ML20205A394

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Rev 4 to Emergency Operating Procedure EOP 2536, Excess Steam Demand
ML20205A394
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: ... further results
References
EOP-2536, NUDOCS 8810250502
Download: ML20205A394 (34)
v • d • e


Text

o STATION PROCEDURE COVER SHEET A.

, IDENTIFICATION Numberi E0P 2536 Rev.

4,

)

Title:

EXCESS STEAM DEMAND Prepared By: STEVE BRINKMAN 8.

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

TITLE SIGNATRRE DATE

?/2a// F DEPAPTHENT HEAD ww ea~

idt0tLL -.

6,hu, a s

C.

SPECIFIC UNREVIEWE0 SAFETY QUESTION EVALUATION REQUIRED:

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

YES ( )

NO {y (If yes, perform writtea USQ determination and Safety

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

ENVIRONMENTAL REVIEW REQUIRE 0 (Adverse environmental impact)

YES [ ]

NO ()G

(

0.

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 (<N (If yes, perform written Safety Evaluation and contact Manager, Safety Analysis Branch to determine need for Integrated Safety Evaluation.)

E.

INTEGRATED SAFETY EVALUATION REQUIRED YES ( j NC @

F.

PROCEDURE REQUIRES PORC/50RC REVIEW (In addition to review, items with a YES response must be documented in the PORC/SORC meeting minutes.)

YES [

NO ( )

G.

PORC/50RC APPROVAL PORC/50RC Meeting Number 3 -)Y-l h I H.

APPROVAL AND IMPLEMENTATION Ine attached procedure is hereby approved, and effectivo on the date below:

G. /[',% %

f[ jj' Stati Service / Unit' Super ntendent Effective Date O

SF301/9/s/SES/87-12/lofl 0810250502 001007 DR ADOCK 050 13

- - _. v - ~.. - - _ _ -. -_.-._=

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UNIT 2 i

j EXCESS ST6AM DEMAND i

I.

l Pace No.

Eff. Rev.

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r E0P 2536 Page 1 Rev. 4

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N EXCESS STEAM OEMAND Q) 1.

PURPOSE To provide the subsequent operator actions which must be accomplished in the event of an excess steam demand event.

These actions are taken after completion of the Standard Post Trip Actions and an excess steam demand has been diagnosed.

The actions in this procedure are necessary to ensure that the plant results in a stable safe condition.

2.

ENTRY CON 0!TIONS a.

The Standard Post Trip Actions have been accomplished and b.

Plant conditions indicate that an excess steam demand event has occurred by one or more of the following O

i.

Decreasing pressure in one or both steam generators (C05) ii.

Possible increase in containment pressure and temperature (C01) 111. MSI actuated on low steam generator pressure (C01X) iv.

CIAS actuated on high containment pressure (C01X) v.

High noise level (local) 3.

OPERATOR ACTIONS Instructions Contingency Actions 3.1 Verify Standard Post Trip Actions, 3.1 Perform Standard Post Trip E0P 2525. have been performed Actions, E0P 2525.

O E0P 2536 Page 2 Rev. 4

7

?

e Te :.., 'ons Contingency Actions

(

i

(~

CAUTION i

i SS/SCO must be notified immediately of any safety function criteria not satisfied.

I i

3.2 Porform Safety Function Status 3.2 If safety function status

[

Checks check criteria are not l

a.

Complete OPS Form 2536-1 satisfied, Then at approximately 10 minute a.

Diagnose problem and intervals until plant go to appropriate E0P conditions stabilize i,

If, any break.is f

and suspected. Then refer to Break b.

Direct STA qualified Identification individual to review data Chart, Figure 4.1 I

and verify acceptance to assist in criteria are satisfied diagnosis and j

11.

Go to appropriate break E0P l

or b.

If diagnosis of one event is not apparent, Then go to Functional l

Recovery, E0P 2540 L

l i

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I E0P 2536 Page 3 l

l Rev. 4 l

l f

r o

t l

l Instructions Contingency Actions n

t CAUTION

\\

Pressurizer level may not provide an accurate indication of total RCS f

inventory due to voids.

Voids may exist, especially if RCPs are not l

running.

However, pressurizer level in conjunction with a subcooled RCS i

is an indication that the core is covered.

The reactor vessel level monitor gives an indication of void size above the core.

l 3.3 Confirm the diagnosis of an excess 3.3 steam demand event, a.

E a loss of prima,ry a.

Refer to Break Identification

  • coolant is diagnosed, Chart, Figure 4.1.

Then go to Loss of Primary Coolant.

E0P 2532 and of b.

Direct chemistry to sample steam b.

M a steam generator tube generators for activity.

rupture is indicated.

Then go.to Steam Generator Tube Rupture, E0P 2534 O

E0P 2536 Page 4 Rev 4

Instructions Contingency Actions

~

(~)

3.4 g pressurizer pressure 3.4 a.

Manually initiate SIAS, decreases to 1600 psia (CO3)

CIAS and EBFAS (C01)

I or containment pressure ad increases to 5 psig (C01),

b.

Take steps to ensure-Then acceptable safety a.

Verify SIAS, CIAS and injection flow EBFAS (C01X) 1.

Ensure electrical and power to valves and b.

Verify Safety Injection pumps (C01/ local)

Flow rate per Figure 4.3 11.

Ensure correct i

safety injection 1

system valve lineup (Col) 111. Start idle HPSI, LPSI and charging i

pumps (C01/2)

O~

3.5 g pressurizer pressure decreases 3.5 continue with this i

to 1600 psia (CO3), Then do the procedure l

following.

l a.

Stop one RCP in each loop-l (A and C preferred) (CO3) b.

Shut the spray valve at the discharge of the idled RCP in Loop 1 and leave in manual (CO3),

(

l l

i I

O E0P 2536 Page 5 Rev. 4

7 r

e Instructions Contingency Actions U

CAUTION:

The 30'F Thot subcooling RCP trip c..'iteria is most limiting only Aring the initial phase of the event.

As the RCS is cooled and depressurized, RCP operating parameters (e.g. NPSH requi'ements) become increasingly restrictive.

3. 6 M, T subcooling decreaser 3.6 Continue with this h

below 30'F, Then stop all procedure.

RCPs (C03)

3. 7 H containment pressure 3.7 increases to 27 psig (C01),

Then a.

Verify CSAS (C01X) a.

Manually initiate CSAS and (C01) l b.

Verify two containment b.

Take steps to ensure spray header flows greater adequate containment than 1350 gpm each (C01) pressure control.

g 1.

Refer to c.

Verify containment air coolers Containment Spray operating in the emergency System Proce< jure mode OP 2309 11.

Refer to Containment Air Recirculation and Cooling Procedure OP 2313A O

E0P 2536 Page 6 Rev. 4 1

(

J.

Instructions Contingency Actions

'O

~

NOTE Worst case licensing analysis (assumes most reactive CEA stuck out) predicts a momentary return to power during initiil blowdown phase.

3.8 HT decreases to 500'F, Then

3. 8 Oo the following e

verify concentrated boric acid a.

Commence boration using being injected into'the RCS at the boric acid pumps as greater than 40 gpm by the follows CVCS (CO2) 1.

Open boric acid pump discharge to charging pump j

suction, 2-CH-514

[

(CO2) l

11. Start both boric acid pumps (CO2)

I lii.Close boric acid pump

[

recirculation valves, 2 CH-510 and 2-CH-511 (CO2)

[

b.

M boric acid pumps fail to start, Then f

1.

Open boric acid i

l gravity feed valves 2 CH-508 and

[

2-CH 509 (CO2)

11. Close volume control tank outlet valve.

[

2-CH-501 (CO2) c.

Start all available l

charging pumps (CO2) l t

i O

E0P 2536 Page 7 Rev. 4

r e

Instructions Contingency Actions i' v

CAUTION Steam generators are vital for RCS heat removal.

One steam generator must be used for this purpose even if multiple breaks are detected.

3.9 Il steam generator pressure 3.9 Do the following decreases to 850 psia (C05), Then.

do the following a.

Verify atmospheric dump a.

E atmospheric dump valves closed (C05) valve indicates open b.

Verify steam dump and bypass (005),Then valves closed (C05)

.i.

~ ke manual. control a

c.

Verify steam seal pressure (C05) 2-6 psig (C05)

E d.

Isolate blowdown (C05)

11. Manually isolate (local)

'u '

e.

Dispatch operator outside b.

H steam dump and bypass to look for steam dis-valves indicate open, charge (local)

Then i.

Manually close (C05)

E

11. Manually isolate (local) c.

Lf steam seal pressure not 2-6 psig, Then close steam seal feed valve, 2-MS-182B (C07) 3.10 H the event was terminated as 3.10 Continue with this a result of Step 3.9, Then prucedure go to Reactor Trip Recovery,

(]

E0P 2526 V

E0P 2536 Page 8 Rev, 4

Instructions Contingency Actions 4

m 3.11 E steam generator,pressurs 3.11 Continue with this decreases below 800 psia, procedure Then close MSIVs (C05) j NOTE

~ The affected steam generator will have lowest steam generator pressure and T '

c i

3.12 If the event was terminated 3.12 Determine which steam I

i by closing the MSIVs, Then generator has excess I

go to step 3.16 steam demand.

i 3.13 y either steam generator 3.13 j

pressure decreases to 500 psia, l

Then verify MSI by the following

\\

a.

MSIVs closed (C05) a.

Manually close valves b.

MSIV bypass valves closed (C05)

-(C05) and b.

Manually trip pumps 1

c.

Main feedwater air (C05) assisted check valves j

closed (C05) i d.

Both Main feedwater regulating l

valves closed (CO3) i e.

Both main feedwater l

pumps trip (C05) f.

Main steam Ive' point drain valves clo ed (C07) i g.

Both main fee.. water regulating valves bypass valves closed j

(C05)

!O E0P 2536 Page 9 i

Rev. 4

7 9

Instructions Contingency Actions

,3

( ')

3.14 M MSI has been initiated, Tt.en 3.14 Manually close valves complete isolation of the (local) affected steam generator by the following a.

Pull to lock on auto auxiliary feedwater override switch (C05) b.

Close associated auxiliary feedwater regulating valve (205) c.

Close associated auxiliary feedwater air assisted check valve (C05) d.

Close steam supply' valves to steam driven auxiliary feedwater pump (C05)

OG O

E0P 2536 Page 10 Rev. 4

Instructions Contingency Actions

'v /.

NOTE If the break is unisolable, RCS temperatures and steam generator pressure will not stabilize until the affected steam generator is dry.

The amount of time required for this is dependent on the break size.

3.15 Verify the correct steam 3.15 generator has been isolated a.

If the wrong steam by stabilization of RCS generator has been temperatures and steam isolated, Then unisolate generator pressure that generator and_

b.

If both steam generators are suspected, Then only isolate the, steam generator with the lowest steam generator pressure and corresponding T e 3.16 if pressurizer pressure is greater 3.16 Continue with this than 1600 psia and stable and procedure containment pressure is less than i

5 psig, Then reset ESAS actuation modules (ESAS)

O E0P 2536 Page 11 Rev. 4

Instructions Contingency Actions CAUTION s-Containment spray moisture may affect proper operation of non qualified equipment and instrumentation inside containment.

When termination criterion is met, containment spray should be promptly termin' ted.

a 3.17 When containment pressure is less 3.17 Continue with this than 10 psig (C01), Then do the procedure following L.

Reset containment spray actuation modules (ESAS) b.

Stop the containment spray pumps (C01) c.

Realign for automatic operation (C01) 3.18 If Pressurizer pressure is 3.18 Continue with this greater than 360 psia and stable, procedure Then stop LPSI pumps (C01).

3.19 When all the following 3'19 If the termination condition

  • conditions exist, Then, one do not exist, Then HPSI pumps facility at a time, HPSI pumps must continue to operate should be throttled or stopped a.

Pressurizer level greater than 35% and constant or increasing (C03) b.

Pressure /Temperatue limits of Figure 4.2 satisfied for T

in the operating loop h

c.

At least one steam generator is removing heat

'N d.

Reactor vessel level above top of Hot Leg (>43%) (ICC Summary Display)

E0P 2536 Page 12 Rev. 4

(-

Instructions Contingency Actions _

~

(

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3.20 Control charging pumps and 3.20 Continue with this letdown flow to restore and procedure maintain a.

Pressurizer level 20-80% (C03) and b.

Pressure / Temperature limits of Figure 4.2 are satisfied for the operating loop T h CAUTION If the RCS has experienced an uncontrolled cooldown which causes RCS temperature to go below 500 F, there is a potential for Pressurized Thermal Shock (PTS) of the reactor vessel.

Pressure / Temperature limits of Figure 4.2 must be maintained by a.

Careful addition of feedwater to steam generators b.

Control of RCS repressurization from HPSI and CVCS p'

'v c.

Control of heat removal by steam dump and bypass or atmospheric dump valves on operating steam generator (s) 3.21 Operate atmospheric dump valves 3.21 Manually operate valves on the operating steam generator (C05/ local) to stabilize RCS parameters (pressure, level and temperatures)

(C05) 3.22 Manually control auxiliary 3.22 If main or auxiliary feedwater to the operating steam feedwater is not available, generator (s) to slowly return and Then go to Functional mairitain steam generator level Recovery, E0P 2540.

70-80% (C05)

(U l

E0P 2536 Page 13 Rev 4 l

e Instructions Contingency Actions i

i

\\J 3.23 H RCPs were stopped, Then 3.23 verify natural circulation flow in the operating loop by the following a.

Pressurizer level greater a.

Verify adequate core than 20% and constant or cooling by incore increasing (C03) thermocouple temperature b.

Heat removal from operating less than 575'F and loop steam generator constant or decreasing (ICC Su. mary Display) c.

Pressure / Temperature 1tmits of or Figure 4.2 satisfied for T b.

M adequate core cooling h

in the operating loop (C03, C101)

.not verified, Then" go to d.

Loop delta T (T -T)

Functional Recovery, h

c between 10 and 45'F (C03, C101)

E0P 2540 e.

T constant or decreasing (C03) c f.

T constant or decreasing (C03, h

\\_)

C101)

Ov I

E0P 2536 Page 14 Rev. 4

Instructions Contingency Actions 3.24 If RCPs were stopped.

Then 3.24 Continue with this RCPs can be restarted provided procedure all of the following conditions can be met:

a.

Pressurizer level greater than 35% and constant or increasing (C03) b.

Pressure / Temperature limits of Figure 4.2 satisfied for T I"

h the operating loop c.

Heat removal from at least one steam generator (C05) d.

RCP start prerequisites are met per "Reactor Coolant Pump Operation," OP 2301C O

E0P 2536 Page 15 Rev. 4

O Instructions Continctncy Actions

~

A CAUTION Pressurizer level and pressure can be expected to decrease upon starting RCPs due to loop shrinkage and/or void collapse.

The level decrease may be large enough to drain the pressurizer, RCP operation may continue provided HPSI and and charging pumps are operating and NPSH requirements are met, l

i 3.25 If conditions exist for RCP 3.25 If RCP operation is not operation, Then, possible or RCPs did not a.

Start HPSI and charging pumps start, Then verify natural (or verify operating) to make up circulation per Step 3.23 for RCS contraction b.

Start one RCP in each loop, operatint) loop first.

(RCP D, 0 preferred) (CO3) c.

Monitor RCS pressure and O

corresponding Tc for adequate pump NPSH (CO3) d.

Operate HPSI and charging pumps l

to restore pressurizer level 35-45% (C03) 3 3.26 Monitor for RCS voiding.

3.26 Continue with this j

Indications of voiding are procedure I

a.

Pressurizer level increases l

greater than expected while l

using auxiliary spray (C03)

E i

b.

Pressurizer level increases l

slower than expected for existing HPSI and Charging i

flow (CO3) l0 1

l E0P 2536 Page 16 Rev. 4 i

i I

7 --

Instructions Contingency Actions O

~

c.

Unheated thermocouple in upper head indicates saturated condition (ICC Summary Display) d.

Reactor Vessel Level less than' 100% (ICC Summary Display) 3.27 Verify RCS voiding not inhibiting 3.27 E adequate core cooling adequate' core cooling by not verified, Then go to a.

Pressure / Temperature limits of Functional Recovery, Figure 4.2 satisfied for incore E0P 2540 thermocouple temperature (INTAMX or TC Map Display:-

and b.

At least one steam generator is removing heat O

3.28 E necessary to cooldown to 3.2f Continue with this make repairs, Then continue procedure cooldown to cold shutdown using Plant Cooldown,'0P 2207, or Plant Cooldown using Natural Circulation, AOP 2553 i

l 3.29 As time permits, Refer to 3.29 Not applicable l

Reactor Trip Recovery, E0P 2526, and carry out additional r

steps as required r

4 4.

FIGURES f

4.1 Figure 4.1 - Break Identification Chart f

L 4.2 Figure 4.2 - RCS Pressure / Temperature Limits f

4.3 Figure 4.3 - Safety Injection Delivery Flow iO j

- Final -

t I

E0P 2536 Page 17 Rev. 4 1

i i

FIGURE 4.1 BREAK IDENTIFICATION CHART INITIAL CONDITION:

PRESSURIZER PRESSURE DECREASING EITHER YES S/G PRESSURE NO

< 800 psi?

CONTAINMENT YES NO PRESSURE INCREASING 7 CONTAINMENT YES gg PRESSURE INCREASING?

sJAE, SECONDARY SECONDARY ftAIN STEA.,

SREAK BREAK LINE, OR BLOW-NO

]NSIDE OUTSIDE DOWN RAD MONITORS YES CONTAINMINT CONTAINMENT ALARMING?

PRIFARY PRIPARY BREAK BREAX INSIDE OUTSIDE CONTAINMENT CONTAINMENT I

I E0P 2536 E0P'2532 E0P 2534 EXCESS LOSS OF STEAM GENERATOR STEA!!

PRlPARY TUSE RUPTURE DEFAND C001. ANT UNIOUE SYF.770MS:

EITHER $/G PRESSURE LOW e HI RAD IN CONTAINMENT

.H1 RAD IN SECONDARY OR AUX BUILDING PLANT

.Ido RAD INCREASE

. NCR?'At CONTAINMENT CONDli10NS i

O E0P 2536 Page 18 Rev,4

r FIGURE 4.2 RCS PRESSURE / TEMPERATURE LIMITS 2500 t

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-. -. j.q- -

q 200 300 400 500 600 RCS TEMPERATURE (F)

  • This curve supercedes the 100F/HR cooldown curve any time the RCS has experienced an uncontrolled cooldown to below 500F.
    • This curve supercedes the 30F subcooling curve if, at any time, the containment pressure has exceeded 5 psig.

E0P 2536 Page 19 Rev. 4

c.

RCS PRESSURE / TEMPERATURE LIMIT DATA l

PTS LIMIT 100*F/HR 30'F DEGRADED 200*F COOLDOWN SU8C00 LED CTMT SUBC00 LED CtlRVE RCS SATURATION MINIMUM MINIMUM MXIMUM MAXIMUM TEMP PRESSURE PRESSURE PRESSURE PRESSURE PRESSURE

('F)

(psia)

(psia)

(psia)

(psia)

(psia) 600 1543 1919 1919 Upper Limit of 595 1487 1852 1852 2350 590 1432 1787 1787 585 1378 1723 1723 580 1326 1662 1662 575 1276 1602 1602 570 1227 1543 1543

~

565 1180 1487 1487 F60 1133 1432 1432 555 1089 1378 1376 550 1045 1326 1326 545 1003 1276 1276 540 963 1227 1227 535 924 1180 1180 530 885 1133 1133 525 848 1089 1089 520 813 1045 1045 515 778 1003 1001 0

510 744 963 963 505 71?

924 924 500 681 885 885 495 650 848 848 490 621 813 513 485 593 773 773

'~

480 566 744 744 475 540 712 712 470 515 681 687 465 490 650 657 P

460 467 621 633 2350 l

455 434 593 607 2286 450 423 566 582 2208 445 402 540 561 2133 440 382 515 540 206's 435 362 490 522 19f9 430 344 467 502 19'.9 425 326 434 483 185?

420 309 423 467 1787 41b 292 402 451 1723 V

410 277 392 436 1662 405 262 362 408 1602 400 247 344 406 1543 O

E0P 2536 Page 20 Rev. 4

~ ~ * '

e RCS PRESSURE / TEMPERATURE LIMIT DATA (Cont'd) i ()

PTS LIMIT 100'F/HR 30'F DEGRADED 200'F C00LDowH SUBC00 LED CTMT SUBC00 LED CURVE RCS SATURATION MINIMUM MINIMUM KAXIMUM MAXIMUM TEMP PRESSURE PRESSURE PRESSURE PRESSURE PRESSURE

('F)

(psia)

(psia)

(psia)

(psia)

(psia) 395 233 326 392 1487 '

Upper Limit 390 220 309 378 1432 of 2350 385

  • 208 292 366 1378 380 196 277 353 1326 375 184 262

,40 1276 370 173 247 329 1227 365 163 233 319 1180 360 153 220 309 1133 355 144 208 299 1089 350 135 196 289 1045 345 126 1 84 281 1003 340 118 173 275 963*

335 110 163 265 924 330 103 153 256 885 325 96 144 251 848 320 90 135 242 813 315 84 126 236 778 O.

310 78 110 230 744 305 72 110 224 712 300 67 103 219 681 395 62 96 214 653 290 58 90 210 621 2230 285 53 B4 205 593 2100 280 49 78 202 566 1970 275 45 72 198~

540 1850 270 42 67 196 515 1730 265 39 62 192 490 1620 260 35 58 190 467 1530 255 32 53 188 434 1450 250 30 49 184 423 1370 245 27 402 1300 240 25 382 1230 235 23 362 1170 230 21 344 1100 225 19 326 1040 220 17 309 980 215 16 292 930 210 14 277 880 205 13 262 840 200 12 247 800 O

E0P 2536 Page 21 Rev, 4

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> ~2 7 ~ 4'c FORMAPPROVyLYSTATIOWSUPERINTENDENT EFFECTIVE DATE PORC MTG NO.

p()

EXCESS STEAM DEMAND-SAFETY FUNCTION STATUS CHECK NOTES:

1.

The purpc,se of this form is to ensure that all necessary information is reviewed when using E0P 2536, Excess Steam Demand.

The safety function status check verifies that the operator is using the correct procedure.

It also assures that the procedure is satisfying all relevant safety functions and maintaining adequate core cooling.

2.

Safety function status is considered satisfied 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 SPDS CRT.

The safety function status should be logged below approximately every 10 minutes

[

until plant conditions stabilize.

Safety Function Status (YES/NO)

Reactivity Inventory 3

Pressure Heat Removal 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 2536-1 Rev. 3 Page 1 of 11

EXCESS STEAM DEMAND SAFETY FUNCTION STATUS CHECK

.\\

V CAUTION SS/SCO must be notified immediately of any safety function criteria not satisf.ied.

TIME */ DATA ACCEPTANCE PARAMETER CRITERIA

,/

/

/

/

/

/

/

REACTIVITY CONTROL i

CONDITION 1 - CEAS, Inserted a.

Reactor Power a.

(C04)

1. < 5%

and

11. decreasing b.

CEA Position b.

No more than one CCA not

~

(J inserted c.

T c.

> 500'F c

Condition 2 - Boration a.

Reactor Power a.

(C04) 1.

< 5%

and

11. decreasing b.

BAST (C02) b.

i. level A

decreasing B

(adding boron to RCS) c.

SIS Flow (C01) c.

Acceptable per Figure 1 Alternative to Shutdown margin g

b and c aoove established per Form 2208-13 OPS Form 2536-1 Rev. 3 Page 2 of 11 LW'

~

O s

V ACCEPTANCE PARAMETER CRITERIA DATA' 2.

RCS INVENTORY CONTROL 4

Condition 1 a.

Pressurizer level a.

> 20%*

(CO3) b.

Pressurizer pressure b.

Acc.eptable per Figure 2 and operating loop Th l

c.

Reactor Vessel c.

above top of j

level (ICC Level hot leg display or ICC

(> 43%)*

cabinets)

O

~

t 1'

Condition 2 j

i a.

SIS Flow a.

Acceptable l

(C01) per Figure 1 J

b.

Charging Flow b.

All available I

(CO2) pumps operating

}

1 1

1 c.

RWST levei c.

> 9.5%*

l l

(C01) l i

d.

Reactor Vessel d.

above fuel i

level (ICC Level alignment plate

(> 0%)

cabinets) i I

OPS Form 2536-1 Rev. 3 Page 3 of 11 i

'P

.jjj t

7 ACCEPTANCE PARAMETER CRITERIA DATA 3.

RCS PRESSURE CONTROL Condition 1 a.

Pressurizer Pressure a. Acceptable and loop T and per Figure 2 h

T.(CO3) e Condition 2 a.

SIS Flow a.

Acceptable (001) per Figure 1 b.

Charging Flow b.

All (CO2) available pumps operating O

OPS Form 2536-1 Rev. 3 Page 4 of 11 MA9 01 C/

k, )

ACCEPTA'NCE PARAMETER CRITERIA DATA 4.

RCS HEAT REMOVAL Condition 1 a.

RCS Tavg a.

<570*F*

(C04) b.

Steam Generator b.

level (feed

i. 10-80%*

A flow) (C05) and B

(One S/G may Trending A

be isolated and to 70-80%

B out of spec) of ii. Feed Flow A

B c.

CST level (C05) c.

[D,

i. > 70%*

v E

11. Action being taken to restore level Condition 2 a.

Incore a.

Thermocouple i.

< 600*F*

(INTAMX or ICC and cabinets)

11. Constant or decreasing b.

SIS Flow b.

Acceptable per (C01)

Figure 1 c.

Charging Flow c.

All available n(y (CO2) pumps operating OPS Form 2536-1 Rev. 3 Page 5 of 11 t

MM " '.J

.w ACCEPTANCE PARAMETER CRITERIA DATA

)

5.

CONTAINMENT INTEGRITY Condition 1 - Break Outside Containment a.

Containment a.

< 2 psig*

pressure (C01) b.

Containment b.

less than area rad alarm setpoint monitors (C101) c.

SJAE, Blowdown c.

less than and Main Steam alarm setpoint Line Rad Monitors (RC14,RC05E)

Condition 2 - Break Inside Containment (n) a.

Containment a.

pressure (C01) 1.

< 5 psig*

E ii. H > 5 psic, Then SIAS, CIAS and EBFAS and

11. H > 27 psig Then CSAS b.

Containment

b. less than alarm area rad setpoint monitors (C101) c.

SJAE, Blowdown

c. less than alarm and Main Steam setpoint

(,)

Line Rad Monitors v

(RC14, RC05E)

OPS Form 2536-1 Rev 3

Page 6 of 11 f.iA3

,.7

4^

O ACCEPTdNCE PARAMETER CRITERIA DATA 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 pressurc (C06)

O O

OPS Form 2536-1 Rev. 3 Page 7 of 11

.,ti r.

;7

1300 1

\\

=

2 1

1200W (,

=

=

p

=

=

=.-

=

7

=

7 1100 : s'-

=

=

=

=

=

=

=

=

=

g

=-

=

=

=

=

=

=

. 1_

J

=

=

=

1000< -,

~

=

2 K

T m

7 t

=

a,

=

300 <

,l

.--, =

_=

g e0c -

~

=

=

=

=

= -

[

=

=

=

=

=

=

=

,.~

~

.4.,c..i.,

4,c,

~

U 700

=-

.ii,

. 4, p

m

=

=

=

v.

ACCEPTA3LE RIGION

=

W 600

- =

=

=

=

=

=

=

=

=

E

=

=

=

$Qo. 7

=

=

=

=

v.

.=

=

=

=

=

=

=

=

gc

_=.

=

.~.

=

400,

=.-

=

=

=

=

=

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=

_=

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=

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=

=

U 3=

=

=

.

=

=.,.3 3,

0, 3=

=

=

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300,

=

=

~

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=

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. =

=

3, -

=

=

=

- =

=

=

=

=

ggg.

-, - ~.

3, 3,,,A

.~.

- =

=

=

=

=

100 L t.TN ACCIPTABLE REGION

. 5-g- -) _

.~

_,.J

=. =..=,.,

=

J

, ~

.J

_i _

..1 g

0 e00 1600 2400 3200 4000 TOTAL OF FOUR HPSI AND LPSI HEADER FLOWS (CPM)

EO T E 1:

This curve is based on one facility operating and assumes at least one charging pump is operating.

NOTE 2:

,I_.f,, c o n t a i n m e n t pressure has exceeded 5 psig at any time during an event, then do not use this curve.

Its accuracy is in doubt.

When determining safety function status, consider the safety function satisfied if all other safety function parameters meet their criteria.

NOTE 3:

The curve applies to the pre-SRAS condition only.

l l

MINIMUM REOUIRED SAFETY INJECTION F ', 0 W CURVE i

FIGURE 1 i

OPS Form 2536-1 Rev. 3 Page 8 of 11 i rL

,g

../

e 2500 l

(

i, NOT

- ACCE PTABLE -

6 1

I ACCG PTA ALE

. j 2000

/

f 1It

}

If 4

ju

,r 2

r 3

fg o

2 g

E.1500 1

1Q i

!/ a' f

I

.1 I

J it.o

$y w

f I

g I'

e jf

/

l

/

l l4

/-

n i

/

)

O i

/

/

~

h1000-

D

/

/_

=. -

g

[

__y a

s

}

h f

~~"

.g

~

a. fj. :.. _

d -

J <

500 -

s* /

I NOT AC.C.r.rTA BLE l-

  1. AM l 'Td. ii~:._-b-hi 8",se wdl Z

.ja.J.J r

0 ut'Ye I.

I f

f...

SOY '

I '

d

...j.,...l 3 j.4

.f r

_1..

Qq y

..L g

200 300 400 500 600 RCS TEMPERATURE (F)

  • This curve supercedes the 100F/HR cooldown curve any time the RCS has experienced an uncontrolled cooldown to below 500F.
    • This curve supercedes the 30F subcooling curve if, at any tire, the containment pressure has exceeded Gpsig.

OM Fom 2W 1 FIGURE. 2 RCS PRESSURE / TEMPERATURE 1.ll11TS Rev. 3 Page 9 of 11

\\ -

RCS PRESSURE / TEMPERATURE LIMIT DATA PTS LIMIT 100'F/HR 30*F DEGRADED 200*F C00LDOWN SU8C00 LED CTMT SU8C00 LED CURVE RCS SATURATION MINIMUM MINIMUM MAXIMUM MAXIMUM TEMP PRESSURE PRESSURE PRESSURE PRESSURE PRESSURE

(*F)

(psia)

(psia)

(psia)

(psia)

(psia) 600 1543 1919 1919 Upper Limit of 595 1487 1852 1852 2350 590 3'12 1787 1787 585

'378 1723

.1723 580 1326 1662 1662 595 1276 1602 1602 570 1227 1543 1543 565 1180 1487 1487 560 1133 1432 1432 555 1089 1378 1376 550 1045 1326 1326 545 1003 1276 1276 540 963 1227 1227 535 924 1180 1180

'N 530 885 1133 1133 525 848 1089 1089

\\

f20 813 1045 1045 515 778 1003 1003 510 744 963 963 505 712 924 924 56D 681 885 885 495 650 848 848 490 621 813 813 485 593 773 773 480 566 744 744 475 540 712 712 470 515 681 687 U

465 490 650 657 460 467 621 633 2350 t

455 434 593 607 2286 450 423 566 582 2208 445 402 540 561 2133

{

440 382 515 540 2060 l

435 362 490 522 1989 430 344 467 502 1919 425 326 434 483 1852 420 309 423 467 1787 l

415 292 402 451 1723 V

l 410 277 392 436 1662 405 262 362 408 1602 O.

400 247 344 406 1543 OPS Form 2536 1 Rev. 3 Page 10 of 11 M 'i,, ?....

(

RCS PRESSURE / TEMPERATURE LIMIT DATA (Cont'd)

PTS LIMIT 100'F/HR 30'F DEGRADED 200*F COOLDOWN SUSC00 LED CTMT SUBC00 LED CURVE RCS SATURATION MINIMUM MINIMUM MAXIMUM MAXIMUM TEMP PRESSURE PRES $URE PRESSURE PRESSURE PRESSURE

(*F)

(psia)

(pJia)

(psta)

(psia)

(psia) 395 233 326 392 1487 Upper 1.imit 390 220 309 378 1432 of 2350 385 208 292 366 1378 380 196 277 353 1326 375 184 262 340 1276 370 173 247 329 1227 365 163 233 319 1180 360 153 220 309 1133 355 144 208 299 1089 350 135 196 289 1045r 345 126 184 281 1003 340 118 173 275 963 335 110 163 265 924 330 103 153 256 885 325 96 144 251 848 320 90 135 242 813 315 84 126 136 778 310 78 118 230 744 305 72 110 224 712 300 67 103 219 681 395 62 96 214 650 0

290 58 90 210 621 2230 285 53 84 205 593 2100 280 49 78 202 566 1970 275 45 72 198 540 1850 270 42 67 196 515 1730 265 39 62 192 490 1620 260 35 58 190 467 1530 255 32 53 188 434 1450 250 30 49 184 4 23 1370 245 27 402 1300 240 25 382 1230 H5~

23 362 1170 230 21 344 1100 225 19 326 1040 220 17 309 980 215 16 292 930 210 14 277 880 205 13 262 840 200 12 247 800 O

OPS Form 2536 1 Rev. 3 Page 11 of 11

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