ML20205A367
| ML20205A367 | |
| 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:
|
| References | |
| EOP-2532, NUDOCS 8810250485 | |
| Download: ML20205A367 (36) | |
Text
_______ _
4 STATION PROCEDURE COVER SHEET A.
IDENTIFICATION t
Number; E0P 2532 Rev.
Title:
LOSS OF PRIMARY COOLANT L
Prepared By: STEVE BRINKMAN B.
REVIEW I have reviewed the above procedure and have found it to be satisfactory.
TITLE SIGNATU8f DATE DEPARTMENT HEAD J
_ 7[24/f7 3d. M Y 77/v7rf OhEhs beiceo s
I I
a C.
SPECIFIC UNREVIEWED SAFETY QUESTION EVALUATION REQUIRED:
Modifies intent of procedure and changes operation of systems as described in design documents.
YES ( )
NO (X (If yes, perform written USQ determination and Safety.
Evaluation, and contact Manager, Safety Analysis Branch to determine need for Integrated Safety Evaluation.)
ENVIRONMENTAL REVIEW REQUIRED (Adverse environmental impact)
YES [ ]
NO %
0.
SPECIFIC SAFETY EVALUATION REQUIRED Affects response of safety systems, performance of systems which may have been credited in the sa'ety analysis or non-credited systems which may indirectly af fect 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 ( )
NO @
F.
PROCEDURE REQUIRES PORC/50RC REVIEW (in addition to review, items with a '!ES response must be documented in the PORC/50RC meeting minutes.)
YESh)
NO ( )
G.
PORC/50RC APPROVAL PORC/50RC Heeting Number 3-N*I)i H.
APPROVAL AND IMPLEMENTATION The attached procedure is hereby approved, and effective on the date below:
hL.s,h th/fr Stat n/ Service /06it Superintendent Effectiver Date
~
O sr>o1'e' ses'87-12'1 <1 B0102')O40500g{DR 13 PDR ADOCK O P
P
- - _ _ _ _._ _. --_ _ _ _ c o
~
LOSS OF PRIMARY C00LM T Page No-Eff. Rev.
1 - 23 4
=
0 O
E0P 2532 Page 1 Rev. 4
LOSS OF PRIMARY C00Lt.NT 1.
PURPOSE To provide the subsequent operator actions which must be accomplished in the event of a loss of primary coolant.
These actions are taken after completion of the Standard Post Trip Actions and a loss of primary coolant event 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 loss of primary coolant has occurred by any one or more of the following i.
Abnormal change in pressurizer level (CO3) 11.
Decreasing pressurizer pressure (CO3) 111. Increasing containment pressure (C01) iv.
High containment radiation (RC-14, C101) v.
Unbalanced charging and letdown flows (CO2) 3.
OPERATOR ACTION 3 Instructions Contingency Actions 3.1 Verify Standard Post Trip 3.1 Perform Standard Post Trip Actions, E0P 2525, have been Actions, E0P 2525 performed O
E0P 2532 Page :
Rev. 4
.c.
Instructions Contingenc_v Actions b)~
D CAUTION SS/SCO must be notified immediately of any safety function criteria not satisfied.
3.2 Perform Safety Function Status 3.2 Iff safety function status Checks check criteria are not satisfied, Then a.
Complete OPS Form 2532-1 a.
Diagnose problem and go at ~ 10 minute intervals to appropriate E0P until plant conditions i.
M any break is stabilize suspected, Then and refer to Break b.
Direct STA qualified indi-Identification vidual to review data and
. Chart, Figure 4.1 verify acceptance criteria to assist in are satisfied diagnosis O'
and ii.
Go to appropraite break E0P 9.C b.
If diagnosis of one event is not apparent, Then go to Functional Recovery, E0P 2540 O
V E0P 2532 Page 3 Rev. 4
6 e
Instructions Contingency Actions (J
i k
CAUTION Pressurizer level may not provide an accurate indication of total RCS inventory due to voids.
Voids may exist, especially if reactor coolant pumps 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 loss 3.3
$ an excess steam demand of coolant event a.
a.
Refer to Break Identification is diagnosed, Then go to Chart, Figure 4.1 E0P 2536 and or b.
Direct Chemistry to sample b.
M a steam generator tube steam generators for activity rupture is diagnosed.
Then go to E0P 2534 -
3.4 H pressurizer pressure 3.4 Manually initiate SIAS, decreases to 1600 psia (CO3)
CIAS and EBFAS (C01) or containment pressure increases to 5 psig (C01)
Then verify SIAS, CIAS, and EBFAS (C01X) 3.5 g pressurizer pressure decreases 3.5 Continue with this procedure to 1600 psia, Then stop all RCPs (CO3) e E0P 2532 Page 4 Rev. 4
Instructions Contingincy Actions O
3.6 If containment pressure increases
- 3. 6 a.
Manually initiate CSAS 27 psig (C01), Then verify (C01)
I a.
CSAS (C01X) b.
Take steps to ensure b.
Two containment spray header flows adequate containment greater than 1350 gpm each (C01) pressure control l,
c.
Containment air coolers operating 1.
Refer to i
in the emergency mode (C01)
Containment Spray System procedure OP 2309 ti.
Refer to Containment Air Recirculation and Cooling procedure OP 2313A 3.7 H EBFAS has initiated, Then 3.7 Continue with this procedure.
i i
align Condenser Air Removal l
System to Unit 2 Stack by O'
the following.
a.
Verify Condenser Air Removal Fan, F-55A or l
F-558, running (or manually start) (C06) and b.
Open 2-EB-57 (C06) t 3.8 Verify Safety Injection flowrate 3.8 Take steps to ensure f
per Figure 4.3 acceptable safety injection l
flow.
Do the following
[
a.
Ensure electrical power l
to valves and pumps (Col / local) i t
E0P 2532 Page 5 Rev. 4
e instructions Contingency Actions
('s b.
Ensure correct safety I
sV injection system valve lineup (C01) c.
Start idle HPSI, LPSI and charging pumps (C01/3) 3.9 Ensure PORVs and pressurizer 3.9 M either PORV is open, Tun safeties are not open by a.
Normal quench tank a.
Verify RCS pressure less level, pressure and than 2300 psia (CO3) temperatures (CO3) and and b.
Close the block valve of b.
No acoustic monitor the open PORV(s) (C03) alarms (CO2/RC05E) 3.10 Review the potential leak paths 3.10 Manually isolate valves and isolate if possible a.
Verify letdown line isolation C
valves closed (CO2) c.
Verify RCS sample valves closed (C01X) c.
Verify shutdown cooling isolation valves,51-651 and i
652, closed (C01) l 3.11 Varify no leakage into RBCCW 3.11 0,o the following System by a.
Attempt to locate leak i
a.
Surge tank level not increasing (local)
[
(C06) b.
Isolate cornponent with l
and leak (C06/ local) l l
1
- O E0P 2532 Page 6 Rev. 4
Instructions Contingency Actions FN b.'
RBCCW radiation monitors not c.
Drain surge tank to increasing (RC14) maintain level (C06) d.
Continue with this procedure 3.12 If, the containment Auxiliary 3.12 Continue with this procedure.
Circulation Fans are operating, Then snift to slow speed (Col)
CAUTION 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 terminated.
3.13 When containment pressure is less 3.13 Continue with this procedure than 10 psig (C01), Then do the v
following a.
Reset containment spray actuation modules (ESAS) b.
Stop the conteinment spray pumps (C01) c.
Realign for automatic operation (C01)
NOTE Plant cooldown must be initiated as soon as possible and within ore e
hour after reactor trip to conserve condensate inventory.
3.14 Initiate a plant cooldown by the 3.14 Feed as necessary to restore following level to 70-80% (C05) a.
Maintain steam generator levels between 70-80% (C05)
O E0P 2532 Page 7 Rev. 4
e Instructions Contingincy Actions bI Operate staam dump and bypass valves or atmospheric dump valves to reduce RCS T at h
50-75'F/ hour (C03/C101/C05) c.
When MSI block permitted, Then block MSI (C01) d.
Refer to Plant Cooldown, OP 2207, or Plant Cooldown using Natural Circulation, AOP 2553 3.15 Verify Natural Circulation flow 3,15 by the following a.
Ensure adequate cor,e a.
Pressurizer level greater tooling by than 20% (C03) 1.
Adequate safety b.
Heat removal from at least injection flow per one steam generator Figure 4.3 c.
Pressure / Temperature 11.
Incore temperature limits of Figure 4.2 satisfied less than 800'F.
for Th (CO3).
(INTAMX or TC Map Display) d.
Loop delta T (T -T) 111.
Heat removal from h
c between 10 and 45'F (CO3/C101) at least one steam e.
T constant or decreasing (CO3) generator, c
l f.
T c nstant or decreasirg (CO3/C101) or h
b.
Go to Functional Recovery Procedure, E0P 2540.
l 3.16 If, pressurizer pressure is 3.16 Continue with this procedure greater than 1600 r,sia and stable and containment pressure is less than 5 psig, Then reset SIAS, CIAS, and EBFAS (ESAS) l E0P 2532 Page 8 Rev. 4
Instructions Contingency Actions
\\
b CAUTIONS 1.
Do not terminate safety injection flow until all termination criteria are satisfied.
2.
If the termination criteria cannot be maintained after LPSI or HPSI pumps are stopped, the pumps must be restarted.
3.17 g Pressurizer pressure is 3.17 Continue with this procedure greator than 360 psia and L
stable Then stop LPSI pumps 3.18 H all the following conditions 3.18 H the termination conditions exist, Then, one facility at a do not exist, Then HPSI pumps time, HPSI pumps may be throttled must continue to operate or stopped a.
Pressurizer level greater p
than 35% and constant or increasing (CO3) b.
Pressure / Temperature limits of Figure 4.2 satisfied for Th (CO3/C101).
I c.
Heat removal from at least one steam generator l
d.
Reactor vessel level above l
top of the hot leg (> 43%)
j (ICC Summary Display) l i
i l
O E0P 2532 Page 9 Rev. 4 t
I
0-Instructions Continoency Actions 3.19 termine if RCPs can be operated 3.19 Continue with this procedure by all of the following a.
Pressurizer level greater than 35% and constant or increasing (CO3) b.
Pressure / Temperature limits of Figure 4.2 satisfied for Th (CO3),
c.
Heat removal from at least one steam generator d.
RCP starting prerequisite *,
are met per "Reactor Coolant Pump Operation," OP 2301C CAUTION Pressurizer level and pressure can be expected to dec' ease upon starting RCPs due to loop shrinkage and/or void collapse.
The level decrease may be large enough to drain the pressurizer, RCP operation with
, rained pressurizer may continue provided HPSI and charging pumps are operating and NPSH requirements are met.
3.20 If conditions exist for RCP 3.20 If RCP operation is not operation, Then, possible or RCPs did g a.
Start HPSI and charging pumps start, Then verify natural or verify operating to make up circulation per Step 3.15 for RCS contraction (C01/2) b.
Start one RCP in each loop (B&O Preferred) (CO3) c.
Monitor RCS pressure and corresponding Tc for adequate pump NPSH (CO3) d.
Operate HPSI pumps and charging pumps to restore pressurizer level to 35-45% (C03)
E0P 2532 Page 10 Rev. 4
O e
Instructions Contincency Actions
/"'T 3.21 Th'roughout the cooldown monitor 3.21 Continue with this procedure for RCS voiding.
Indications of voiding are a.
Pressuriter level increases greater than expected i
while using auxiliary l
spray (CO3)
SI b.
Pressurizer level increases slower than expected for existing HPSI and charging Flow (CO3) or c.
Unheated thermocouples in upper head indicate i
saturated conditions.
(ICC Summary Display)
O EE d.
Reactor vessel level less than 100% (ICC Summary l
Display) i I:
t i
I I
i I
l E0P 2532 Page 11 I
Rev. 4
Instructions Contingency Actions 3.22 Th'roughout the cooldown, verify 3.22 RCS voiding not inhibiting a.
Do the following (C01/2) e adequate core cooling by
- 1. Verify letdown is a.
Pressure / Temperature limits isolated of Figure 4.2 are satisfied
- 11. Stop pressurizer spray for incore thermocouple flow a
temperature (INTAMX or 111. Operate pressurizer I
TC Hap Display) heaters and/or all and HPS! and charging b.
At least one steam pumps te restore generator is removing heat Pressure / Temperature limits of Figure 4.2 iv. Refer to RCS Vent l
Procedure, OP'2398, for actions to vent reactor vessel head b.
If incore thermocouple O.
temperature is greater than 800*F, Then go to Functional Recovery Procedure, E0P 2540 t
3,23 Verify CST level greater than 3.23 Oo the following 70% (C05) a.
Replenish per Condensate i
Storage / Surge System, 1
OP 23198 1
b.
M CST level decreases to less than 56% (C05), Then
[
verify fire system available (Unit 1) c.
If CST level reaches 16%
(C05), Then align I
[
to the fire system I
per Auxiliary Feedwater System, OP 2322.
l[
E0P 2532 Page 12 L
Rev. 4
[
^
e Instructions Contingency Actions
[')
3.24hRWSTlevelfallsto10%,Then 3.24 Continue with this procedure.
obtain keys from operational key locker for 2-SI-659 and 2-51-660, place in key lock switches, and s' elect "0PER" (C01)
CAUTION Oo not prematurely initiate SRAS.
The manual action should not be taken until 6% RWST level.
3.25 If RWST level decreases below 9.5%
3.25 If RWST level decreases to Then ensure SRAS (C01X) by the 64, Then manually initiate following SRAS (C01),
a.
Both LPSI pumps stop (C01) b.
Both containment sump outlet valves, 2CS-16.1A and C
2CS 16.18, open (C01) c.
Both shutdown heat exchanger RBCCW outlet valves open (C06) d.
Both SI/CS minimum recirculation valves, 2-51-659 and 2-SI-660, closed (C01).
O E0P 2532 Page 13 Rev. 4
O Instructions Contingency Actions
~
p NOTE The HPSI pump design minimum suction pressure is 10 psig.
This is indicated by LPSI pump discharge pressure (C01) or by local indication.
Increased containment wide range sump level and pressure will contribute to this value.
3.26 Monitor HPSI pump performance 3.26 while on SRAS a.
Total HPSI flow greater than a.
M HPSI flow is less 60 gpm (30 gpm for one pump than required for pump 1
operation) cool'ng, Then turn off one charging pumpi at a time and t'en one HPSI h
pump until the remaining HPSI pump flow is greater p
than 30 gpm.
O i
b.
Total HPSI flow less than 1350 gpm b.
If HPSI flow is (less than 675 for one pump operation) greater than allowed.
Then throttle HPSI pump flow until the required flow is attained.
c.
Stable motor current, discharge c.
If cavitation occurs, pressure and flow Then throttle the affected i
pump's discharge until i
the cavitation stops.
NOTE Containment pressure must be less than 10 psig to place the hydrogen concentration monitor in service.
t i
3.27 Place hydrogen concentration 3.27 Direct Chemistry to monitor in operation per sartple containment OP 2313C E0P 2532 Page 14 f
Rev. 4 m
e
-w y
e i
l Instructions, Contingency Actions rm 3.28 Clieck area radiation levels 3.28 Direct Health Physics to (RC14,C101) perform local surveys 3.29 when Boric acid tank levels are 3.29 Continue with this procedure less than 10% Then do the following a.
Stop boric acid pumps l
(CO2) l b.
Stop all three charging pumps (CO2)
I c.
H level in RWST is greater j
than 9.5% (Col), Then 1.
Realign charging pump suction to RWST (C02) and ii. Operate charging pumps as required to restore pressurizer level to 20-80% (CO3) 3.30 When the 51Ts are empty (C01), Then 3.30 continue with this procedure a.
Direct maintenance to install the breaker closing coils (local) and b.
Close the four S!T isolation valves (C01) 3,31 wt.an safety injection termination 3.31 Operate charging and HPS!
criteria are satisfied, pumps until the criteria Then control charging and in Step 3.18 are satisfied letdown or HPS! pump flow to maintain level 20-80% (CO3)
O E0P 2532 Page 15 Rev. 4
Instructions Continoincy Actions 3.32 0etermine if shutdown cooling 3.32 M the RCS remains system operation is possible pressurized due to within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> after trip by an isolated S/G then a.
Pressurizer level greater cool the isciated S/G than 20% and constant or by steaming or blowdown increasing (CO3) and/or feeding, b.
Pressure / Temperature limits of Figure 4.2 satisfied for all RCS temperatures (ICC Summary Display),
c.
RCS activity within appropriate limits.
(Confer with Technical Support Centnr) d.
Other conditions satisfied per Shutdown Cooling System OP 2310 CAUTION Shutdown cooling initiation steps require valve manipulations in a potentially high radiation area.
l l
l 3.33 If the criteria are satisfied for 3.33 If shutdown cooling cannot shutdown cooling operation, Then be initiated Then perform a.
Initiate shutdown cooling Step 3.34, per Shutdown Cooling System.
OP 2310 and b.
Go to Step 3.35 O
E0P 2532 Page 16 Rev 4 l
l
's Instructions Continoency Actions CAUTION Boron precipitation control steps require valve manipulations in a potentially high radiation area.
3.34 Initiate boron precipitation 3.34 Initiate boron precipitation control via SDCS suction within control via Pressurizer 8-10 hours following reactor trip auxiliary spray by the by the following following a.
Verify RCS pressure less than a.
Verify both HPSI pumps 200 psia (CO3) operating (CO2) b.
Close LPS! injection valves, b.
Stop facility 1 HP,SI 2-SI-615, 625, 635 and 645 (C01)
- (Col) c.
Open SOCS warmup isolation c.
Close Facility 1 HPSI valve, 2-51-400 ano SOCS injection valves, suction isolation, 2-51-709 2-51-617, 627, 637 (local) and 647 (C01).
d.
Open key locked SOCS suction d.
Open charging to HPSI isolation valves, 2-51-651 hydro test isolation and 2-51-652 (C01) valve, 2-CH-340 and 2-CH-440 (local) e.
Start one LPSI pump (C01) e.
Close loop 1A and 18 f.
Verify flaw is greater charging valves, 2-CH-518 than 185 gpm (Col) and 519 (CO2).
Verify open charging header isolation valve, 2-CH 429.
f.
Open pressurizer auxiliary spray valve, 2-CH-517 (CO2) g.
Restart facility 1 HPSI pump (C01)
O E0P 2532 Page 17 Rev. 4
e Instructions Contingency Actions
/"N h.
Verify flow is greater than 140 gpm (charging header flow pegged high)
(CO2)
I 3.35 H containment hydrogen 3.35 M Hydrogen Recombiners concentration exceeds 2%,
Then place Hydrogen concentration exceeds 3%,
Recombiners in operation Then purge containment per per OP 2313C, Containment OP 231SC, Containment Post t
Post Incident Hydrogen Incident Hydrogen Control Control 3.36 Operate control rcom 3.36 Continue with this pfocedure ventilation in the recirculation mode per Control Room Ventilation, OP 2315A 3.37 As time permits.
3.37 Not applicable Refer to Reactor Trip Recovery, E0P 2526, and perform additional steps as required I
4.
FIGURES l
4.1 Break Identification Chart l
4.2 RCS Pressure / Temperature Limits 4.3 Safety Injection System Delivery Flow l
l
[
i I
l
- Final -
l O
E0P 2532 Page 18 Rev. 4 t
FIGURE 4.1 BREAK IDENTIFICATION CHART
/
\\
INITIAL CONDITION: PRESSURIZER PRESSURE DECREASING EITHER YES 5/G PRESSURE NO
< 800 psi?
YES CONTA!NMENT g3 PRESSURE INCREASING?
CC'iTAINMENT YES 33 PRESSURE INCREASING?
W A ?.,
SECONOARY SECONOAgy NAIN STE L BREAK EREAK LINE, CR BLOW.
N INSIDE OUTSIDE COUN RAD MONITORS YES CONTAINFENT CONTAINMENT ALARMING 7 O
PRIMARY PRIMARY BREAK BREAK INSIDE OUT5!DE CONTAINMENT CONTAINMENT I
1 E0P 2536 E0P'2532 E0P 2534 EXCESS LOSS OF
- TiAM GENERATOR STEAM PRlFARY TUSE RUPTURE DEFAND COOLANT UNIOUE SYMPTOM 5:
- EITHER 5/G PRES 5URE LOW
- HI RAD IN CONTAINMENT
.H1 RAD IN SECONOARY OR AUX BUILDING PLCiT
.N3 RAD INCREASE
.NCR"AL CONTAINMENT CONO1T I0'i5 E0P 2532 Page 19 Rev. 4 m v,
FIGURE 4.2 RCS PRESSURE / TEMPERATURE LIMITS 2 W*
ii i i6 'ii ii 6
.ii,
'l i
t i
i
(
i i
e i
i 6
(n")
I NOT i
- ACCC FTAGLE '
i 1
AccdPrAAtt 2000 f
tl 6
)
6][
f 6
'I f
1y e
l l*
f i
r r
l
, ~T }
l
?
7 iIo I
~~O 35e
.t "
!I t' y
f.
it.
g b
j F l y
}-.. }
9
'jgY E
l.
13 l
/
x m
n v.f f,
f h1000
[
l/
' 'I
/
~~
7 y
v s
4 a.
s
~
- l t
3_
...g.
t 1....T Soo.
d
. j NOT AC.C.r.t T4LE l-p,.*
. g.
-. 7...i. l.-
-r-i
,j.
4 c'p e, #,,
.j
.J..!
r 7
A
+t
.I 1
.q
,4. j..-
..l 3 ;.
4
- 7. '
.+
g y
200 300 C5 500 600 ROS TEP.Fi'.;iURE (F) r
- This curve supercedes the 100F/HR cooldown curve any time the RCS has l
l esperienced an uncontrolled cco'Jewn to below 500F.
f
- This curve supercedes the 30F *abcooling curve if, at any time, the l
contain ent pressure has exceeded 5 psig.
E0P 2532 Page 20 l
Rev.4
0 l
RCS PRESSURE / TEMPERATURE LIMIT DATA PTS LIMIT 100'F/HR l
30'F DE0MOED 200'F C00LDOW j
$UIC00 LED CTMT SUSC00 LED CliRVE RCS SATURATION MIN! mis MINIMW Mx! MUM MXIMUM TEMP PRE 55URE PRESSURE PRESSURE PRE 55URE PRE 55URE
(*F)
(psta)
(psis)
(psla)
(psia)
(psta)
I 600 1543 1919 1919 Upper Limit of 595 1487 1852 1852 2350 l
590 1432 1787 1787 585 1378 1723 1723 l
c F40 1H6 1662 1662 575 1276 1602 1602 570 1227 1543 1543 565 1180
- ,487 1487 I
TR 1D3 l,432 1432 i
555 1089 1378 1376 J
550 1045 1326 1326 545 1003 1276 1276 540 ST3 1277 1227 535 924 1180 1180
)
530 885 1133 1133 525 84 8 1099 1089 l
T20 813 1045 1045 1
515 778 1003 1003 1
510 744 963 963 505 712 924 914 4
WO 681 465 Sa5 l
495 650 848 448
{
490 621 813 813 485 593 773 77J l
Ts0 566 744 744' l
475 540 712 712 l
470 515 681 687 465 490 650 657 0
I60 467 621 633 2350 455 434 593 607 2286 l
i 450 423 566 582 2208 i
445 402 540 567 113) 2 i
440 382 515 54, 2060 t
435 362 490
!.2 1989 f
430 M4 467
'02 1919 425 326 434 483 185?
467 1787 420 309 423 415 292 402 451 1723 410 277 392 436 1662 405 262 302 408 1602 1
400 247 344 406 1543 i
l i
l i
E0P 2532 Pne 21 Rev. 4 l
i
l i
1 RCS PRESSURE / TEMPERATURE LIMIT DATA (Cont'd) h Pts LIMIT 100'F/HR U
30'F DEGRADED 200'F C00L00VN l
SUSC00 LED r.TM7
$UIC00 LED CURVE i
RCS SATURATION MIN! MUM '
MINIMUM max 1 MUM MAXIMUM i
TEMP PRE 35URE PRE 55URE PRE 55URE PRE 55URE PRE 55URE (psis)
(psia)
(psia)
(*F)
(psia)
(psia) i 355 231 326 392 1487 Upper Limit 390 220 309 378 1432 of 2350 i
385
' 208 292 366 1374 i
j 350 Its_
277 353 h326 D5 184 _
262 340 l275 370 173 -
247
- 329 1227 i
365 163 233 319 1180 360 153 220 309 L133 355 144 204 299
- ,089 I
350 135 156 289 1045
]
345 126 184 281 1003 q
340 118 173 275 963 335 110 163 265 924 1
i 330 103 153 256 485 l
325 96 144 251 848 i
320 90 135_
242 81) 315 84 12 6 236 778 I
310 78 118 230 744 i
305 72 110 224 712 i
300 67 103 219 681 i
395 62 96 214 650 0
l
{
290 58 90 210 621 2230 285 53 84 205 593 2100 280 49 78 202 566 1970 1
1 D5 45 72 198 540 1E5 i
270 42 67 196 515 1730 l
265 39 42 192 490 4620 l
l 260 35 58 190 467 1530
[
j 255 32 53 158 434 1450 j
250 30 49 144 423 1370 J
245 27 402 1300 240 25 382 1230 q
Uh 23 362 1170
[
3 1
230 21 344 1100 i
225 19 326 1040 I
i 220 17 309 980 L
lib 16 292 930
)l
[
210 14 277 850
]
205 13 262 840 t
200 12 247 800 l
t 1
r t
2 l
L O
f
[
c e 22 e0 25,,
n Rev. 4 j
i l
?
FlGURE 4.3 MINIMUM REQUIRED SAFETY INJLCTION DEUVERY CURVE 1300.
3
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3 3
il 1 l
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,- T
,3 4
,yr-/
g g m m ;iQ
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=
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2100 E '$_
=
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=
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=
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=---
900 W,,, i-
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= 7 7
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=
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w 7C,1i,a 3..,
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-... - l i
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600
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0 000 1600 2400 3200 4000 TOTAL OF FOUP. H?SI AND LPSI HEADER FLOWS (SP!',)
NOTES: 1. This curve is based on one fr:ility operating and at lease one charging pump in operation.
2.
I,,f containment pressure has exceeded 5 psig at any time during an event, then do not use this curve.
Its accuracy is in doubt.
l When determining Safety Function status:
Consider the Safety Function satisfied if all other
{
safety function parameters meet criteria.
\\
l E0P 2532 Page 23 l
Rev. 4 l
S__hl4th 3/Jh7 A
FCRMAPPROVJEBY STATIOW SUPERINTENDENT EFFECTIVE DATE PORC MTG NO.
d,,
LOSS OF PRIMARY C'00LANT SAFETY FUNCTION STATUS CHECK NOTES 1.
The purpose of this form is to ensure that all necessary information is reviewed when using E0P 2532, Loss of Primary Coolant.
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 SPDS displays.
The SS/SCO shall ensure the correct recovery E0P numbe;' 's selected at the SPDS CRT.
The safety function status should be logjed be'ow approximately every 10 minutes until plant conditions stabilize.
Safety Function Status (YES/N0)
Reactivity Inventory 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.
AV 5.
Parameters marked with an asterisk require meter readings to be logged.
All other parameters are responded to by yes or no.
OPS Form 2532-1 Rev. 3 Page 1 of 12
6
(
)
LOSS OF PRIMARY COOLANT SAFETY FUNCTION STATUS CHECK CAUTION SS/SCO must be notified immediately of any safety function criteria not satisfied.
TIME */0ATA ACCEPTANCE
/
PARAMETER CRITERIA
/
/
/
/
/
/
1.
REACTIVITY CONTROL
-s(y s
CONDITION 1 - CEAs Inserted a.
Reactor Power a.
(C04) 1.
< 5%
and ii. decreasing b.
CEA Position
- b. No more than one CEA not inserted
( )
m OPS Form 2532-1 Rev. 3 Page 2 of 12 ER '.1 Ei
e I
ACCEPTANCE PARAMETER CRITERIA DATA 1.
REACTIVITY CONTROL (cont)
Condition 2 - Boration a.
Reactor Power a.
(C04) 1.
< 5%
and 1
- 11. decreasing b.
BAST b.
(C02) 1.
level (A)
I decreasing *(B)
i ii, shutdown margin established OPS Form 2208-13 i
}
i i
!O OPS Form 2532-1 Rev. 3 Page 3 of 12 l
MM ' t :Z7
r l
2.
RCS-INVENTORY CONTROL DATA
]
,-b 1
Condition 1 a.
Pressurizer level a.
> 20%*
(CO3) b.
Pressurizer Pressure b.
Acceptable and T per Figure 2 h
(CO3/C101) c.
Reactor Vessel c.
above top level (ICC cabinets of hot leg *
(ICC level display,
(>.43%)
ICC cabinets)
Condition 2 a.
SIS Flow a.
Acceptable (C01) per Figure 1 I
b.
Charging Flow b.
When a (CO2) suction source
- exists, all available pumps operating c.
RWST level c.
(C01) 1.
> 9.5%*
E ii. H6
-9%
Then SRAS OPS Form 2532-1 Rev. 3 Page 4 of 12
!":' ' O S
(~'
~
ACCEPTANCE
(__))
PARAMETER CRITERIA DATA 3.
RCS PRESSURE CONTROL Condition 1 a.
Pressurizer Pressure a. Acceptable and Th (CO3) per Figure 2 Condition 2 a.
SIS Flow a.
Acceptable (C01) per Figure 1 b.
Charging Flow b.
When a s
sj (CO2) suction source exists, all available pumps operating (G
OPS Form 2532-1 Rev. 3 Page 5 of 12
?.';..i : *,::l
4.
RCS-HEAT REMOVAL DATA
{s}
s s_
Condition 1 a.
RCS Tavg a.
<570'F*
(C04) b.
level (feed
- i. 10-80%*
A flow) (C05) and B
Trending A
to 70-80%
B or
- 11. Feed Flow A
B c.
CST level c.
i.
> 70%*
4 or 4 ()
ii. Action being taken to restore level i
Condition 2 a.
Incore a.
< 800'F*
Thermocouple (INTAMX, ICC cabinet) b.
SIS Flow (C01) b.
Acceptable per Figure 1 J
c.
Charging Flow c.
When a suction (CO2) source exists, all available
, ()
pumps operating OPS Form 2532-1 Rev. 3 Page 6 of 12
?"7 ",! ZDT
~
5.
CONTAINMENT lNTEGRITY DATA
-Condition 1 - Break Outside Containment
~
a.
Containment pressure a.
< 2 psig*
(C01) b.
Containment t.
less than radiation monitors alarm (C01) setpoint c.
Containment H c.
< 2%*
2-Concentration (after (C101) placed in service) d.
SJAE, Blowdown and d.
less than Main Steam Line alarm Rad Monitors setpoint-Condition 2 - Break Inside Containment a.
Containment pressure a.
(C01)
- 1. < 5 psig*
or
- 11. E 5 psig,
- 27 psig Then SIAS, CIAS and EBFAS E
tii. E > 27 psig l
Then CSAS b.
Containment H b.
2 l
Concentration i.
< 2%
-(C101)
E
- 11. H > 2%,,
j then H2 Recombiners j
operating j
c.
SJAE, Blowdown and c.
less than Main Steam Line Rad alarm Monitors setpoint j
l OPS Form 2532-1 Rev. 3 i
l Page 7 of 12 4
....,,. m
=.
i l
L O
ACCEPTANCE PARAMETER CRITERIA DATA 6.
VITAL AUXILIARIES a.
Buses 24C or 24D a.
Energized (C08) b.
125VDC Buses, 201A b.
Energized or 201B (C08) c.
Instrument Air c.
> 90 psig l
pressure (C06) i I
!O 1
1 l
=
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O OPS Form 2532-1 Rev. 3 Page 8 of 12
.JA.7 '; 4 100/
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,,, _,,ii o
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ACCEPTABLE REGICN 1
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0 800 1600 2400 3200 4000 NOTE 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 d u r i n i; 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.
MINIMUM RE0UIRED SAFETY INJECTION FLOW CURVE l
FIGURE 1 OPS Form 2532-1 Rev. 3 Page 9 of 12
../
n.m..
. ~
2500 V
HM
- ACCE PTABLE -
i AcceprAnts s'
2000 J
j?
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a l
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t
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'd y
L 8.1500
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U-..---.---._.
500 -
s" / ---/-
NOT ACCteTABLE <
d/,4-_.., g. :.:
l= l..
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etNI
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40T p.!.
g
._g Iv 0
200 300 400 500 600 RCSTEMPERATURE(F).
- This curve supercedes the 100F/HR cooldown curve any tirae the RCS has experienced an uncontrolled cooldown to below 500F.
" This' curve supercedes the 30F subcooling curve ti, at any time, the cont)inment pressure has exceeded Spsig.
FIGURE 2 RCS PRESSURE /TEP.PERATURL Litt!TS OPS FORT! 2532 1 Rev.
3 Page. 10.o4 M
~,,.,
I()
RCS PRESSURE / TEMPERATURE LIMIT DATA PTS LIMIT 100*F/HR 30*F DEGRADED 200*F COOLDOWN
$U8C00 LED CTMT SUSC00 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 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
(
530 885 1133 1133
/
525 848 1089 1089 l
520 813 1045 1045 l
515 778 1003 1003 510 744 963 963 505 712 924 924 500 681 885 885 495 650 848 848 490 621 813 813 485 593 773 773 480 566 744 744 475 540 712 712 470 515 681 687 465 490 650 657 u
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 1787 415 292 402 451 1723 410 277 392 436 1662 V
405 262 362 408 1602
'lO 400 247 344 406 1543 OPS Form 2532 1 Rey, 3 Page 11 of 12 Mll 21 i:Jf
b)
RCS PRESSURE / TEMPERATURE LIMIT DATA (Cont'd)
PTS LIMIT 100*F/HR l
30*F DEGRADED 200*F C00LOOWN l
SU8C00 LED CTMT SU8C00 LED CURVE RCS SATURATION MINIMUM MINIMUM MAXIMUM 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 375 104 262 340 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 340 118 173 275 963 335 110 163 265 924 330 103 153 256 885 325 9G 144 251 848 320 90 135 242 813 f
315 84 126 236 778 0
310 78 118 230 744 305 72 110 224 712 300 67 103 219 681 395 62 96 214 650 C
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 49 184 423 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 l
OPS Form 2532-1 Rev. 3 Page 12 of 12 i U.', '.. '. E,'
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