ML20205C415

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Rev 2 to Emergency Operating Procedure EOP 35 ECA-3.3, Steam Generator Tube Rupture W/O Pressurizer Pressure Control
ML20205C415
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-3.3, NUDOCS 8810260485
Download: ML20205C415 (18)


Text

O STATI*0N PR0CE0VRE COVER SHE

  • A. IDENTIFICATION Number: E0P 35 ECA-3.3 Rev. 2

Title:

SGTR WITHOUT PRESSURIZER PRESSURE CONTROL Prepared By: A. W. HORTON/ JOHN BUCKINGHAM B. REVIEW I have reviewed the aboue procedure and have found it to be satisfactory.

TITLE SIGNATURE DATE i OEPARTMENT HEAD g /i!ef e J t

i i

C. SPECIFIC UNREVIEWED SAFETY QUESTION EVALUATION REQUIRED:

Modifies intent of procedure and changes operation i of systems as described in design documents.

YES [ ] NO ,[T '

(If yes, perform written USQ determination and Safety *  ;

Evaluation, and contact Manager, Safety Analysis Branch to  !

determine need for Integrated Safety Evaluation.) l

, ENVIRONMENTAL REVIEW REQUIRED (Adverse environnental impact) YES ( ) NO [& [

D. SPECIFIC SAFETY EVALUATION REQUIRED Affects response of safety systems, performance of systems which may have been credited in the safety analysis or non-credited systems which may indirectly affect safety system response. YES [ ] NO ( t "  !

i

! (If yes, perform written Safety Evaluation and ,

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

E. INTEGRATED SAFETY EVALUATION REQUIRED YES [ ] NO[T F. PROCEDURE REQUIRES h SORC REVIEW (In addition to revfiw, it with e YES response must be documented in the OR /SORC meeting minutes.) YES [ [ NO ( )

G. SORC APPROVAL SORC Meeting Number .3 Pf-/dY I

H. APPROVAL AND IMPLEMENTATION  !

The attached procedure is hereby approved, and effective on the date below: {

- 41./>"-ff ('

Station / Service / Unit Superintendent Effective Date SF301/9/s/SES/87-12/20fl 8910260405 881007 PDR l 1

P ADOCK 05000213  !

] PDR J

E0P 35 ECA-3.1 page 1

  • Rev. 2 STEAM GENERATOR TUBE RUPTURE k'ITliOUT PRESSURIZER PRESSURE CONTROL Page No. Eff. Rev 1 - 16 2 Attachment A 2 4

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, STEAM GENERATOR TUBE RUPTURE WITHOUT E0P 35 ECA-3.3 Page 2 PRESSURIZER PRESSURE CONTROL I.ev. 2 l O,

A. PURPOSE This procedure provides actions for a SGTR with coincident loss of nnrmal and auxiliary pressurizer sprays and PORVs.

B. ENT'tY CONDITIONS This procedure was written for modes 1, 2, and 3 assuming RlIR is not ,

in service. Using this procedure when not in these modes requires a j step by step evaluation to determine if the required action is still applicable to current plant conditions.

This procedure is entered from E0P 35 E-3, STEAM GEVERATOR TUBE RUPTURE, Step 18, when pressurizer pressure control is not available.

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i STEAM OENERATOR TliBE RUPTURE WITH0lTI E0P 35 ECA-3.3 Page 3  ;

4 PRESSURIZER PRESSURE CONTROL Rev. 2 [

.. L 1 -

- step ACTION /EEPSCTto RSSPONet RESPONSE NOT 00TA4NED

(

1 j NOTE l j Toldout page should be open l J  !

t CAUTION f If at any time, during the use of this E0P, the ruptured SG(s) narrow range level exceeds >

82% and is increasing in an uncontrolled manner, OR  !

is offscale high THEN proceed directly to step 7.

  • 1 Check Ruptured SG(s) Narrow Go to Step 7. 1 Range Level < 82% ,

(61% FOR ADVERSE CONTAINMFNT) , i 2 Try To Establish Nor'aal p PZR Spray l

a. Check RCP status - AT a. Try to start one RCP  !

LEAST ONE RUNNING IN in loop with spray line l EITHER LOOP 1 OR LOOP 2  ;

O 1) Establish conditions for starting a RCP

a. RPCCW to RCP [

thermal barrier - I ALIGNED

b. #1 Seal leakoff [

> .2 spa j

c. #1 Seal AP > 210

~

i psid (

2) START one RCP. IF a

~

RCP can NOT be l started THEN go to (

Step 3  ;

i

b. Normal spray - AVAILABLE b. Go to Step 3. [
c. Go to E0P 35 E-3, STEAM GENERATOR TUBE RUPTURE, i Step 17 f

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1 e m si va.

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, STEAM GENERATOR TUBE RUPTURE WITHOUT E0P 35 ECA-3.3 Pago 4 PRESSURIZER PRESSURE CONTROL Rev. 2 D -

STEP ACTION / EXPECTED RESPONtt RESPON88 NOT 001 AINED 3 Try To Restore PZR PORV

a. Establish conditions for a. IF no PZR PORV can be opening a PZR PORY opened. THEN go to Step 4.
1) Check PZR PORV power available
2) Check PZR PORV isolation valves open.
b. Go to E0P 35 E-3, STEAM GENERATOR TUBE RUPTURE, Step 18 4 Try To Establish Auxiliary Spray
a. SI pumps - BOTH RUNNING a. Try to START pumps. .

IF any SI pump can by be started THEN go to Step 5.

b. Charging pumps - AT LEAST b. Try to START one ONE RUNNING charging pump. If no f' N pump can be started than

() go to Step 5

c. Establish Normal charging flow
d. CLOSE Charging Pump to Reactor Cold Les Isolation valves
e. Establish Auxiliary Spray e. Go to Step 5.
1) Establish normal letdown
2) Unlock and OPEN Auxiliary spray valve
f. Go to E0P 35 E-3, STEAM GENERATOR TUBE RUPTURE, Step 17b o

OPK661 344

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L STEAM GENERATOR TUBE RUPTURE WITHOUT E0P 35 ECA-3.3 Pass 5 ,

PRESSURIZER PRESSURE CONTROL Rev. 2 I O - efsp ACTtow/SEPecteo Response mesponse not ceimmeo CAtTTION  !

The CST can be used as an Alternate water  !

source for the AFW pumps if DWST level decreases to < 80,000 gal.

5 Check Intact SO Levels i

a. Narrow range level > 4% a. Maintain total feed [

(34% TOR ADVERSE flow 3 525 spa until CONTAINMENT) narrcw range level  ;

> 4% (34% FOR ADVERSE  ;

CONTAINMENT) in at l 1 east one SG .  !

b. Control feed flow to b. IF narrow range level  ;

maintain narrow range in any intact SG l' 1evel between 4% (34% FOR continues to increase ADVERSE CONTAINMENT) and in an uncontrolled

  • 50% manner, THEN go to [

E0P 35 E-3, STEAM O

GENERATOR TURE RUPTURE, l Step 1 6 Check PZR Level Return to Step 1.

> 7% (50% TOR ADVERSE CONTAINMENT) i h

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STEAM GENERATOR TUBE RI'?TURE WITHOUT E0P 35 ECA-3.3 Pass 6 PRESSURIZER PRESSURE ;0NTROL Rev. 2 O

- etsp - Actiewespectes neePowse neePONSE N07 09TMNES 7 C'eck n If ECCS Can Be Terminated

a. RCS subcooling based on a. DO NOT STOP ECCS PUMPS.

core exit TCs > 30*F (90'T Go to E0P 35 ECA-3.1, FOR ADVERSE CONTAINMENT) SGTR WITH LOSS OF REACTOR COOLANT-SUBCOOLED RECOVERY DESIRED, Step 1.

b. Secondary heat sink b. IF neither condition satisfied, THEN DO NOT
1) Total feed flow to STOP ECCS PUMPS. Go to SGs > 525 spa AVAILABLE E0P 35 ECA-3.1, SGTR WITH LOSS OF REACTOR COOLANT - SUBC00 LED RECOVERY DESIRED, Step 1.

9R,

2) Narrow range level in e at least one intact SG

> 4% (34% FOR ADVERSE ,

CONTAINMENT)

c. RVLMS plenum level c. DO NOT STOP ECCS PUMPS.

> 19% Go to E0P 35 ECA-3.1, O

SGTR WITH LOSS OF REACTOR COOLANT - SUBC00 LED RECOVERY DESIRED, Step 1.

d. Ruptured SG(s) narrow d. DO NOT STOP ECCS PUMPS.

range level - INCRF.ASING Return to Step 2.

IN AN UNCONTROLLED MANNER OR OFFSCALE HIGH 8 STOP ECCS Pumps And Place In Auto

a. SI pumps
b. All but one charging pump. -

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OPW84-1 344

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STEAM GENERATOR TUBE RUPTURE WITHOUT E0P 35 ECA-3.3 Pass 7 [

PRESSURIZER PRESSURE CONTROL Rev. 2 '

1 .

- sTap actiowsapactes neapoNes nespoNes NOT osTAINEo  ;

l i 9 Establish Normal Charging Pump i Injection Flow Path i

a. IF two charging pump cold j les injection valves are open, THEN CLOSE one valve I I
b. Establish 60 apa normal i charging path

}

c. CLOSE the charging pump i miniflow isolations to the ,

RWST (3CHS*MV8511A/B)

d. CLOSE a Charging Pump Cold Les Injection Valve l 10 OPEN the Charging Pump Recire
  • t Isolations 1 . l l

11 Verify ECCS Flow Not Required Manually operate ECCS pumpr.  !

a. RCS subcooling based on as necessary. Go to E0P 35 i I core exit TCs > 30*F ECA-3.1, SGTR WITH LOSS OF l

(90' FOR ADVERSE REACTOR COOLANT - SUBC00 LED l

CONTAINMENT) RECOVERY DESIRED, Step 1.

I b. RVLMS plenum level

> 19%

1 12 Check VCT Makeup Control System

a. Makeup set for greater a. Adjust controls as than RCS boron necessary concentration
b. Makeup set for automatic control 13 Establish Normal Letdown Establish excess letdown as per 00 3304A, CHARGING AND LETDOW 14 Align Charging Pump Suction To VCT
a. OPEN VCT header and outlet isol
b. CLOSE RWST Supply charging Pump Suct O

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, STEAM GENERATOR TUBE RUPTURE WITHOUT E0P 35 ECA-3.3 Page 8 PRESSURIZER PRESSURE CONTROL Rev. 2 7

STEP ACTION /tXPECTED RESPONSE RESPONSE NOT OBTAINED 15 Equalize Charging And Letdown Flows

a. Take manual control of charging
b. Control charging and seal injection flows to equal letdown and seal leakoff flows 16 Check If Diesel Generators Should Be Stopped
a. Verify ac emergency busses a. Try to restore offsite

- ENERGIZED BY OFFSITE power to ac emergency POWER busses

b. RESET any LOP, SIS, or CDA
  • signal at MB2
c. Stop any unloaded diesel generator and place in standby

/~~N ls

) d. RESET Station LOP at both Sequencer panels i 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 1

3EGS*PNLIB at 32-1U-3H l

l 17 Minimize Secondary System Contamination l

l

a. Stop condensate reject to i Condensate Surge Tank l

I b. Remove all but two demin l from service

c. Start the Auxiliary Boiler System to supply steam to l reduce system contamination

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STEAM GENERATOR TUBE RUPTURE VITHOUT E0P 35 ECA-3.3 Pmge 9 PRESSURIZER PRESSURE CONTROL Rev. 2

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STEP ACTION / EXPECTED RESPONSE = RESP 0NSE NOT OSTAINED 18 Check RCP Cooling - Normal

a. RPCCW to RCP thermal a. Refer to OP3330A, RPCCW barriers - ALIGNED
b. RCP Seal Injection Flow b. Refer to OP 3304A, CHARGING AND LETDOWN
1) Check flow between 8 and 13 GPM
2) Check VCT temperature

< 135'T

3) Check RCS pressure

> 115 psia 19 Check If RCP Seal Return Flow Should Be Established

a. RPCCW Flow available to a. Go to Step 20. .

seal water heat exchanger e

b. OPEN RCP Seal Water, Containment Isolation Valves 20 Check If Source Range Detectors

(~')s

(

Should Be Energized

a. Check intermediate range a. Continue with Step 21 flux < 10E-10 amps WiEN j flux < 10E-10 amps on Post Accident Neutron l Monitor, THEN do Steps 20b and c.
b. Verify source range b. Manually energize source detectors - ENERGIZED range detectors
c. Transfer nuclear recorders to sor.rce range scale 21 Shut Down Unneccessary Plant Equipment i
a. All but one condensate pump l
b. All but one circulating water pump per bay
c. Moisture separater drain pump s
d. 4th point heater drain

( pumps v

OPK$0i 3 44

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STEAM GENERATOR TUBE RUPTURE WITHOUT E0P 35 EA-3.3 Peg 2 10 PRESSURIZER PRESSURE CONTROL Rev. 2 SU* ! ACTIONsIIPECTED RESPONSE RESPON64 NOT OSTAINED NOTE Direction of Station Emergency Organization (DSEO) should decide whether to repair PZR pressure control systems or continue with this procedure. If PZR pressure control is established. PZR level should be restored to > 7%

(50% FOR ADVERSE CONTAINMENT) and then further recovery should continue with E0P 35 E-3, STEAM GENERATOR TUBE RUPTURE, Step 29.

22 Check If $1 Accumulators Should Be Isolated

a. Check the following a. Return to step 11.
1) RCS subcooling based on core exit TCS

> 30*F (90'F FOR .

{

ADVERSE CONTAINMENT) e

2) RVLMS pienem level

> 19%

b. Restore power to Accumulator isolation r~~'s valves.

(

) (32-2R-R5F, 32-2W-R3J.

32 *R-F4M, 32-2W-F4M)

c. CLOSE 011 SI accumulator c. Vent any unisolated isolatian valves accumulator
d. Remove power from Accumulator Isolation Valves CAUTION f Dilution of RCS boron concentration may occur on transfer of secondary water into the RCS.

23 Verify Adequate Shutdown Margin

a. Sample RCS
b. Shutdown margin - ADEQUATE b. Borate as necessary l 24 Maintain Required RCP Seal ,

7-~s Injection Flow between l l

8-13 gpm l

(v) 1 cw,34 i

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7 STEN 1 GENERATOR TU M VPTURE WITHOUT E0P 35 ECA-3.3 Pags 11 PRESSURIZER PRESSURE CONTROL Rev. 2 t . n O -

e739 &cTt0NisspecTse Resp 0 Net metPONGS NOT 00TalN80 j 25 Initiate RCS Cooldown To 350*F (350'F FOR ADVERSE CONTAINMENT) i

4. Maintain cooldown rate in -

RCS cold legs < 100'F/HR

[

l

b. Dump steam to condenser b. Dump steam from  ;

from Antact SG(s) intact SG(s) to  !

atmosphere.  !

IF no intact SG Uailable,TjHE use faulted SG l i

CAtTTION RCS and ruptured SG(s) presJure must be maintaine ,

less than the ruptured SG(s) PORV setpoint. '

26 Control Charging Flow To  !

Maintain RCS Subcooling

a. RCS subcooling based on a. Increase charging core exit TCs > 50'F flow to maintain f r

(110'F FOR ADVERSE subcooling > 50'T [

l CONTAINMENT) (110*F FOR ADVERSE

! CONTAINMENT) Go to Step 27.

1 l l b. Ruptured SG(s) nttrow b. Control charging flow  ;

I range level < 92% to maintain RCS pressure 1

(77% FOR ADVERSF at ruptured SG(s) ,.

CONTAINMENT) pressure. Go to Step 27.  !

f

, c. Ruptured SG(s) narrow c. Decrease charging flow i 3

range level - STABI.E OR to stabilize level.

l JECREASING Maintain RCS subcooling -

1

> 50'T (110'T FOR ADVERSE l 4 CONTAINMENT) l

_ 27 Check If RCS Cooldown Should Be Stopped 4 a. RCS temperature a. Return to Step 23. l I < 350'T l

b. Stop RCS cooldown i

) 28 Check RCS Pressure Go to Step 32, f

Q > 390 psia I

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STEAM GEVERATOR TUBE RUPTURE WITIIOUT E0P 35 ECA-3.3 Peg 2 ;2 PRESSURIZER PRESSURE CONTROL Rev. 2

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' - STE9 - ACTION / EXPECTED RESPONS RESPON6s NOT OSTAINED i NOTE In the following step, it is intended that the operator allow the ruptured SG to drain to a low narrow range ard then refill it to a high astrow range rather than continuously feeding the ruptured SG to control level.

29 Cbeck Ruptured SO(s. Narrow Refill ruptured SG to Range Level > 4% (34% FOR 82% (61% FOR ADVERSC ADVERSE CONTAINMENT) CONTAINMENT) using feed flow.

IF either of the following conditions occurs, THEN stop feed flow to ruptured SG and go to Step 30.

a. Ruptured SG pressure .

decreases in an uncontrolled manner gR

b. Ruptured SG pressure 7s increases to 1100 psig (Lj )

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STEAM GENERATOR TUBE RUPTURE WITHOUT E0P 35 ECA-3.3 Page 13

. PRESSURIZER PRESSURE CONTROL Rev. 2

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STEP - d .- ACTION /EXPECTSO RESPONSE RESPOegsg NOT OSTAINEO

'a leck Status Of Steam

'enerators Two Steam Generators a. With < two intact steam intact 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 plant verified in intact steam I

generator loop then natural circulation in accordance with Attachment A go to Step 300. .

SE i

If operating RCP in a ruptured steam generator loop then go to step 31.

f O)

( c. Consult Director of Station Emergency Organization (DSEO) on closing ruptured steam generator (s) loop isolation valves  !

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STEAM GENERATOR TUBE RUPTURE WITHOUT E0P 35 ECA-3.3 Page 14 PRESSURIZER PRESSURE CONTROL Rev. 2 L

STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OSTAINED CAUTION

1. Steam should not be released from a ruptured SG if water may exist in its steamline.
2. Ruptured SG pressure may decrease rapidly when steam is released NOTE The upper head region may void during RCS depressurization if RCPs are not running. This may result in a rapidly increasing PZR level. .

31 Depressurize RCS And Ruptured SG(s) To 390 psia (390 psia FOR ADVERSE CONTAINMENT)

a. Perform the following

() 1. Decrease. charging and increase letdown to initiate backfill 98

2. Initiate blowdown from

, ruptured SG(s) 9B

3. Dump steam from g, ruptured SG(s) 11 . Check RCS pressure b. Return to Step 30.

< 390 psia (390 psia o FOR ADVERSE CONTAINENT)

, c. Stop RCS depressurization i'

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, STEAM GENERATOR TUDE RUPTl'RE WITHOUT E0P 35 ECA-3.3 Page 15 PRESSURIZER PRESSURE CONTROL- Rev. 2 1

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aTEP ACTION / EXPECTED RESPONSE RESPONSE NOT OSTAINEO 32 Check If RHR System Can Be Placed In Cooldown Mode t

a. RCS temperature a. Return to Step 25. I

< 350'F (350'F FOR  !

ADVERSE CONTAINMENT)  !

l

b. RCS pressure b. Return to Step 29. '

< 390 psia (390 psia FOR ADVERSE CONTAINMENT) 4

c. Place RHR System in cooldown mode IAW OP 3208, PLANT COOLDOWN
CAUTION .

Dilution of RCS boron concentration may occur -

on transfer of secondary water into the RCS.

33 Verify Adequate Shutdown Margin

a. Sample RCS '
b. Shutdown margin - b. Borate as necessary ADEQUATE a

] 34 Initiate RCS Cooldown To Cold Shutdown

a. Maintain cooldown rate  ;

in RCS cold legs i

< 100'F/HR i

b. Use RHR System  !

OR  !

6 Dump steam to condenser Dump steam from intact SG(s)  !

from intact SG(s) to atmosphere. IF no intact SG available THEN use faulted SG. i J

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STEAM GENERATOR TUBE RUPTURE WITHOUT E0P 35 ECA-3.3 Page 16 PRESSURIZER PRESSURE CONTROL Rev. 2

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.t STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OETAINED 35 Control Charging Flow To Maintain RCS Subcooling

a. RCS subcooling based on a. Increase charging flow core exit TCs > 50*F to maintain subcooling (110'F FOR ADVERSE > 50*F (110'F FOR ADVERSE CONTAINMENT) ADVERSE CONTAINMENT). Go to Step 36.
b. Ruptured SG(s) narrow b. Control charging flow range level < 92% to maintain RCS pressure

[

(77% FOR ADVERSE equal to ruptured SG(s) i CONTAINMENT) pressure. Go to Step 36.

l

c. Ruptured SG(s) narrow c. Decrease charging flow '

range level - STABLE OR to stabilize level.

DECREASING Maintain RCS subcooling

> 54*F (110*F FOR ADVERSE l

CONTAINMENT) 36 Check If RCPs Must Be Stopped

a. Check the following a. Go to Step 37.
1) Number 1 seal O'

differential pressure

< 210 psid QR

2) Number 1 seal return j flow < .2 gpm
b. STOP affected RCP(s) 37 Check RCS Temperature - Return to Step 33.

AND RVLMS Head TCs 7 200*F 38 Evaluate Long Term Plant Statur

a. Maintain cold shutdown conditions
b. Consult Director ef Station Emergency Organization (DSEO)

-FINAL-O oPK4&t 344

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STEAM GENERATOR TUBE RUPTURE WITHOUT E0P 35 ECA-3.3 Page 1 of 1 PRESSURIZER PRESSURE CONTROL: Rev. 2 O -

eTEP ACTION / EXPECTED RESPONSE RESPONSE NOT OSTAINEO ATTACHMENT A The following conditions support or indicate natural circulation flow:

  • RCS subcooling based on core exit TCs > 30'F
  • SG pressures - STABLE OR DECREASING
  • RCS hot leg temperatures - STABLE OR DECREASING
  • Core exit TCs - STABLE OR DECREASING
  • RCS cold leg temperatures - AT SATURATION TEMPERATURE FOR SG PRESSURE O

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FOLDOUT FOR E0P 35 ECA-3.3 PROCEDURE

1. SI REINITIATION CRITERIA Manually operate ECCS pumps as necessary IF EITHER condition listed below occurs.
a. RCS subcooling based on core exit TCs < 30*F (90*F FOR ADVERSE CONTAINMENT)

-OR-

b. RVLMS plenum level < 19%
2. RED PATH

SUMMARY

a. SUBCRITICALITY - Nuclear power > 5%
b. CORE COOLING - Core exit TCs > 1200'F
c. HEAT SINK - Narrow range level in all SGs < 4% (34% FOR ADVERSE CONTAINMENT) AND total feedwater flow < 525 gpm 1
d. INTEGRITY - Cold leg temperature decrease > 100*F in last 60 minutes AND RCS cold leg temperature

< 252*F

e. CONTAINMENT - Containment pressure > 60 psia
3. SECONDARY INTEGRITY CRITERIA Go to E0P 35 E-2, FAULTED STEAM GENERATOR ISOLATION, Step 1.

IF EITHER condition listed below occurs ( UNLESS needed for RCS cooldown)

a. Any SG pressure is decreasing in an uncontrolled manner, AND has NOT been isolatad.

O b.

-OR-Any SG pressure has completely depressurized, AND had NOT been isolated.

4. AFW SUPPLY SWITCHOVER CRITERION Establish the CST alternate AFW water supply IF DWST level decreases to < 80,000 gal l

O