTR WITH LOSS OF REACTOR COOLANT E0P 35 ECA-3.2 Page 12 SATURATED RECOVERY DESIRED Rev. 2 O -

STEP ACTION /ERPECTED RESPONSE RESPONSE NOT OSTAINED 13 Check If Normal Charging Should Be Established

a. Check the following a. Go to Step 20.
1) SI pumps - STOPPED AND
2) Charging pumps - ALL BUT ONE STOPPED
b. RCS subcooling based on b. IF RCS hot leg core exit TCn > 41*F Temperatures > 370*F (104*F FOR ADVERSE (345'F FOR ADVERSE CONTAINMENT) CONTAINMENT THEN go to Step 20. IF RCS hot-leg temperatures

< 370'F (345'F FOR ADVERSE CONTAINMENT) THEN START one RHR pump if none running. IF at least one RHR pump can NOT be operated, THEN go O to Step 20.

c. PZR level > 7.0% (50% c. Return to Step 9.

FOR ADVERSE CONTAINMENT) 14 Establish Normal Charging Pump Injection Flow Path

a. IF two charging pump cold leg injection valves are open, THEN CLOSE one valve
b. Establish 60 spa normal charging path
c. CLOSE the Charging Pump miniflow isolations to the RWST (3CHS*MV8511A/B)
d. CLOSE a Charging Pump Cold Leg Injection valve 15 OPEN the Charging Pump Recite 4 Isolations O

I OPW6&1 3 44 m

, SGTR WITH LOSS OF REACTOR COOLANT E0P 35 ECA-3.2 Page 13 SATURATED RECOVERY DESIRED Rev. 2

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STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 16 Check If Charging Flow Should Be Controlled to Maintain Reactor Coolant Inventory

a. RHR pumps - NONE RUNNING a. Go to Step 20.

IN SI MODE

b. Control Charging Flow To Maintain Reactor Coolant Inventory
1. RVLMS plenum level

> 82%

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eTSP ACTION /tXPSCTRO RESPONSE RESPONSE NOT 08TAINED

, CAUTION 1

If seal injection had previously been lost, the affected RCP(s) should not be started prior to a status evaluation.

NOTE RPCs should be run in order of priority (2, 1 Then 3 or 4) to provide normal PZR spray.

17 Check RCP Status

a. RCPs - AT LEAST ONE a. Try to start an RCP ,

RUNNING .

1) Establish Conditions for Starting an RCP a) RPCCW to thermal barrier - ALIGNED b) #1 Seal leak off

, flow > .2 spa c) #1 Seal AP) 210 psid

2) START one RCP. IF an RCP can NOT be started, THEN refer to ATTACHMENT
A to verify natural circulation. IF natural circulation NOT verified, THEN increase dumping steam.
b. STOP all but one RCP i

i OPNS&t 344

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sum w1Tu LOSS OF REACTOR COOLANT E0P 35 ECA-3.2 Page 15 SATURATED RECOVERY DESIRED Rev. 2 O' _ sys, Action /supscreo ResPONss RESPONGS NOT OSTAlf0E0 CAITTION

1. Voiding may occur ~in the RCS during RCS depressurization.

This will result in a rapidly increasing PZR level.

2. If SI has been terminated, the accumulators should be isolated prior to depressurizing the RCS to < 709 psia.

18 Depressurize RCS To Saturation At Core Exit

a. Determine saturation pressure for core exit .

TCs .

b. Use normal PZR spray b. Use one PZR PORV. IF ,

no PORV available, THEN use auxiliary spray.

c. Control PZR heaters as necessary
d. Depressurize RCS until EITHER of the following conditions satisfied
1. PZR level > 73% (50%

FOR ADVERSE CONTAINMENT)

OR

2. RCS pressure - AT SATURATION FROM STEP 18A O

OP5064-1 344 I

SGTR WITH LOSS OF REACTOR COOLANT E0P 35 ECA-3.2 Page 16 -

SATURATED RECOVERY DESIRED Rev. 2 O -

STEP ACTION /EIPSCTED RESPONSE RttPONSE NOT OGTA.lNEO  ;

I i

CAUTION Dilution of RCS boron concentration may occur on i transfer of secondary water into the RCS.

19 Verify Adequate Shutdown Margin

a. Sample RCS I
b. Shutdown margin - b. Borate as necessary i ADEQUATE ,

20 Verify ECCS Flow Not Required a t

a. Core exit TCs - DECREASING a. Increase dumping steam. IF core exit TCs

~

do NOT decrease, THEN  !

manually operate ECCS i pumps as necessary. .

b. RVLM3 plenum level b. Manually operate ECCS f

> 82%. pumps as necessary 1 21 Check If SI Accuculators [

Should Be Isolated  ;

4. RCS subcooling based on a. IF_ at least two RCS hot  ;

cc.,re exit TCs > 30*F leg temperatures < t (90'F FOR ADVERSE 375'T THEN go to j CONTAINMENT) Step 21C. IJF NOT,  ;

THEN Go to Steps 22. '

r t

b. PZR level ) 7% (50% i YOR ADVERSE CONTAINMENT) b. Return to Step 9. [

l

c. Restore power to isolation l valves (32-2R-RSF, 32-2W-R3J, 32-2R-F4M, 32-2W-F4M)  ;
d. CLOSE all SI accumulator d. Vent any unisolated isolation valves accumulators
e. Remove power to accumulator isolation valves O

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svin witn tuss ur nr.at.avn t.vvLMT r.vr a r.UA-J.Z rage U ]~

  • SATURATED RE".0VERY DF.8tRED Rev. 2 i i

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- SYtp ACTION /tXPECTRO RESPONSS RESPONSE NOT 09TMwE0 22 Check If Diesel Generators  !

Should Be Stopped l

a. Verify ac energency busses - a. Try to restore offsite j ENERGIZED BY OITSITE POWER power to ac emergency busses.  !
b. RESET any LOP, SIS or CDA .

signal at MB2.

c. Stop any unloaded diesel generator and place in standby
d. RESET station LOP at both Sequencer panels,
e. RESET, then turn ON each Diesel Sequencer Automatic ,

Tester toggle switch,

f. CLOSE Feeder Breakers to Emergency Generator Distribution Panels 3EGS*PNLIA at 32-1T-3H and 3EGS*PNLIB at 32-1U-3F.

23 Minimize Secondary System Contamination

a. STOP condensate reject to condensate surge tank
b. Remove all but two condensate desins from service
c. Start the Auxiliary Boiler system to supply auxiliary steam loads

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suan WITM LOSS OF REACTOR C00LAhT LOP 35 ECA-3.2 Pega 18 SATURATED RECOVERY DESIRED Rev. 2

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eTEP ACTION / EXPECTED RESPONSE RESPONSE NOT OSTAINEO 24 Check RCP Cooling Flows

a. RPCCW to RCP thermal a. Refer to OP 3330A, barrier - ALIGNED REACTOR PLANT COMPONENT COOLING n
b. RCP seal injection flow b. Refer to OP ??04A
CHARGING AND LETDOWN
1) Check flow between 8 and 13 gym.
2) Check VCT temperature

< 135'F

3) Check RCS pressure

> 115 psia 25 Check If RCP Seal Return Flow Should Be Established ,

a. RPCCW flow available a. Go to Step 26, i to seal water heat exchanger 1

l b. OPEN RC? Seal Header Containment Isolation 3

l valves - FLOW ESTABLIGHED 26 Check If Source Range Detectors Should Be Energized

! a. Check intermediate range a. Continue with Step 27.

flux < 10E-10 amps WHEN flux < 10E-10 amps i on Post Accident Neutron Monitor, THEN do Steps 26b ano c.

a

b. Verify source range b. Manually energize

' detectors - ENERGIZED source range detectors

c. Transfer nuclear recorders to source range scale 27 Shut Down Unnecessary Plant Equipment j a. All but one condensate pump
b. All but one circulating water pump per bay
e. Hoisture separator drain pumps
d. 4th point heater drain pumps O

OPK6&1 3-44

Du1K Wiln LU33 UP KLALAUK LUULANI LUt' J) LGA-J.Z l'a gs 19 SATURATED RECOVERY DESIRED Rev. 2 O -

STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OSTAINED CAUTION Feed flow should NOT be initiated to the ruptured SG if it is faulted unless needed for RCS cooldown.

NOTE In the following step, it is intended that the operator allow the ruptured SG to drain to a low narrow range level and then refill it to a high narrow range level rather than continuously feeding the ruptured SG to control level.

28 Check Ruptured SG(s) Narrow Refill ruptured SG to Range Level > 4% (34% FOR 82% (61% FOR ADVERSE ,

ADVERSE CONTAINMENT) CONTAINMENT) using feed flow. IF either of the following conditions occurs, THEN stop feed flow to the

~

ruptured SG unless needed for RCS cocidown, and go to Step 30.

a. Ruptured SG pressure decreases in an uncontrolled manner.

0,.R

b. Ruptured SG pressure increases to 1100 psig.

O OPS 441 344

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suin WITH Loss OF REActun COOLANT EOF 35 ECA-3.2 Page 20 SATURATED RECOVERY DESIRED Rev. 2 O -

STEP ACTION /EXPECTSO RESPONSE RESPONSE NOT 09TAINED 29 Check Status Of Steam Generators

a. Two Steam Generators a. With < two intact intact steam generators, consult with the Director of Station Emergency Organization (DSEO) on advisability of isolating the ruptured steam generators by closing the appropriate loop stop valves.
b. No RCPs operating and b. If operating RCP in an plant verified in natural intact steam generator circulation in accordance loop, then so to 29C. ,

with Attachment A. .

OR If operating RCP in a ruptured steam generator loop then go to Step 30.

() c. Close ruptured steam generators (s) loop isolation valves with concurrence of the Director of Station Emergency Organization (DSEO)

O CPW6&1 3-44

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  • SGIR WITH LOSS OF REACTOR COOLANT E0P 35 ECA-3.2 Pege 21 SATURATED RECOVERY DESIRED Rev. 2

[ )

STEP ACTION / EXPECTED RESPONSE RESPONet NOT OBTAINED 30 Check If RCPs Must Be Stopped

a. Check the following a. Go to Step 31,
1) Number 1 seal differential pressure < 210 psid OR
2) Numbe F1 seal leakoff flow

< .2 gpm

b. STOP affected RCP(s)

NOTE At 425' RCS temperature, OP 3208 PLANT COOLDOWN should be used (in parallel with the following steps) with steps being evaluated for applicability based on plant conditions.

31 Cooldown RCS By Dumping Steam IF condenser not available, To Condenser and BLOCK Low dump steam to atmosphere Steamline SI Signal using an intact SG p) l V 32 Check If RPR System Can Be i Placed in Cooldown Mode I

a. Check the following a. Go to Step 33.

l 1) RCS temperatures l < 350'F (350'F FOR ADVERSE I CONTAIh?iEhT]

l 2) RCS pressure < 390 psia (390 psia FOR ADVERSE

, CONTAINMENT) 1

b. Cocault Director of Station l Teergency Organization (DSEO) l to determine if RHR System should be placed in cooldown mode 33 Check RCS Temperatures Return to Step 4.

@ RVUiS Head TC's

< 200*F CPkW1 3 84

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susa WITN LOSS OF REACTOR COOLANT E0P 35 ECA-3.2 Past 22 ,

SATURATED RECOVERY DESIRED Rev. 2

- ofsp ActiowszpscTso assposses assposses Not OSTMNeo l

34 Evaluate Long Term Plant t Status  !

a. Maintain cold shutdown i conditions i
b. Consult Director of Station Emergency I Organiz* tion (DSEO) f i

- FINAL -

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j suan w1In LU53 Ut REALIVK UUULANT E0P 35 ECA-3.2 Pag 2 1 of 1 ,

SATURATED RECOVERY DESIRED Rev. 2 l

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I ATTACHMENT A  :

t I

The following conditions support or indicata natural circulation flow under  !

saturated conditions l l

1. SG pressures - STABLE OR DECREASING  !
2. RCS hot les temperatures - STABLE OR DECREASING [

i

3. Core exit TCs - STABLE OR DECREASING i l 4. hCS cold les temperatures - AT SATURATION TEMPERATURE FOR SG l l PRESSURE  ;

1 l

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lr FOLDOUT FOR E0P 35 ECA-3.2 PROCEDURE

1. SI REINITIATION CRITERIA i Manually operate ECCS pumps as necessary g EITHER condition listed '

below occurs k a) Core exit TCs - INCRCASING

{

- OR - [

b) RVIJts plenue level LISS THAN 82% t i

2. RED PATM

SUMMARY

l

a. SURCRITICALITY - Nuclear power > 5% l
b. CORE COOLING - Core exit TCs greater than 1200'F
c. HEAT SINK - Narrow range level in all SGs < 4% (34% FOR ADVERSE l CONTAINMENT AJh total feedwater flow 525 spa l
d. INTEGRITY - Cold les temperature decrease > 100'T in last 60 l minutes AND RCS cold les temperature 252*F  :
e. CON ~AINMENT - Containment pressure > 60 psia .
3. SECONDARY MTEGRITY CRITERIA Go to E0P 35 -2. FAULTED STEAM GENERATOR ISOLATION, Step 1 ~IF

~ 'THER condition listed below occurs (UNLESS needed for RCS

.ooldown),

a. Any F.) pressure is decreasing in an uncontrolled manner, AND has NOT been isolated.

O b. Any SG has completely depressurized, AND has NOT been isolated.

4. COLD LEG RECIRCULATION SWITCHOVER CRITERION Go to E0P 35 ES-1.3, TRANSFER TO COLD LEG RECIRCULATION, Step 1. E RWST level decreases to < 520,000 gal.
5. AFV SUPPLY SWITCHOVER Establish the CST alternate AW water supply g DWST level decreases to < 80,000 gal.

O

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