ML20205A383
Text
{{#Wiki_filter:* f e . STATION PROCEDURE COVER SHEET 4 A. IDENTIFICATION Number: E0P 2534 Rev. 5
Title:
STEAM GENERATOR TUBE RUPTURE Prepared By: STEVE BRINKMAN B. REVIEW I have reviewed the above procedure and have found it to be satisfactory. TITLE SIGNAT@E DATE DEPARTMENT HEAD j /I
.0%ebru Euktes v y -
~)li v/r'f t i C. SPECIFIC UNREVIEWED SAFETY QUESTION EVALUATION REQUIRED:
Modifies intent of procedure and changes operation of systems as described in design documents. , YES [ ] NO-(K (If yes, perform written 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 l 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 J may indirectly affect safety system response. YES [ ] NO [7] (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 ( ) NO [g ^ F. PROCEDURE REQUIRES PORC/SORC REVIEW (In addition to review, items with a YES response must be documented in the PORC/50RC meeting minutes.) YES [ NO ( ) G. PORC/SORC APPROVAL PORC/50RC Meeting Number 2 N /31 H. APPROVAL AND IMPLEMENTATION The attached procedure is hereby approved, and effective on the date below:
/ w. 3 /b'% u'%
/ Service / Unit Superintendent 3! N Effective Date Stat O SF301/9/s/SES/87-12/lof1 8810250499 881007
- _ y* *** **%P
- i l
. l l
l UNIT 2 j STEAM GENERATOR TUBE RUPTURE Page No. Eff. Rev. [ 6 1-24 5 l f I l l t i t l l l l 1 E0P 2534 Page 1 Rev. 5
O, STEAM GENERATOR TUBE RUPTURE
- 1. PURPOSE ,
To pr' ovide the subsequent operator actions which must be accomplished in the event of a steam generator tube rupture. These actions are taken after completion of the Standard Post Trip Actions and a steam generator tube rupture has been diagnosed. The actions in this procedure are necessary to ensure that the plant results in a stable safe condition.
- 2. ENTRY CONDITIONS .
- a. The Standard Post Trip Actions have been accomplished.
. and
- b. Plant conditions indicate that a steam generator tube rupture has occurred by one or more of the following
- i. Steam generator blowdown radiation high alarm (RC14)
- 11. SJAE Radiation monitor high alarm (RC14) 111. Unbalanced charging and letdown flows (CO2) iv. Standby charging pumps start (CO2)
- v. Decreasing pressurizer level and pressure (C03) vi. Main steam line radiation monitor (s) alarming (RCOSE)
- 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 2534 Page 2 Rev. 5
Instructions Conting:ncy Actions [ ;) CAUTION
/
SS/SCO must be notified immediate1 of any safety function criteria not satisfied. 3.2 Perform Safety Function Status 3.2 H safety function status check checks criteria are not satisfied, Then
- a. Complete OPS Form 2534-1 a. Diagnose problem and ,
at approximately 10 minute go to appropriate E0P intervals until plant conditions stabilize i. E any break is and suspected, Then refer to b Direct STA qualified
- Break Identification individual to review report Chart, Figure 4.1 to and verify acceptance assist in diagnosis criteria are satisfied, and
- 11. Go to appropriate break E0P EE
- b. E diagnosis of one event is not apparent, Then go to Functional Recovery E0P 2540 O
V l E0P 2034 Paca ? Rev. 5 l
Instructions Contingency Actions (v) CAUTION Pressurizer level may not provide an accurate indication of total RCS inventory due to voids. Voids may exist, espec'ially if RCPs are not running. However, pressurizer level in conjunction with a subcooled RCS is an indication that the core is covered. The reactor vessel level monitor gives an indication of void size above the core. 3.3 Confirm the diagnosis of a steam 3.3 generator tube rupture
- a. Refer to Break a. E a loss of primary Identification Chart, coolant is indicated, ,
Figure 4.1 Then* to to E0P 2532 - and g
- b. Direct Chemistry to b. M excess steam demand is sample steam generators indicated, Then go to
) for activity E0P 2536 3.4 g pressurizer pressure decreases 3.4 Manually initiate *SIAS, to 1600 psia (C03), Then do CIAS and EBFAS (C01) the following
- a. Verify SIAS, CIAS and EBFAS (C01X)
- b. Stop one RCP in each loop (A and C preferred) (C03)
- c. Shut the spray valve at the discharge of the idled RCP in loop 1 and leave in manual (CO3)
- d. Refer to Figure 4.3 for acceptable safety injection system delivery flow.
O E0P 2534 Page 4 Rev. 5
Instructions Contingency Actions / "T CAUTION: (. / The 30'F Thot subcooling RCP trip criteria is most limiting only during the initial phase of the event. As the RCS is cooled and depressurized, RCP operating paramete's (e.g. NPSH) become increasingly restrictive.
- 3. 5 ET subcooling h
decreases below 3. 5 C_ontinue with this procedure. 30 F, Then stop all RCPs (CO3) - 3.6 E EBFAS has initiated, Then 3.6 Continue with this procedure, align Condenser Air Removal System to Unit 2 Stack by the , following ' -
- a. Verify Condenser Air Removal Fan, F-55A or F-558, running (or manually start) (C06)
~'
and
- b. Open 2-EB-57 (C06)
O E0P 2534 Page 5 Rev. 5
e . Instructions Contingency Actions
~
O CAUTION D RCS hT should be reduced to less than 520 F in both loops before isolating a steam generator to minimize the potential for subsequent lifting of steam generator safc-ties. NOTE Narrow range T h stops at 515*F. Wide range T h ic available on C101. _3. 7 Initiate a plant cooldown using 3.7 both steam generators to reduce a. Opente atmospheric dump Th to less than 520 F in both valves (C05) loops (C04). and ,
- a. Operate steam dump and b. ,L3 opening and closing O bypass valves to reduce RCS times in SS Log.
T at 50-75 F per hour (C05) h and
- b. Refer to Plant Cooldown, OP 2207, or Plant Cooldown using Natural Circulation, AOP 2553.
CAUTION Use of the steam driven auxiliary feedwater pump will result in an uranonitored radioactivity release. 3.8 During the cooldown, maintain 3.8 Manually control main or steam generator level auxiliary feedwater (C05) / 50-70% (C05) - E0P 2534 Page 6 Rev. 5
Instructions Contingency Actions 3.9 During the cooldown, When 3.9 H MSI occurs, Th g maintain permitted, block HSI (C01) steam in the tuebine building by [] '~' opening the MSIV bypass valves CAUTION
- 1. As the RCS is cooled and depressurized, RCP operating parameters (e.g. NPSH requirements) become increasingly restrictive.
- 2. If naximum spray water temperature differential exceeds 350 F l an Engineering evaluation must be performed following the event. Notify Engineering if spray water temperature differential exceeds 200 F.
NOTE
- 1. Auxiliary spray depressurization rate may be as high as 50 psi / min.
CN PORV depressurization rate will be even faster. Auxiliary spray U should provide better control of the depressurization process.
- 2. Reducing pressure may require throttling HPSI flow. Step 3.17 provides HPSI termination criteria.
3.10 Reduce and maintain RCS pressure 3.10 Depressurize using PORV(s). using main or auxiliary spray Refer to Functional Recovery of until one of the following RCS Inventory and Pressure, conditions is reached. E0P 2540C, Step 3.4
- a. RCS pressure is approximately equal to steam generator pressure (C05) 0E
- b. RCS T subcooling approaches h
30*F (ICC Summary display) A V E0P 2534 Page 7 Rev. 5
Instructions Conting:ncy Actions 3.11 Determine which steam generator 3.11 Select steam generator with has the rupture. Symptoms are [/'t
\s_
higher radiation readings to be isolated.
- a. High radiation on main steam *ine rad monitors (RCOSE)
- b. Higher steam generator activity (sample results)
- c. Higher baron concentration (sample results)
- d. Increasing steam generator level (C05)
- e. Lower feedwater flow rate as indicated by valve .
position (C05) * [J'l E0P 2534 Page 8 Rev. 5 1
c - _ _ _ _ - _ _ _ _
. Instructions Conting ncy Actions i ) . CAUTIONS v
- 1. Steam generators are vital for RCS heat removal. One steam generator must be used for this purpose even if ruptures are detected in both steam generators.
- 2. Do not isolate atmospheric dump valves, unless they have failed open.
3.12 When RCSh T is less than 520*F (C05), 3.12 Manually close valves Then isolate the affected steam generator. Do the following
- a. Raise the setpoint of the ,
associated atmospheric ' - dump to 975 psia (C05)
- b. Close the MSIV (C05) ,
- c. Verify the MSIV bypass f closed (C05)
- d. Close the feed regulating valve (C05)
- e. Close the main feed block valve (C05)
- f. Close the auxiliary feed regulating valve (C05)
- g. Close the auxiliary feed air assisted check valve (C05)
- h. Verify blowdown is isolated
- i. Close steam supply to steam driven auxiliary feed pump (C05)
- j. Close main steam low point drain (C07)
E0P 2534 Page 9 Rev. 5
0 Instructions Contingency Actions 3.13 Verify the correct steam 3.13 ('~ j generator has been isolated by chemistry analysis,
- a. M the wrong steam generator has been isolated, Then unisolate that generator and isolate the affected steam generator (Step 3.12).
- b. H both steam generators are suspected, Then only isolate the steam generator with the highest radioactivity determined by chemistry sample or radiation readings on main steam line rad monitors (RCOSE)
E0P 2534 Page 10 Rev. 5 [
Instructions Contingency Actions 3.14 Continue RCS cooldown on RCP's 3.14 Refer to Plant Cooldown using ,3' , to cold shutdown Natural Circulation, AOP 2553 ! ) a. Verify cold shutdown boron a. Verify cold shutdown boron concentration, Then concentration, Then
,. Override and open i. Override and open 2-CH 192, RWST to 2-CH-192, RWST to charging r, ump charging pump suction (CO2) suction (CO2) it. Open 2-CH-504, RWST 11. Open 2-CH-504, RWST to charging pump to charging pump suction (CO2) suction (C02) 111. Stop the boric acid 111. Stop the boric acid pumps (CO2) pumps (C02) iv. Close 2-CH-514, iv. Close 2-CH-514 Emergency Borate , Emergency Borate Valve (C02) Valve (C02)
- v. Close 2-CH-508 and v. Close 2-CH-508 and 509, gravity feed 509, gravity feed g isolation valves (C02) isolation valves (C02)
V vi. Complete OPS Form vi. Complete OPS Form 2208-13, shutdown margin 2208-13, shutdown margin and and
- b. Refer to Plant Cooldown, b. Refer to Plant Cooldown, OP 2207 OP 2207 O
E0P 2534 Page 11 Rev. 5
e . Instructions Contingency Actions 3.15 Throughout the cooldown, 3.15 Continue with this procedure
~
monitor for RCS voiding. (~') 'U Indications of voiding are
- a. Pressurizer level increases greater than expecteu while using auxil bry spray (CO3)
E
- b. Pressurizer level increases
- lower than expected for existing HPSI and charging flow (CO3)
E *
- c. Unheated thermocouples in upper head indicate * .
saturated conditions (IC,C Summary display) E
- d. Reactor vessel level ,
less than 100% (ICC Summary display) 3.16 Throughout the cooldown, 3.16 If,RCS f voiding is inhibiting core verify RCS voiding not inhibiting cooling, Then go to Functional adequate core cooling by Recovery E0P 2540
- a. Pressure / Temperature limits of Figure 4.2 are satisfied for incore thermocouple temperature (INTAMX or Tc Map Display) and
- b. At least one steam generator !
is removing heat E0P 2534 Page 12 Rev. 5
Instructions Contingtncy Actions 3.17 Determine if RCPs can be 3.17 Continue with this procedure. restarted by all of the I%.)T following:
- a. Pressurizer level greater than 35% and constant or increasing (C03)
- b. Pressurizer temperature limits of Figure 4.2 satisfied for T 1 " D' '
h operating loop (C03)
- c. One steam generator is removing heat (C05)
- d. RCPs starting prerequisites are met per Reactor Coolant Pump Operation, OP 2301C.
- O O
E0P C534 Page 13 Rev. 5
0 Instructions Contingency Actions CAUTIONS Pressurizer level and pressure can be expected to decrease upon stari.ing RCPs due to loop shrinkage and/or void collapse. The level decrease e.1y be large encugh to drain the pressurizer. RCP operation with a drained pressurizer may continue provided HPSI and charging pumps are operating and NPSH requirements are met. 3.18 If conditions exist for RCP 3.18 l operation, Then
- a. Start HPSI and charging *
- a. Verify Natural Circulation (or verify operating) to flow in the operating .
make up for RCS contraction loop' ' (C01/2) .
. b. Start one RCP in each loop i. Pressurizer level greater (operating loop first) than 20% (CO3)
(B & D Preferred) (C03; ii. . Verify. heat removal from
- c. Monitor RCS pressure and unaffected steam corresponding Tc for generator.
adequate pump NPSH (C03). iii. Pressure / Temperature
- d. Operating HPSI and charging limits of Figure 4.2 pumps to restore pressurizer satisfied for T h I" level 35-45% (C03) the operating loop (CO3) iv. Loop delta T (T -T) h g between 10 and 45*F (C03)
- v. T constant or decreasing e
(CO3) vi. T constant or decreasing h (CO3) 1C
- b. Verify adequate core cooling by incore thermocouple less than 555'F and constant or decreasing.
E09 2534 Page 14 Rev. 5
Instructions Contingency Actions
~
- c. M adequate core cooling
("]' cannot be verified, then go to Functional Recovery, E0P 2540, 3.19 M Pressurizer pressure is 3.19 Continue with this procedure greater than 360 psia and stable, Then stop the LPSI pumps (C01) 3.20 When all the following conditions 3.20 M the HPSI pump termination exist, Then, one facility at a conditions do not exist, Then time, HPSI pumps may be throttled c' to operate HPSI pumps or stopped ' ' .
- a. Pressurizer level greater than 35% and constant or increasing (003)
^ b. Pressure / Temperature limits of Figure 4.2 satisfied for T
h in the operating loop.
- c. Heat removal from the unaffected steam generator
- d. Reactor vessel level above top of Hot leg ( > 43%)
(ICC Summary Display) 1 E0P 2534 Page 15 Rev. 5
a Instructions Contingency Actions
/ 3.21 Control HPSI and/or Charging 3,21 Continue with this procedure pumps flow to restore and maintain
- a. Pressurizer level 20-80%
(C03) 80d b RCS operating loop subcooling at least 30*F subcooled (ICC Summary display) 3.22 jf F9FAS was initiated and 3.22 Un;t 1 Stack recorder indicates a. Continue running EBFS Fans less than 10 cps above pre-event and value, Then return Condenser Air b. Continue discharging. Air Removal Discharge to Unit 1 Removal to Unit 2 Stack. Stack by the following:
- a. Override and stop "A" -
(N' and "B" E8FS Fans (C01) .
b. Close 2-EB-40, 2-EB-41, 2-EB-50, and 2-EB-51 (C01)
- c. Open Condenser Air Removal discharge dampers, 2-EB-55 and 2-EB-56 (C06)
- d. Close 2-EB-57 (C06)
O LJ E0P 2534 Page 16 Rev. 5
Instru'ctions Contingency Actions
- )
3.23 Control level in the isolated 3.23 steam generator less than 90% a. Ifcondenserisavailable, (C05) by maintaining RCS Then do the following: pressure: 1. If level increases above
- a. Nearly equal to the isolated 90%, Then open MSIV steam generator pressure bypass valves (C05) and 11. When level decreases
- b. Within the Pressure / below 50%. Then close Temperature limits of the MSIV bypass valves Figure 4.2 for T in the (C05) h operating loop. b. If the condenser is not available, Then operate atmospheric dump valves' to reduce level.
l "%
\_,
w Ca) E0P 2534 Pp.ge 17 Rev. 5
Instructions Contingency Actions i
~
[d CAUTION i Vse of the Blowdown Treatment System involves processing water that may be highly contaminated. Radiation and contamination levels will be much higher than during normal operation. 3.24 If RCPs cannot be restarted, 3.24 @ the following: Then cool the isolated steam generator by the following:
- a. Lower steam generator a. Lower steam generator level '
level by the following by steaming to the condenser
.i. Obtain management i. Open affected ste4m concurrence to override ' generator MSIV bypass blowdown isolation valve (CO3) ,
signal, and
- 11. Manually position the 11. Whe'n steam generator
. blowdown valves (local) to level decreased to 20%,
allow a drain rate of 75 gpm. Then close MSIV bypass 111. Place steam generator valve (C05), blowdown treatment b. Raise steam generator level system in operation to 90% using auxiliary per Main Steam System feedwater pumps at
! OP 2316A. approximately 150 gpm (C05).
iv. When steam generator c. Repeat' fill and drain process level reaches 20%, Then until desired steam generator I stop draining. pressure and temperature ;
- b. Raise steam generator level obtained (local /C05), i to 90% using auxiliary l l feedwater pumps at approximately 150 gpm (C05).
- c. Repeat fill and drain I
process until desired steam generstor pressure and i temperature obtained (local /COS). i E0P 2534 Page 18 l l Rev. 5 i
~,-r- - -
Instructions Contingency Actions
~
/] 3.25 Alian turbine building sumps 3.25 Align the turbine building sumps V to the CPF sumps (local). to the Aerated Wasts System Refer to OP 2336A, Station Refer to OP 2336A, Station Sumps and Orains Sumps and Orains. _3.26 Verify 2-CN-334, Atmospheric 3.26 Continue with this procedure Orain Collecting Tank drain to LIS, is closed (local) 3.27 Direct Chemistry to sample the 3.27 Continue with this procedure secondary systems for activity 3.28 Refer to AOP 2569, Steam 3.28 Continue with this procedure Generator Tube Leak, for . . guidance on operation with a contaminated secondary system , 3.29 As time permits, Refer to 3.29 Not applicable Reactor Trip Recovery, E0P 2526, and perform additional steps as necessary
- 4. FIGURES 4.1 Break Identification Chart 4.2 RCS Pressure / Temperature Limits 4.3 Safety Injection System Delivery Flow
- Final -
O E0P 2534 Page 19 Rev 5
l 4 j FIGURE 4.1 BREAK IDENTIFICATION CHART INITIAL CONDITION: PRESSURIZER PRESSURE DECREASING EITHER YES S/G PRESSURE NO T 800 pst? YES CONTAINMENT NO PRESSURE INCREASING 7 ygg CONTAINMENT NO PRESSURE INCREASING 7 i , JAE, SECONDARY SECONOARy MAIN STEA. BREAK BREAK LINE. OR BLOW-INSIDE OUTSIDE N" YES DOWN RAD MONITORS O CONTAINMENT CONTAINMENT
, ALARMING 7 PRIMRY PRIMRY BREAK BREAK INSIDE OUTS!DE CONTAINMENT CONTAINMENT -
1 I E0P 2536 E0P'2532 E0P 2534 EXCESS LOSS OF STEAM GENERATOR STEAtt PRIMRY TUSE RUPTURE DE %ND COOLANT UN!QUE SYMPTOMS: EITHER S/G PRESSURE LOW
- HI RAD IN CONTAINMENT .H1 RAD IN SECONDARY
-OR AUX BUILDING PLA!iT .NO RAD INCREASE .
- NORf'AL CONTAINMENT CONDli10NS O
E0P 2534 Page 20 Rev. 5
( FIGURE 4.2 RCS PRESSURE / TEMPERATURE LIMITS ( 2500 ! 4 '
) i e3 ' ' '
i
.- NOT ._
- ACCE PTABLE -
L f Accd PTA ALE 2000 . > f .. 1 1? - If 4 _ ju !
,t _.
j% . .
~~'
7 i ! t E' o[ 7
~
' I1 E150"' l 11 g y [ /
~
w s il,o f j I' f f f , f m E Id ID H E f-+ r~~ r y . J& O k ~
-)
f' ' M t j
/
~
7-
' 'I 6 / / _.
O s$1000 S A::- y/ : . s' '/ "
..[ _-
l q_.
. a. . . . . . _ _.__ _.._. _._
' ' ' 'L--- - - - < - --
500 - s* --
,.' NOT AC.C.f.t TA SLE l-9
'#h pf 1
-_k -I -
l<.~n T e p er * ,g.s A p
- g .. _ _ __ _ _L.J.. .
g_;f I ,J. 10T _-.
.q_ , .!_.- . j . . . .
..;,j.
. _ ______1 . .. .. _ _ . . . . . . . . , . _.
_-: q - __ __ 7._ .+__ 0
- 200 300 400 500 600 i RCS TEMPERATURE (F) i a This curve supercedes the 100F/HR ;ooldown curve any time the RCS has experierced an uncontrolled c>oldown to below 500F.
** This curve supercedes the 30F subcooling curve if, at any time, the containment pressure has exceeded 5 psig.
E0P 2534 Page 21 i Rev. 5
RCS PRESSURE / TEMPERATURE LIMIT DATA r PTS LIMIT 100*F/HR 30*F DEGRADED 200*F COOLDOWN
$U8C00 LED CTNT SU8C00 LED CURVE RC5 SATURATION MINIMUM
- MINIMUM MAXIMUM MAXIMUM TEMP PRESSURE PRESSURE PRESSURE PRES 5URE PRES $URE
(*F) (psia) (psia) (psia) (psta) (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 560 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 F20 813 1045 1045 515 778 1003 1003 0 510 505 500 744 712 681 963 924 885 963 924 885 495 650 848 448 490 621 813 813 485 593 773 773 480 566 744 744 475 540 712 712 470 515 681 687 465 490 650 657 0 460 467 621 633 2350 455 434 593 607 2286 450 423 566 542 2208 445 402 540 561 2133 440 382 515 540 2060 435 362 490 522 1989 430 344 467 502 1919 425 325 434 483 1852 420 309 423 467 1787 415 292 402 451 1723 V 410 277 392 436 1662 405 262 362 408 1602 400 247 344 406 1543 O E0P 2534 Page 22 Rev. 5
7 ( C RCS PRESSURE / TEMPERATURE LIMIT DATA (Cont'd) PTS LIMIT 100'F/HR 30'F DEGRADED 200'F COOLDOWN SUSC00 LED CTMT SU8C00LE0 CURVE RCS 5ATURATION MINIMUM ' MINIMUM MAXIMUM MAXIMUM TEMP PRESSURE PRES $URE 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 1374 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 1045 345 126 184 281 1003 ,
340 118 173 275 963 .
- 335 110 163 265 924 330 103 153 256 $85 325 96 144 251 848 320 90 135 242 813 315 84 126 . 236 778 310 78 118 230 744 4
O 305 300 72 67 110 103 224 219 712 681 395 62 96 214 650 C 290 58 90 210 621 2230 84 205 593 2100 ( 285 280 53 49 78 202 566 1970 l l 275 45 72 198 540 '"' TIT 5
! 270 42 67 196 515 1730
, 265 39 62 192 490 1620 l 260 35 58 190 467 1530 255 32 53 188 434 1450 4 250 30 49 184 423 1370 245 27 402 1300 l 240 25 382 1230 235 23 362 1170 230 21 344 1100 225 19 326 1040
, 220 17 309 980 115 16 292 930 210 14 277 880 205 13 262 ,
840 200 12 247 800 !O E0P 2534 Page 23 Rev. 5
s f1GURE 4.3 (s MINIMUM REQUIRED SAFETY INJECTION DELIVERY CURVE 1300-1200 of , - _ -
- =
,t 1100-
=
= = .
h-
=
_ t _
=
10 g g a l = : _
.---.- = =
en.ua- : - - g g; , 7 '
-a '
E
* .y -,
.+=. .
f,
-- =
~{-a = =
00
= ---. .--
.s. I
- . = . = --
=
-. d ==.a -
100 '
,U L,4'
... . . .,i i
., i ,
p __-- a W 600 -= ACCZPTABLZ RICION i
- n. , -
. = =
gg, , o , o , u y , a l
=
m o l _ _ y j-
= a : =
400 -
= = ,- = . _
u
;=. .
a ., = a. - --- --- -
=
A.
.! = ,
c
= - - ,
= _
=
3cc < _ = = - -
= -- _
= :
. .a- .* - ---
= c =
_ - .a ....a .a .a .a .=.au
-- =- -- u- u = -
200 -
- --- - ' - - ~ ~ ~ = = : - -- -' --~~~ -~~ --- --
- --. .a
.. ..- - y yg ,
== =
- - - =
=
,,,,,u,7 = = ---
y - - - .-, -- - - a. - ' 100- ~-V WACCIP7ABLZ RICICN 2 '
= -
---- = -
a--
~ ~ ~~~ ~~ ~~ ~~~-
%)~~~~ ~~
m -j .a--
. q..a = .a .a a - .a == l - .a.-== = .g - == =a -
.w.- - .a- .a .i .a '- =a - .a+ .a
- a 0
0 000 1600 2400 3200 4000 TOTAL OF FOUR HPSI AND LPS! HEADER FLOWS (3PM) NOTES: 1. This curve is based on one facility operating and at lease one charging pump in operation.
- 2. If containment 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 f'Jnction parameters meet criteria. E0P 2534 Page 24 Rev.5
~ 8 /hmta-- 3b%k1 2 - V 7-V6 ,
' M APPROVF Y STATIOK SUPERINTENDENT EFFECTIVE DATE PORC MTG NO. !
STEAM GENERATOR TUBE RUPTURE , SAFETY FUNCTION STATUS CHECK NOTES: ! i 1. The purpose of this form is to ensure that all necessary information is
- reviewed when using E0P 2534, Steam Generator Tube Rupture. 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 t'eh SPOS displays. The SS/SCO shall ensure the ,
correct recovery E0P rumber is selected at the SPOS CRT. The~ safety function ! status should be logged below approximately every 10 minutes until plant conditions stabilize. Safety Function Status (YES/NO) Reactivity 4 Inventory l l Pressure i . Heat Removal t Containment Integrity f 3 Vital Auxiliaries Time i
- 4. If the integrated computer system is not functional, then completion of the j rest of this form is necessary at approximately 10 minute intervals until l 1
the plant conditions stabilize. ! f
- 5. Parameters marked with an asterisk require meter readings to be logged. [
All other parameters are responded to by yes or no. OPS Form 2534-1 l Rev. 2 : Page 1 of 10 !
. I
e . STEAM GENERATOR TUBE RUPTURE
. SAFETY FUNCTION STATUS CHECK O -
CAUTION SS/SCO must be notified immediately of any safety function criteria not satisfied. TIME */ DATA ACCEPTANCE PARAMETER CRITERIA / / / / / / /
- 1. i4EACTIVITY CONTROL C_0NDITION 1 - CEAs Inserted
- a. Reactor Power a.
(C04) 1. < 5% and ,
- 11. decreasing ,_ _
- b. CEA Position b. No more t,han one CEA not inserted Condition 2 - Boration '
- a. Reactor Power a.
(C04) i, < 5% and
- 11. decreasing
- b. BAST (CO2) b.
i, level A creasing B (adding boron to RCS) 9.E li. Shutdown margin established O per OPS Form 2208-13 OPS Form 2534-1 Rev. 2 Page 2 of 10 m.,.
-~s ACCEPTANCE
( ) PARAMETER CRITERTA DATA
- 2. RCS INVENTORY CONTROL Condition 1
- 4. Pressurizer level a. > 20%*
(CO3) .
- b. RCS operating loop b. > 30'F" ,
Th subcooling (ICC cabinets)
- c. Reactor Vessel c. above top Level (ICC of hot leg display) ,
h 43t.)'- (ICC Diaplay) xm/ Condition 2
- a. SIS Flow a. Acceptable (C01) per Figure 1
- b. Charging Flow b. All .
(CO2) available pumps operating
- c. RWST level c. > 9.5%*
(C01)
- d. Reactor Vessel d. above fuel level (ICC alignment Display plate (> Ot.)*
(ICC Display) OPS Form 2534-1 Rev. 2 Page 3 of 10 p:' : : "'
ACCEPTANCE (s) PARAMETER CRITERIA DATA
- 3. RCS PRESSURE CONTROL Condition 1
- a. Pressurizer Pressure a. Acceptable per and operating loop T h Figure 2 ,
(CO3) Condition 2 .
- a. SIS Flow a. Acceptable per (C01) Figure 1
. t
- b. Charging Flow b. All available ',
l() pumps operating (CO2) O OPS Form 2534-1 Rev. 2 Page 4 of 10
O (
) ACCEPTANCE '- CRITERIA DATA PARAMETER
- 4. RCS HEAT REMOVAL Condition 1
- a. RCS Tavg a, < 555'F*
(C04)
- b. Steam Generator b.
. level (feed flow) 1. 10-80%* A (C05) ad B (One S/G may be Trending A _ _
isolated and out to 70-80 B . of spec) E it. Feed A Flow B
- c. CST level c.
(C05) 1. > 70%* E
- 11. Actions being taken to restore ,
level O OPS Term a34*L Rev. 2 , Pagi. 5 m 10
.~ ov ~ a -.- -
~
(^')
\ / PARAMETER ACCEPTANCE CRITERIA DATA
- 5. CONTAINMENT INTEGRITY
- a. Containment a. < 2 psig* __
pressure (C01)
- b. Containment area b. less than Rad Monitors alarm (C101) .
setpoint
- 6. VITAL AUXILIARIES ,
- a. Buses 24C or 240 a. Energized (COB) ,
- b. 125VDC Buses, 201A b. Energized ,
or 201B (COB)
- c. Ir.strument Air c. > 90 psig pressure (C06) -
i O OPS Form 2534-1 Rev. 2 Page 6 of 10
1300- : = =
= = ..= -- = , = _ _ , -
_ =
- = = - -
- . = = = z -
, = = , _
= = = = = = = . . . - - -
= = --
= = -
=
12002 k-
= =
=
_= q
' Il z . = = = = = .. , = = = = . -- -
= -
~p -- ---- -, = = = .. . ., z : = ., z , . . . .. . . =
1100< = = = =
= = : = - -
= ---- = - -
. : = , -
= = =
-{-
- . . = = , = ; = - = . = -
= , z : , . -- = -
F- 2 , :
. . : = = = : = z
= = . .,-- .-- =
- - - = =
1000< - - ~~ '< = = = - -'-~ ~ : = = = = = -' -
=. =-=
.,J i
=
= =
= = --'
=
=
=
=
= -
- = -
- =
=
=
4
=
=
l M
. = =
~
*.I
= _
- =
..- = = _ = _ = = =, - -
= ; _, - -".=...- .=. ..-- y . ,
= : : . - - -- =
900 < :
. - - _ = _ _
..-- ,, - = = = : _ : _ - - = = = x .-- . - - __. .
.- . -, .-, e, - ~
, = , T = = 4
-- i = = - -
= -' ' --- M . 4- -
4
, . .. . - , = = = = = = . a = -
= . - = = 2 : --- = = =
g $$$ g .-,- = = r = - = -
,= = = -
. c = = = = x .,-, . - ., = - - = , -
=
=
= = = = = - : -
- a. -' -
= - -
- = =
~ = = = . - : =
q-, --
= : .- - - - - -
; = = z
=_=
--,- - = = = -
-.-- .,-, - , z = =.-- ., .., = =
.. - =
E 700- -- --,--
,,. , .,i
= = -
c = . - -
. ...--- - = z .. ,
p.
.--- ,--- - = = .-- -
W 600 i = -
== ,- -- -
ACCEP7MLE MG20H . -
= = _
= = : =
., = = = .--- _
2
== : = = = = J = 2 -- _ _.
K : = ,- = = = '
= _.
- = = = -
=
500 = = = = =
= = =
-- - = -
= - - - -
d,. 5- -- -- ,
= _ = = -----, - = = = = = =
7 a; ;= - - _ = --
= = = = .,- ,-. - - -,- -, ,-, - = -
D -
= - - -
= , : = = = : = ---- .- - * - -
y 40g , - -
=- --
=
=
=
=
= , = . ---
= =
= -
=
= = =
E . g ., .. ,, . , ;- . _ ; - - -
= = = = - = , ... _ . .-- . -__ . -
- =
- a. .J . = = = = = = . , = = = = = = = = =
}gg , -= 1-, - -
= : -- = --
= _ = : = = - = - _-
=
--- -- . - ,-., == - - -
= = = = ;
= = : = ... - .. , .. . .. =
= = = :
= = = = ..,
g = w . - gA , .g - .g.g .g., , og g .g g.g .g%., ., g i.,,.g .g .g .g 7
.g..pgg gq
. --_. ., .- . - . . - . ,- - - -- = =
. ,-- - . = - -
{ N ]:[%,--Q . .7- '
=
q=
,- t/NAccIP7ML
=
J- - '. - . g-p 100 M C20N - - = -- -
.m.q q .q , M ., . ., e,. ., . . . .u. -., . . .,. .a- ... . . e, .a g , g m..
_> J' _ - . 0 1 _ _ 0 000 1600 2400 3200 4000 NOTE 1: This curve i s based on one facility operating and assumes at least one charging pump is operating. l NOTE 2: [f_ containment pressure has exceeded 5 psig at any time during l 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 l para =eters meet their criteria. 1 l , NOTE 3: The curve applies to the pre-SRAS condition only. MINIMUM REOU! RED SAFETY INJECTION FLOW CURVE J l ers Fct- : s n-1 Rev. 2 Page 7 ef 10
7
. ._ .. . . _ . . . . . .- = - . ~ . .
',. 2 500 < --- , ,
Ir s I 6 i
.- NoT -. ,
(Qy - ACCE PTAME -k i f ACCG PTA ALE 2000 . f --
! I It If t
}_
ja y _.
,e s ~~~
T 1} N IQ #
~
7 E1500 -
! 1 g' I /;
~
f t i w si.o f l' f / / 0
)$
- 5 *
) /
$ IB f
/-f n f
/
i . _.., i - g __
/
31000 _ 6 / /- _ m C -
/
w - y s oc .
=.,
x@ - 2 l
, l --.
._L * . . .,
.. d' . L
.4.' - :
500 - L./)
' . 1. . -' ' ~ d- E - - -< --
s* ((! NOT AC.c.f.eT A BLE < ~ '
,& "_,/
.lE.' ...-
- h. j .., .
> er ** # 1 g__ .a j.f-~ ! , F .
p t 'I - t '
}l . ,. '
u ([t _.. ,q_ .! .. y . , . . .
..q _
s . . . .
...j,).44 y.. .
g e . .._ .-. , , . ., ,_
, ; 7_ .;
200 300 400 500 600 RCS TEMPERATURE (F)
- This curve supercedes the 100F/HR cooldown curve any tirae the RCS has experienced an uncontrolled cooldown to below 500F. l
" This curve supercedes the 30F subcooling curve if, at any time, the contaivent i pressure has exceeded Spsig. !
\ FIGURE 2 RCS PRESSURE /TD'PERATURE LltilTS OPS Form 2534-1 Rev. 2 Page 8 of 10 :
g..) ,...,s, 2 -
f e . RCS PRESSURE / TEMPERATURE LIMIT DATA N] PTS LIMIT 100*F/HR 30'F DEGRADE 0 200'F C00LOOWN SU8C00 LED CTMT SU8C00LE0 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 1432 1787 1787 585 1378 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 (
/
530 525 885 848 1133 1089 1133 1089
, 520 813 1045 1045 '
515 778 1003 1003 (\--) 510 744 963 963 505 712 924 924 500 681 885 885 495 650 848 848 490 621 813 813 485 593 773 773 480 566 744 744 475 540 712 712 470 515 681 687 657 V 465 490 650 460 467 621 633 2350 455 434 593 607 2286 450 423 566 582 2208 445 402 540 561 2133 440 382 515 540 2060 435 362 490 522 1989 430 344 467 502 1919 425 326 434 483 1852 420 309 423 467 1781 415 292 402 451 1723 410 277 392 436 1662 405 262 362 408 1602 400 247 344 406 1543 l L) OPS Form 2534-1 Rev. 2 Page 9 of 10
\" ,,
o . RCS PRESSURE / TEMPERATURE LIMIT DATA (Continued) t PTS LIMIT .100*F/HR 200*F C00LOOWN 30'F DEGRADED CTNT SUSC00 LEO CURVE SUSC00 LED MIN! MUM MAX 1 MUM MAXIMUM RCS , SATURATION MINIMUM PRESSURE PRES 5URE PRES 5URE TEMP PRESSURE PRES 5URE (psia) (psia) (psia) (psta) (psta) ('F) 395 233 325 392 1487
- L% :r Limit 309 378 1432 ef 2350 390 220 208 292 364 1378 385 :,3H6 380 ,H 277 353 375 :,84 262 340 :,2;'t 173 247 329 1227 370 163 233 319 1180 365 :,13h 360 :,53 220 309 299 :,08' l -
355 :,44 204 135 1H 289 1044 350 184 281 1003 345 126
- ,:,8 :,73 275 M3 340
- ,:,0 :,63 265 524 335 153 256 885 -
330 103 251 848 325 H 144 D 320 315 310 90 84 78 1,35
- ,25 118 242 236 230 813 775 744 110 224 712 305 72 103 2:,9 681 300 67 0 M 2:,4 650 395 62 2230 90 210 621 290 58 2100 84 205 593 245 53 :,970 78 202 564 280 49 :,850 72 1M 540 275 45 1730 67 1M 515 270 42 1620 62 192 490 265 39 :,5E0 58 190 467 260 35 :,450 53 188 434 255 32 1370 49 144 423 250 30 1300
- 402 245 27 :,230 M2 240 25 :,170 362 235 23 1100 344 230 21 1040 326 225 19 940
- ,7 309 220 292 930 215 :,6 480 277 210 14 840 262 205 13 800 247 200 12 0 .
OPS Form 2534-1 Rev. 2 Page 10 of 10
'l? .'}}