ML20205A401

Rev 4 to Emergency Operating Procedure EOP 2537, Loss of All Feedwater

ML20205A401
Person / Time
Site:	Millstone, Haddam Neck, 05000000
Issue date:	08/03/1988
From:	Brinkman S, James Smith CONNECTICUT YANKEE ATOMIC POWER CO.
To:
Shared Package
ML20204H467	List: A07413, Forwards Specific Emergency Operating Procedures for Use During Incident Response Ctr Activation ML20204H704 ML20204H734 ML20204H868 ML20204H928 ML20204H963 ML20204J027 ML20204J039 ML20204J092 ML20204J109 ML20204J115 ML20204J120 ML20204J128 ML20204J133 ML20204J139 ML20204J147 ML20204J497 ML20204J543 ML20204J565 ML20204J627 ML20204J633 ML20204J638 ML20204J642 ML20204J659 ML20204J669 ML20204J685 ML20204J707 ML20204J733 ML20204J739 ML20204J746 ML20204J767 ML20204J781 ML20204J786 ML20204J814 ML20204J824 ML20204J849 ML20204J853 ML20204J865 ML20204J878 ML20204J902 ML20204J914 ML20204J920 ML20204J939 ML20204J947 ML20204J954 ML20204J958 ML20204J965 ML20204J975 ML20204J982 ML20204J994 ... further results
References
EOP-2537, NUDOCS 8810250504
Download: ML20205A401 (24)

Text

.

STATIONPROCEDURECOVERSHEET A. IDENTIFICATION Numberr E0P 2537 Rev. 4,

\"

Title:

LOSS OF ALL FEE 0 WATER Prepared By: STEVE BRINKMAN B. REVIEW I have reviewed the above procedure and have found it to be satisfactory.

TITLE SIGNATURE DATE DEPARTMENT HEAD s 2e/gf o, m e- u

- chran sw r ,

C. SPECIFIC UNREVIEVE0 SAFETY OSdSTION EVALUATION REQUIRED:

Modifies intent of procedure and changes operation of systems as described in design documents. YES [ ] NO %

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

, Evaluation, and contact Manager, Safety Analysis Branch to

! determine need for Integrated Safety Evaluation.)

t ENVIRONMENTAL REVIEW REQUIRED .

, (Adverse environmental impact) YES ( ) NO (>d  ;

I

0. SPECIFIC SAFETY EVALUATION REQUIRED Affects response of safety systems, performance of systems which may have been credited in the ,

i safety analysis or non-credited systems which  !

may indirectly affect safety system response. YES ( ) NO %) l

(If yes, perform uritten Safety Evaluation an'd  ;

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

i j E. INTEGRATED SAFETY EVALUATION REQUIRED YES ( ) NO ()c]

j F. PROCEDURE REQUIRES PORC/50RC REVIEW

(In addition to review, items with a YES response ,

must be documented in the PORC/50RC meeting minutes.) YES @() NO ( ) i G. PORC/SORC APPROVAL PORC/50RC Meeting Number W 'l bl  !

[

APPROVAL AND IMPLEMENTATION L H.

The attached procedure is hereby approved, and effective on the date below: I l k $ /hMw Y7f Effective Date Shtion/ Service /UnitSuperintendent iO, SF301/9/5/SES/87-12/lof1

, 0010250504 881007 1 PDR ADOCK 05000213 4

P PDR

UNIT 2 LOSS OF ALL FEE 0 WATER Page No. Ef{. Rev.

1 - 16 4  !

O t

G E0P 2537 Page 1 Rev. 4

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e

~

m LOSS CF ALL FEEDWATER

1. PURPOSE 4

To provide the subsequent operator actions which must be accomplished in the event of a loss of maic and auxiliary feedwater. These actions are taken after completion of the Standard Post Trip Actions and a loss of all feedwater has been diagnosed. The actions of this procedure are necessary to ensure that the plant results in a stable ssfe condition.

2. ENTRY CONDITIONS

a. The Standard Post Trip Actions have been accomplighed and

b. Plant conditions indicate that a loss of all f'edwater e has occurred by one or more of the following i

1. Decreasing steam generator water level (C05)

11. Motor driven auxiliary feedwater trip / lockout (C05)

j. iii. Low-low conden' sate storage tank level (C05) j 3. OPERATOR ACTIONS Instructions Contingency Actions

3.1 Verify Standard Post Trip Actions, 3.1 Perform Standard Post Trip E0P 2525, have been pe,rformed. Actions, E0P 2525.

i j

E0P 2537 Page 2 Rev. 4

k_,) Instructions contingency Actions CAUTION SS/SCO must be notified immediately of any safety function criteria not satisfied.

3.2 Perform Safety Function Status 3. 2  !

Checks a. If safety function status

a. Complete OPS Form 2537-1 , check acceptance c'riteria at approximately 10 minute not satisfied, Then intervals until plant conditions i. Attempt event stabilize diagnosis

,-~s and 11. Go to appropriate

(,) b. Direct STA qualified indi- procedure vidual to review data b. I,f plant not responding and verify acceptance as expected or diagnosis ,

criteria satisfied of one event not appar-ent, Then go to Func-tional Recovery, E0P 2540 3.3 Stop two RCPs 3.3 Continue with this (one in each loop A & C preferred) procedure.

(C03) l 3.4 Close steam generator 3.4 Manually close valves blowdown and sample (local).

valves (C05).

E0P 2537 Page 3  !

Rev. 4

e .

Ok- / Instructions Contingency Actions CAUTION

1. The loss of all feedwater is a time sensitive event. The success path of last resort, when steam generator heat removal is not available, is once through RCS cooling via the PORV's (EOP 25400, Section 3.4). If it becomes apparent that feedwater will not be restored within minutes, then consideration should be given to use the remaining S/G inventory to cooldown.

2. When restoring steam generator level, add feedwater slowly to avoid

a. excess pressurizer level and pressure transient

b. excessive cooldown rate e

c. overfilling steam generators

d. Waterhammer in feed sparger O

b NOTES

1. Auxiliary Feed Auto Start is actuated if either steam generator level falls below 12% for 3 minutes and 25 seconds.

2. Steam driven auxiliary feed pump speed control can be from C21 or C05. The selector switches on C21 must be in normal for control to be at C05.

O E0P 2537 Page 4 Rev. 4

p)s

\s- 3. 5 Take action to restore feedwater 3.5 If unable to restore flow. Attempt to start one main main feedwater, Then feed pump by the following a., Check open main feed pump discharge isolation valve 2-FW-38A (B) (C05) (CR 0486-01)

b. Verify speed controller b. Dispatch an operaar potentiometer is turned to verify integrity fully counter clockwise (C05) of feedwater system

c. Position motor speed and changer switch to "fast c. Refer to Main Feed-lower" until low speed water, OP 2321 s+op (green light) is ,

observed (C05)

d. Depress reset pushbutton.(C05)

e. Pos'ition motor speed changer 0, to the "fast raise" position until high speed stop (red light) is observed (C05).

O E0P 2537 Page 5 Rev. 4

, .w ._ _ _ _ _ ________________ - __ ______________ _.

- e .

( ,)

}Istructions Contingency Actions

f. Adjust speed controller potentiometer to maintain main feed pump discharge pressure 50-150 psi greater than steam generator pressure (C05) 3.6 ff main feedwater is restored, 3.6 Close feed pump discharge Then go to step 3.12. isolation valves 2-FW-38A and 2-FW-388 (C05) 3.7 Verify suction flowpath to 3. 7 auxiliary feedwater pumps

,. by.

(m,) a. CST level greater tts1 16% (C05) a. If CST level is less than 16%, Then

i. Open 2-FIRE-34, fire main stop valve to auxiliary feed pumps (local) ii. Stop any auxiliary feed pumps (C05) and iii. Align the desired pump for operation on the fire water tank per OPS Form 2537-3 iv. Start the desired pump and reestablish feedwater flow to at least one steam

. generator by operating s_ Feed Regulating Valves 2-FW-43A and 2-FW-43B E0P 2537 Page 6 Rev. 4

l

b. Proper valve lineup. v. Replenish CST per Complete OPS Form 2537-2 Condensate Storage and Transfor, OP 2319B . t and

b. When CST level is restored to greater than 16%, Then {

re-establish auxiliary feedwater pump suction r from CST l

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I i

i 2

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r I

I I

I L

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O 1 4

I E0P 2537 Page 7 Rev. 4 [

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n,- Instructions Contingency Actions CAUTION If feedwatcr flow has been lost for greater than 5 minutes, limit feedwater flow to 600 gpm until level is greater than 45%.

3.8 Attempt to start "A" or "B" 3.8 Continue with this procedure auxiliary feed pump (s) and control feedwater flow rate by operating auxiliary feed regulating valves, ,

2-FW-43A and 2-FW-43B (C05) 4.9 M auxiliary feedwater is restored, 3.9 Continue with this procedure then go to step 3.12 3.10 Attempt to start steam d' riven 3.10 M unable to start auxiliary auxiliary feed pump by the feedwater, Then following

a. Opening combined steam a. Dispatch an operator stop inlet to steam driven to verify integrity auxiliary feed pump (C05) of auxiliary feed-

b. Increase turbine speed water system until feed pump discharge and pressure is 50-150 psi b. Refer to Auxiliary above steam generator Feedwater System, pressure (C05) OP 2322

c. Control Feedwater flow-rate by operating aux-iliary feed regulating valves, 2-FW-43A and 2-FW-438 (C05)

O E0P 2537 Page 8 Rev. 4

O

/ x

{ )

CAUTION The path of last resort when steam generator. heat removal is not available is once through RCS cooling via the PORV's (EOP 25400, Section 3.4). The use of this success path is time sensitive. If it beco:aes apparent that feedwater will not be restored within minutes, then consideration should be given to use the remaining S/G inventory to cooldown.

3.11 if feedwater has been restored, 3.11 if unable to restore feedwater Then perform steps in the remainder ' system to operation, Then of this procedure go to Functional Recovery, E0P 2540 (v

x_ -

E0P 2537 Page 9 Rev. 4

i i

Instructions Contingency Actions i

(

i CAUTIONS l

i

1. When restoring steam generator level, add feedwater slowly to avoid j

a. excessive pressurizer level and pressure transient t

b. excessive cooldown rate j

c. overfilling steam generators

d. Waterhammer in feed sparger l

2. If feedwater flow has been lost for greater than 5 minutes, limit feedwater flow to 600 gpm until level is greater than 45% I

[

i 3.12 Manually control main feedwater 3.12 Manually control auxiliary [

flow to return and maintain feedwater flow to return  !

steam generator level 70-80% (C05) and maintain steam generator l level 70-80% (C05) t 3.13 Verify proper steam generator 3.13  !

L heat removal by steam dump and a. Manually operate valves.

}

bypass or atmospheric dump g l valves functioning to return b. Verify steam generator f Tavg to 530-535'F (C04/5) Safeties are functioning  !

t to restore and maintain  ;

Tc at 540-550*F (C04) j

[

O -

L E0P 2537 Page 10 I Rev. 4 j

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~

f

( Instructions Contingency Actions 3.14 Verify RCS Inventory Control by 3.14

a. Pressurizer level trending a. Manually control charging to 35-4C% (CO3) and letdown (CO2) '

and and  ;

b. RCS Th greater than 30'F b. 'E pressurizer level subcooled (ICC display) control is lost, Then refer to Functional Recovery of RCS Inventory and Pressure, j 2540C e 3.15 Verify RCS pressure control by 3.15 Pressurizer pressure trending a. Manually control heaters to 2225-2300 psia (CO3) and spray (CO3) and

b. H pressurizer pressure control is lost, Then refer to Functional Recovery of RCS Inventory and Pressure, 25400 3.16 Ensure CST level greater than 3.16 Replenish per OP 23198, 70% (C05) Condensate Storage and Transfer i 3.17 As time permits, refer to 3.17 Not applicable, ,

Reactor Trip Recovery E0P 2526, and perform additional j steps as required, f I

d E0P 2537 Page 11 Rev. 4

- ' ' = --n-_

+w- n,- - -___..- _ _ _ - _ - - - - ,g-,._m ,- - g -

1

. . 1 l

l

. l l

1 l

4. FIGURES 4.1 Break Identification Chart j 4.2 RCS Pressure / Temperature Limits

{

P

- Final - l O

. f I

f i

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l I

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E0P 2537 Page 12 i Rev. 4

O FIGURE 4.1 BREAK IDENTIFICATION CHART INITIAL CONDITION: PRESSURIZER PRESSURE DECREASING EITHER

, YES S/G PRESSURE NO-

<.,800 psi?

CONTAINMENT -

YES NO PRESSURE *

• INCREASING?

CONTAINMENT NO YES PRESSURE INCREASING 7 O -

~

SJAE V~ SECONDARY SECONDARY OR BLOWDOWN BREAK BREAK N YES OUTSIDE RAD torilTORS INSIDE ALARitlNG?

CONTAINMENT CONTAINMENT PRIMARY PRIMRY t

BREAK BREAK INSIDE OUTSIDE -

CONTAINMINT CONTAINMENT '

1 J E0P'2532 E0P 2534 E0P 2536 STEAM GENERATOR  !

EXCESS LOSS OF PRIMARY TUBE RUPTURE STIAft

- DEMND COOLANT l UNIOUESYMPTOM5:

• HI RAD IN CONTAINMENT eHI RAD IN SECONDARY

• EITHER 5/G PRESSURE LOW PLA!iT

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OR AUX BUILDING O *NO RAD INCREASE - .tiORML CONTAINMENT CONDITIONS E0P 2537 Page 13 Rev. 4

, FIGURE 4.2 RCS PRESSURE / TEMPERATURE LIMITS

~

CN/

i 2500-i --

V r

,_ hot --

_ /CCE PTABLE -

J J AccG PTABLI.

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f 2000 ,

j I

J s, .

Is e ( -

I iv r

[ ~_

1% n ~

7 J f 7 cd 500-w u

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Il .0 1

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f I

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l y Q

w 1 w r

-/B g ,

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< i m . i (o",! .  ;;;

5h000-c 3 _ _

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/, ____._.

c - c / .__.

g ._

%g ,2 /_.__ _ __ __

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. . a. ..

yiy

[. .J...l_ _. _.-- -.-

_._ .. i i :_ L L ., - .,....... _.

500 -

f _ _

A ' Noi Ac.c.c.tT A BLE .

s 3. _ . -<

l 1

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't Tb~_' . ~.2.' _T[l'~2 f .

~, o st>,sopfN Df .L.J.1 ' ..- i y v _

.- + .,' ..

W g ot ', f ' . . -

4. . ._j. . -J<

q- .=._.. j p . __ _ _ _.. .. _ - ., --

,g _

g- ,,

i 0 -

500 600 300 400 i 200 RCS TEMPERATURE (F)

• This curve supercedes the 100F/HR cooldown curve any time the RCS has experienced l

I i an uncontrolled cooldown to below 500F. ,

t l

" This' curve supercedes the 30F subcooling curve if, at any time, the containment <

pressure has exceeded Spsig. , ,

E0P 2537 Page 14 Rev. 4

~ -

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O RCS PRESSURE / TEMPERATURE LIMIT DATA DATA SHEET 1

• PTS LIMIT 100'F/HR 200*F C00LDOWN

.30*F DEGRADED CTMT SUSC00 LED CURVE

$UBC00 LED MINIMUM MAXIMUM MAXIMUM RCS 5ATURATION MINIMUM PRESSURE PRES 5URE PRESSURE PRES 5URE TEMP PRES 5URE (psia) (psla) (psia) (psia)

('F) (psia) 1919 1919 upper Limit of 600 1543 2350 595 1487 1852 1852 1432 1787 1787

590 1378 1723 1723 565 1326 1662 1662 hs0 1276 1602 1602 595 1227 1543 1543 , .

570 1180 1487 1487

• 565 '

1133 1432 1432 560 1089 1378 1376

,- 555 1045 1326 1326 550 1003 1276 1276 545 963 1227 1227 540 924 1180 1180 O, 535 530 885 1133 1133 1089

e. 525 848 1089

~

813 1045 1045 i

520 778 1003 1003 l 515 744 963 963 510 712 924 924 505 681 885 885 500 650 848 848 495 621 813 813 490 593 773 773 485 566 744 744 480 712 7 12 475 540 681 647 470 515 0 650 657 .

465 490 2350 621 633 i 460 467 2286 593 607 455 434 2208 566 582 450 423 2133 540 561 445 402 2060 515 540 440 382 1989 490 522 435 362 - 1919 344 467 502 430 483 1852 425 326 434 467 1787 4fD 309 423 402 451 1723 y 415 292 1662 392 436 O 410 405 400 277 262 247 362 344 408 406 1602 1543 E0P 2537 Page 15 Rev. 4

- ^^

4

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O k RCS PRESSURE / TEMPERATURE LIMIT ONfA DATA SHEET 1 (Continued)

I PTS LIMIT 100*F/HR 200*F C00LDOWN 30'F DEGRADED CURVE 5U8C00 LED CTNT SUSC00 LEO

=

MINIMUM MAXIMUM MAXIMUM RCS SATURATION MINIMUM PRES 5URE PRE 55URE PRESSURE PRES 5URE TEMP PRESSURE (psia) (psia) -

(psia) (psia) l

(*F) '(psia) l

~ 392 1487 Upper Limit 395 233 326 of 2350 ,

309 378 1432 390 220 1378 366 385 208 292 1 077 353 1326 380 196 1276 184 P62 340 375 1227 329 1

370 173 2 47 233 319 1180 ,

) 365 163 1133 153 220 309 360 1019 144 208 299

• 355 1045 135 196 249 350 1003 126 184 281 345 963 118 173 275 340 924 110 163 265 335 885 103 153 256 330 O4 325 370 96 90 144 135 126 251 242 236 848 813 778 315 84 744

' 78 118 230 310 712 72 110 224 305 681 67 103 219 300 650 C 62 96 214 395 621 2230 58 90 210 I 290 593 2100 l 53 84 205 285 566 1970 i 49 78 _ 202 280 540 1850 l

{ 275 45 72 lit 1730 515 42 67 196

! 270 490 1620 39 62 192 265 190 467 1530 ,

260 35 58 434 1450 188 255 32 53 1370  !

184 423 250 30 49 1300 402 l 245 27 362 1230  ;

240 25 362 1170 (

! 235 23 344 1100 230 21 326 1040 19 980 i 225 309 220 17 292 930 [

215 16 277 880 l l 210 14 262 840 ,

205 13 247 800 200 12 l

i i

l E0P 2537 Page 16 Rev, 4

r .T./6. M - 3/w/f7 2-37-yc.~~

APPROVED F STATION SUPERINTENDENT EFFECTIVE DATE PORC MTG NO. ,

j ) LOSS OF ALL FEE 0 WATER SAFETY FUNCTION STATUS CHECK NOTES:

1. The purpose of this form is to ensure that all necessary information is reviewed when using E0P 2537, Loss of All Feedwater. The safety function status check verifies that the operator is using the correct procedure, j It also assures that the procedure is satisfying all relevant safety {

functions and maintaining adequate core cooling.

2. Safety function status is considered Jatisfied when all of the parameters of any one condition meet their criteria. .

3. With the integrated computer system functional, the safety function status may be determined from the SPOS displays. The SS/SCO shall ensure the correct recovery E0P number is selected at the SPOS CRT. The safety function status should be logged below approximately every 10 minutes until plant conditions stabilize.

Safety Fustion Status (YES/NO)

Reactivity Inventory _

Pressure _

Heat Remova) _

Containment Integrity _

Vital Auxiliaries _

Time  ;

4. If the integrated computer system is not functional, then completion of the rest of this form is necessary at approximately 10 minute intervals until the plant conditions stabilize.

5. Parameters marked with an asterisk require meter readings to be logged.

All other parameters are responded to by yes or no.

OPS Form 2537-1 Rev. 3 Page 1 of 6

LOSS OF ALL FEEDWATER

(' ' ' ' )' .

SAFETY FUNCTION STATUS CHECK CAUTION SS/SCO must be' notified immediately of any safety function criteria not satisfied.

TME*/ DATA ACCEPTANCE PARAMETER CRITERIA / / / / / / /

1. REACTIVITY CONTROL CONDITION 1 - CEAs Inserted i

a. Reactor Power a.

(C04) 1. < 5%

v and li, decreasing

b. CEA Position b. No more than one i CEA not l inserte.

1 4

i OPS Form 2537-1 Rev. 3 Page 2 of (

?M 14 T37

!o) PARAMETER ACCEPTANCE CRITERIA DATA

1. REACTIVITY CONTROL (cont)

_ Condition 2 - Boration

a. Reactor Power a.

(C04) 1. < 5%

and 11.

decreasing .

b. BAST b.

(CO2) 1. level A decreasing

• B (adding boron to RCS)

E

11. Shutdown __

margin established per CPS Form 2208' 13 O

OPS Form 2537-1 Rev. 3 Page 3 of 6

" * 2 4 GT

k_,) ACCEPT NCE PARAMETER CRITERIA DATA

2. RCS INVENTORY CONTROL

a. Pressurizer level a. > 20%*

(CO3)

b. All RCS subcooling b. > 30*Fa I (ICC Summary Display or ICC cabinets)

3. RCS PRESSURE CONTROL .

a. Pressurizer Pressure a. 1900-2350 psia" (CO3) and

b. Trending to

/l 2225-2300 psia C/

r OPS Form 2537-1 Rev. 3 Page 4 of 6

"* ?, ; ; 1537

e ACCEPTA'NCE PARAMETER CRITERIA DATA t

4. RCS HEAT REMOVAL k i

t I

Condition 1 - Feedwater Restored  ;

i  !

a. RCS Tavg a. 530-550*F" [

(C04)

b. Steam Generator b. -

level (feed flow) 1. 10-80%* A j (C05) (One and B

S/G may be out Trending A .

of spec.) to 70 B l

to 80% (

E *

[

11. Feed A t Flow B l

c. CST level c.  ;

} (C05) 1. > 70%* l ,

i or i 11. action i

i being l

] -

taken  !

I to i l

restore l i

level t i

d Condition 2 - Feedwater Being Restored i

a. RCS Tave (C04) a. < 550*F*

l j b. Efforts Underway b. Yes/No 2

to Restore Feedwater i O l k

OPS Form 2537-1  !

j Rev. 3 [

Page 5 of 6 [

i_ -

."I : ; 1337 .

ACCEPTANCE ,

PARAMETER CRITERIA DATA -

5. CONTAINMENT INTEGRITY

a. Containment t

, Pressure (C01) 2 psig Sump Level (C06) no abnormal

increase Normal Radiation (RC14) alarm setpoint Area Radiation (C101) alarm setpoint

b. Secondary Plant Radiation ,

SJAE (RC14) alarm e setpoint Blowdown (RC14) alarm setpoint Main Steam Line (RC05E) alarm _

setpoint

c. Stack Radiation Unit 1 Wide Range alarm setpoint Unit 2 Wide Range (C101) alarm setpoint ,

6. VITAL AUXILIARIES

a. Buses, 24C or a. Energized 240 (C08)

b. 125VDC Buses, b. Energized 201A or 201B (C08) c .- Instrument Air c. > 90 psig Pressure (C06)

O OPS Form 2537-1 Rev. 3 Page 6 of 6

,i , s .

y

f?//f l's9-i bI u3 (dan <.-

FORMAPPyVEDBYUNIT2 SUPERINTENDENT EFFECTIVE DATE PORC MTG. NO.

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AUXILIARY FEEDWATER FROM CST VALVE LINEUP Valve Valve Required Name Number Position Check CST Suction 2-CN-25 Open CST Suction 2-CN-26 Open Suct. Hdr. Isol. 2-CN-27A Open Suct. Hdr. Isol. 2-CN-278 Open "A" Pump Suction 2-CN-29A Open "B" Pump Suction 2-CN-298 Open Steam Pump Suction 2-CN-30 Open "A" Pump Discharge 2-FW-9A Open "B" Pump Discharge 2-FW-98* Cpen Steam Pump Discharge 2-FW-9C Open Pump Disch X-Comm 2-FW-44 Open Feed Reg. Valve 2-FW-43A Open Feed Reg. Valve 2-FW-438 Open Feed Reg. Isol. 2-FW-10A Open Feed Reg. Isol. 2-FW-11A Open Feed Reg. Isol. 2-FW-108 Open Feed Reg. Isol. 2-FW-118 Open O OP5 Form 2537-2 Rev. 1 Page 1 of 1