ML20247M801

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Rev 1 to 1BWEP-0, Reactor Trip or Safety Injection Unit 1
ML20247M801
Person / Time
Site: Byron, Braidwood, 05000000
Issue date: 02/01/1989
From:
COMMONWEALTH EDISON CO.
To:
Shared Package
ML20247M747 List:
References
1BWEP, 1BWEP-0, NUDOCS 8908020232
Download: ML20247M801 (34)
v • d • e


Text

_ - - _ _ _

ATTADNENT ' 12 REY. 1 REACTOR TRIP OR SAFETY INJECTION 1BWEP-0 WOG-1A UNIT 1 l

A. EpRPOSE This procedure provides actions to verify. proper response of the automatic protection systems following manual or automatic actuation of a Reactor Trip or Safety Injection, to assess plant conditions, and to identify the appropriate recovery procedure.

B. SYMPTOMS OR ENTRY CONDITIONS

1) The following are symptoms that may require a Reactor Trip, if one has not occurred:

o Source range high level 1 105 CPS o

Intermediate range high level 1 25% power o

Power range lo-level 1 25% power o Power range hi-level 1 109% power o

Power range positive rate 1 5% power chance in 2 seconds o

Power range negative rate 1 5% power change in 2 seconds o

Overtemperature Delta T 1 116.4% + penalties Overpower Delta T 1 107.2% - penalties o

o High PER pressure 1 2385 psig o

Low PZR pressure i 1885 psig o

High PZR level 1 92%

o Single loop loss of flow I 90% loop flow o

Two loop loss of flow i 90% loop flow in 2/4 loops o

RCP breakers - open o

RCP bus low frequency 1 57.0 Hz o

RCP bus undervoltage 1 5268 volts Turbine trip emergency trip header 1 540 psig oil pressure, o

or Turbine stop valves shut o

8I manual actuation o

Containment high pressure SI > 3.4 psig Low PZR pressure SI i 1829 psIg o

o Low stomaline pressure SI < 640 psig (rate sensitive) o Steam Generator water level low-low 1 40.8% of narrow range span

2) The following are symptoms of a reactor trip:

o Any Reactor Trip first out annunciator lit.

I Rapid decrease in neutron level indicated by nuclear o

instrumentation.

APPROVED Step continued on next page FEB 1

$89

_--mmm on. ens asvww Page 1 of 33 (0024Q/0002Q/040488) 890802O232 890727 PDR ADOCK 05000454 P

PDC

l REV. 1 OPERATOR ACTION

SUMMARY

1BWEP-F.0 WOG-1A FOR 1BWEP-0 SERIES PROCEDURES TRIP RCPS WHEN:

RED PATH

SUMMARY

o CC water.to RCP lost

1. Subcriticality - NUCLEAR (affected pumps only)

POWER >5%

-OR-o Cnmt Phase B actuated

2. Core cooling - CORE EXIT

-OR-TCs >1200*F o

ALL of the following conditions exist:

3. Heat sink-ALL SGs NR__

LEVEL (4% (34% FOR e

Controlled RCS cooldown NOT ADVERSE CNMT) AND TOTAL in progress FEEDWATER FLOW (500 GPM

-AND AVAILABLE RCS pressure - (1370 PSI _G

-AND-

4. Integrity - DECREASE

.High head SI pump flow indicator

>100*F IN LAST 60 MINUTES _.

(1FI-917) >50 GPM flow or AND RCS COLD LEG (246*F SI pumps >100 GPM SI ACTUATION:

5. Containment - CNMT PRESSURE >50 PSIG Actuate SI and GO TO 1BwEP-0, REACTOR TRIP OR SAFETY INJECTION, IF CST LEUE_ <20%, " HEN Step 1, if:

' CONSIDER

'H E FOLLOWLNG:

o RCS subcooling - NOT ACCEPTABLE o Makeup from MUDS or PER ICONIC DISPLAY OR radwaste ATTACHMENT A.

o Prepare to isolate

-OR-secondary supply side o

PZR level - CANNOT BE MAINTAINED of 3 SGs

> 4% (38% FOR ADVERSE CNMT) o Crosstie unit's CST o

Reduce cooldown rate a IF AUX FEED PUMP DA TANK LEVEL

< 50% THEN PERFORM

'HE

0LLOWING: ff IE_fST LEVEL <3%. " HEN PERFORM 1HE FOLLOWLNG:

Refill the day tank e

a. Verify secondary side of 3 SGs isolated
b. Switch AF suction to SX cuppl'j (00220/00020/041388)

APPROVED FEB1 1989 2"EMa

.j REV. 1-REACTOR TRIP OR SAFETY INJECTION 1BWEP-0 WOG-1A' UNIT 1 Step B 2)'(continued) o All shutdown and control rods fully inserted and rod bottom lights lit.

o Rapid decrease in Unit load to zero power.

3) The following may be symptoms that require a Reactor Trip and Safety Injection, if one has not occurred:

o Low PER pressure i 1829 psig.

c' Low steamline pressure 1 640 psig (rate sensitive) o Containment high pressure y_ 3.4 psig 4)'The following may be symptoms of a Reactor Trip and Safety Injection:

o Any SI first out annunciator lit.

All Group 2 cold leg injection monitor lights lit.

o o ESF equipment actuated.

o SI actuated BYPASS-PERMISSIVE light lit.

5)ThisproceduremayalsopsAIteredfrom:

IBwEPES-0.1,REaCbRTRIPRESPONSE, Step 7,whenPZR o

pressure i 1829 psig.

APPROVED FEB 1 1989

."A*n!T!w Page 2 of 33 (0024Q/0002Q/040488) a

REY. 1 OPERATOR ACTION

SUMMARY

1BWEP-F.0 WOG-1A' FOR 1BWEP-0 SERIES PROCEDURES TRIP RCPs WHFN RFD PATH

SUMMARY

9

~

o CC water to RCP lost'

1. Suberiticality - NUCLEAR (affacted pumps only)

POWER >5%

-OR-o Cnet Phase B actuated

2. Core cooling - CORE EXIT

-OR-TCs >1200*F o

ALL of the following conditions exist:

3. Heat sink-ALL SGs NR LEVEL (44 (34% FOR e

Controlled RCS cooldown NOT ADVERSE CNMT) AND TOTAL in progress-

@2DWATER FLOW (500 GPM

-AND AVAILABLE e

RCS pressure - (1370 PSIG

-AND-

4. Integrity - DECREASE High head SI pump flow indicator

>100*F IN LAST 60 MINUTES e

-(IFI-917) >50 GPM flow or AND RCS COLD LEO <246*F SI pumps >100 GPM SI ACTUATION:

5, Containment - CMMT PRESSURE >50 PSIG Actuate SI and GO TO IBwEP-0, REACTOR TRIP OR SAFETY INJECTION, IF CST

_EVEL <20T "4 EN Step 1, if:

CONSIDE t TME'FOL OW:: G:

o RCS subcooling - NOT ACCEPTABLE o Makeup from MUDS or PER ICONIC DISPLAY OR radwaste ATTACHMENT A.-

o Prepare to isolate

-OR-secondary supply side o

PER level - CANNOT BE MAINTAINED of 3 SGs

> 4% (38% FOR ADVERSE CNMT) o Crosstie unit's CST o Reduce cooldown rate a IF AUX

E :D ) J 4P DA" TA WK

_EVEL

< SO% T1 E ni PE t :0R '

'HE

0L _0WIjifai I: :ST LEVEL <3%,

W FN l

PER:0RM TH E FOLLOW : n 3:

Refill the day tank

a. Verify secondary side of 3 SGs isolated
b. Switch AF suction to SX supply (0022Q/0002Q/041388)

APPROVfD FE81 1989

.22.***.*.*.

i

v H -

' REV. 1-REACTOR TRIP OR SAFETY INJECTION 1BWEP-0 WOG-1A UNIT 1-l-

1.

1.

STEP ACTION / EXPECTED RESPON5E RESPONSE NOT OSTAiNED l

CAUTION During a loss of offsite power, operator action will be necessary to actuate PZR PORVs.

.................................ne nee e

NOTE With this procedure in effect, notify the Station Director who will*

evaluate for GSEP conditions per DwZP 200-1, BRWD EMERGENCY ACTION LEVELS.

enamenneseneeseneeeeeeeeeeeeeemeneesenen s

.............eeeeeeen e

e NOTE Steps 1 through 15 are IMMEDIATE ACTION steps.

eeeeeeeeeeeeeeeee.....ee.....eeeeeeeesee

....................................e***

NOTE

" Adverse' Containment" as used in Braidwood Emergency Procedures is defined as:

e o

containment pressure GREATER THAN 5 PSIG

-OR-o contaiment radiation level GREATER THAN 105 R/HR.

I 1RT-AR020 Grid 4 4AS120 1RT-AR021 Grid 4 4AS121

...=*e

...........eeee.........neeneseen l1l VERIFY REACTOR TRIP:

Manually trip the Reactor.

I Rod bottom lights - LIT

.II the Reactor will NOT trip, Reactor trip and bypass THEN GO TO IBwFR-S.1, breakers - OPEN RESPONSE TO NUCLEAR POWER Neutron flux - DECREASING GENERATION /ATWS, Step 1.

APPROVED (0024Q/00020/040488)

FEBi 1989 OTW

REVil-OPERATOR ACTION

SUMMARY

1BWEP-F.0 WOG-1A FOR 1BWEP-0 SERIES PROCEDURES TRIP RCPs WHFN: '

RED PATH

SUMMARY

o CC water to RCP lost

1. Subcriticality - NUCLEAR (affocted pumps only)

PONER >5%

s

-OR-o Cnet Phase B actuated 2

Core cooling - 90RE EXIT j

-OR-TCs >1200*F o

ALL cf the following conditions exist:

3. Heat sink-ALL SGs NR LEVEL (4% (34% FOR Controlled RCS cooldown HQT ADVERSE CIDET) AND TOTAL e

in progress.

FEEDWATER FLON <500 GPM

-AND AVAILABLE e

RCS pressure - (1370 PSIG j

-AND-

4. Tntegrity - DECREASE High head SI pump flow indicator

>400*F IN LAST 60 MINUTES e

(IFI-917) >50 GPM flow or AND RCS COLD LEG <246*F SI pumps >100 GPM SI ACTUATION:~

5. Containment - CMMT PRESSURE >50 PSIG Actuatie SI and GO TO IBneEP-0, REACTOR TRIP OR SAFETY INJECTION, IF CST

_ pre _ (20%. "

EN Step 1, if:-

CONFIDE t "4 E FOM13:

o RCS subcooling - NOT ACCEPTABLE o Makeup from MUDS or PER ICONIC DISPLAY OR radwaste ATTACHMENT A.

o Prepare to isolate

-OR-secondary supply side o

PZR level - CANNOT BE MAINTAINED of 3 SGs

> 4% (38% FOR ADVERSE CIDtT) o Crosstie unit's CST o Reduce cooldown rate o.IF AUX

D >J4P 3A" TAdK

_ EVE

< 50% T 4 F WP E t :0R1

'HE

0L 0WI dG I: CST LEVEL <31 "4 EN PER:ORM TH E FOLLOWL W 3:

Refill the day tank

a. Verify secondary side of 3 SGs isolated
b. Switch AF suction to SX supply (0022Q/0002Q/041388)

APPRoygg FEB1 1989 JM.*%"'.

.9 REV. 1 REACTOR TRIP OR SAFETY INJECTION 1BWEP-0' WOG-1A UNIT 1 i

STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED l2l VERIFY TURBINE TRIP:

Perform the following:

I All Turbine. throttle stop

1) Manually trip the turbine e

valves - CLOSED

2) LF turbine will NOT trip, All Turbine governor valves -

THEN manually run back CLOSED the turbine at maximum rate by the following method:

a) Press TURB MAN.

b) Press FAST ACTION and GOV LWR simultaneously.

IF turbine can NOT be run

back, THEN place EH pumps in PULL OUT position.

IF Turbine still will NOT l

Eip, THEN manually initiate Main Steamline Isolation and manually close MSIV bypass valves.

l1l VERIFY POWER TO 4KV ESF BUSSES' i

l

a. ESF busses - AT LEAST ONE
a. Try to restore power to at ENERGIZED:

least one ESF bus.

o Bus.141 alive light -

H power can NOT be 1

LIT restored to at least one

-OR-ES? bus, j

o Bus 142 alive light -

THEN GO TO IBwcA-0.0, 1

1 LIT LOSS OF ALL AC POWER, Step 1.

i

b. ESF busses - ALL ENERGIZED:
b. Try to restore power to deenergized ESF bus while e

Bus 141 alive light - LIT continuing with this

-AND-procedure.

s Bus 142 alive light - LIT APPROVED FEB1 1989 Eh,R**Ea Page 4 of 33 (0024Q/0002Q/040488) e - _

o REV. 1 OPERATOR ACTION

SUMMARY

1BWEP-F.0 WOG-1A FOR 1BWEP-0 SERIES PROCEDURES TRIP RCPS M :

RED PATH

SUMMARY

o CC water to RCP lost

1. Subcriticality - NUCLEAR (affected pumps only)

POWER >5%

-OR-o Cnet Phase B actuated

2. Core cooling - CORE EXIT

-CR-TCs >1200*F o

ALL of the following conditions exist:

3. Heat sink-ALL SGs NR LEVEL (4% (34% FOR Controlled RCS cooldown NOT ADVERSE CNMT) AND TOTAL in progress FEEDWATER FLOW <500 GPM

-AND AVAILABLE RCS pressure - <1370 PSIG e

-AND-

4. Integrity - DECREASE High head SI pump flow indicator

>100*F IN LAST 60 MINUTES e

(1FI-917) >50 GPM flow or AND RCS COLD LEG (246*F SI pumps >100 GPM SI ACTUATION:

5. Containment - CNMT PRESSURE >50 PSIG Actuate SI and GO TO 1BwEP-0, REACTOR TRIP OR SAFETY INJECTION, IF CST

_ EVE _ <20%. "H'EN Step 1, if:

CONSIDE 4

'H E FOLLOWLNG:

o RCS subcooling - Not ACCEPTABLE o Makeup from MUDS or PER ICONIC DISPLAY OR radwaste ATTACHMENT A.

o Prepara to isolate

-OR-secondary supply side o

PZR level - CANNOT BE MAINTAINED of 3 SGs

> 4% (38% FOR AD'.*ERSE CNMT) o Crosstie unit's CST o Reduce cooldown rate a IF AUX

EED >J1P DA TANK LEVEL

< S0% T 4EN P E R :0RM "HE FOLLOWING:

I: CST LEVEL <3%.

' HEN P :R;;0RM TH E FOLLOWLNG:

Refill the day tank a

a. Verify secondary side of 3 SGs isolated
b. Switch AF suction to SX supply i

(0022Q/0002Q/041388) l APPRoyfD FEB 1 1989

".42f"".

l l

REY. 1 REACTOR TRIP OR SAFETY INJECTION 1BWEP-0 WOG-1A UNIT 1 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED

_ 4 1

15l CHECK IF SI ACTUATED:

Check if SI required:

Any SI first out o

PZR pressure less than annunciator - LIT 1829 PSIG.

e Group 2 Cold Leg

-OR-Injection monitor lights o

Stermline pressure less

- LIT-than 640 PSIG.

-OR-o Containment pressure greater than 3.4 PSIG.

_IF SI required, THEN manually actuate.

IF SI NOT required,

-THEN GD TO 1BwEP ES-0.1, REACTOR TRIP RESPONSE, Step-1.

APPROVED FEB 1 1989

.h%*'ll'?*.*.

age 5 of 33 (00240/0002Q/040488)

REV. 1 OPERATOR ACTION

SUMMARY

1BWEP-F.0 WOG-1A FOR 1BWEP-0 SERIES PROCEDURES TRIP RCPS WHEN:

RFD PATH

SUMMARY

'o CC water to RCP lost

1. Subcriticality - NUCLEAR (affected pumps only)

POWER >5%

-OR-o Cnmt Phase 9 actuated

2. Core cooling - CORE EXIT

-OR-TCs >1200*F o

ALL of the following conditions exist:

3. Heat sink-ALL SGs NR LEVEL (4% (34% FOR e

controllod 3tCS cooldown NOT ADVERSE CNMT) AND TOTAL in progress FEEDWATER FLOW <500 GPM

-AND AVAILABL,E o

RCS pressure - <1370 PSIG

-AND-

4. Integrity - DECREASE High head SI pump flow indicator

>100*F IN LAST 60 MINUTES e

(IFI-917) >50 GPM flow or AND RCS COLD LEG <246*F SI pumps >100 GPM SI ACTUATION:

5. Containment - CNMT

. PRESSURE >50 PSIG Actuate SI and GO TO IBwEP-0, REACTOR TRIP OR SAFETY INJECTION, IF CST

_ EVE _ <20%. "H EN Step 1, if:

.CONSIDE 1 "H E FOLLOW' N 3:

o RCS subcooling - NOT ACCEPTABLE o

Makeup from MUDS or PER ICONIC DISPLAY OR radwaste i

ATTACHMENT A.

o Prepare to isolate l

-OR-secondary supply side o

PZR level - CANNOT BE MAINTAINED of 3 SGs

> 4% (38% FOR ADVERSE CNMT),

o Crosstie unit's CST o

Reduce cooldown rate o IF AUX FEED >JMP DA" TAWK LEVEL

< 50% TH EN P E RFORM

'HE

0LLOWING:

IF CST LEVEL <3%, " HEN PER :0RM TH E FOLLOW::NG:

I Refill the day tank a

a. Verify secondary side of 3 SGs isolated
b. Switch AF suction to SX supply j

l (00220/00020/041388)

APPROVID FEB1 1989 OWw L___ - -

REY. 1 REACTOR TRIP OR SAFETY INJECTION 1BWEP-0 WOG-1A UNIT 1 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED l5l VERIFY FW ISOLATION:

l

a. N pumps-TRIPPED:
a. Manually trip pumps.

1 e

N PUMPS TRIP alarms - LIT

b. FW pumps discharge valves
b. Manually close valves.

- CLOSED:

e 1FWOO2A e

IFWOO2B e

IFW002C

c. FW reg valves - CLOSED:
c. Manually close FW reg valves.

e 1FW516 e

1FW520 I_F,any valve will NOT e

1FW530

close, THEN close its associated e

1FW540 FM shutoff valve:

o 1FW006A o

1FW006B o

IFWOO6C o

1FW006D

d. FW reg byp valves - CLOSED:
d. Manually close valves.

e 1FW510A e

1FW520A e

1FW530A e

1FW540A

e. FM isol valves - CLOSED:
e. Manually close valves.

e 1FW009A e

1FW009B e

1FW009C e

1FW009D Step continued on next page APPROVED FEB1 1989 o'A%iY"w (0024Q/0002Q/040488)

s REV.r1 OPERATOR-ACTION

SUMMARY

1BWEP-F.0

'WOG-1A FOR 1BWEP-0 SERIES PROCEDURES

. TRIP RCPs klHFN:

RFD PATH

SUMMARY

o.

CC water:to RCP lost

1. Subcriticality - NUCLEAR (affected pumps only)

POWER >5%

)

-OR-o Cnet Phase B actuated

2. Core cooling - CORE EXIT

-OR-TCs >1200*F o

ALL of the following conditions exist:

3. Heat sink-ALL SGs NR ~'

LEVEL <4% (34% FOR e

Controlled RCS cocidown NgT ADVERSE CNMT) AND TOTAL in progress FEEDWATER FLOtt <500 GPM

-AND AVAILABLE RCS pressure - <1370 PSIG e

'i

-AND-

4. Integrity - D*r'**ME High head SI pump flow indicator

>100*F IN LAST 60 MINUTES

.e (1FI-917) >50 GPM flow or AND RCS COLD LEG <246*F SI pumps >100 GPM SI ACTUATION:

5. Containment - CNMT PRESSURE >50 PSIG Actuate SI and GO TO IBwEP-0, REACTOR TRIP OR SAFETY INJECTION,

. IF CST

_EifE _ (201. "4 :N Step 1, if:

CONSIDE t 4 E FO J OW':d3:

o RCS subcooling - NOT ACCEPTABLE o Makeup from MUDS or PER ICONIC DISPLAY OR radwaste ATTACHMENT A.

o' Prepare to isolate

-OR-secondary supply side o-PZR level - CANNOT BE MAINTAINED of 3 SGs

> 4% (38% FOR ADVERSE CNMT) o Crosstie unit's CST Reduce cooldown rate o

o IF AUX

E :D ) J 4P 3A" TA dK LEVE g n F.

< 50% T 4 E dP E R:0Rt

'HE

0L _0WI dG! C I: CST LEVEL (31, "4 EN y

PER :0RM TH E FOLLOW::d3:

~

e Refill the day tank

a. Verify secondary side of 3 SGs isolated
b. Switch AF suction to SX supply (00220/00020/041388)

APPRoygg FEB1 1989 JM***.*.*.

..[

T REY. 1 REACTOR TRIP OR SAFETY-INJECTION 1BWEP-0 WOG-1A UNIT 1 STEP.

ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED Step 5 (continued) f 'FW temprng flow cont valves -

f. Manually close. valves.

CLOSED:

e 1FW034A e

1FWO34B e

1FWO34C e

1FW034D

g. FW temprng isol valves -
g. Manually close valves.

CLOSED:

e~

1FW035A e

1FWO35B e

IN035C e

1FWO35D

h. FW prehtr byp isol' valves -
h. Manually close valves.

CLOSED:

e 1FW039A e

1FW039B e

1FWO39C e

1FWO39D

i. FWIV byp isol valves
i. Manually close valves.

CLOSED:

y :,., y e

IN043A

~

e 1FWO43B e

1FWO43C e

1FWO43D

)

i APPROVED FEB1 1989 oSYrra"nsYEw Page 7 of 33 (0024Q/0002Q/040488)

kdV.1 OPERATOR ACTION

SUMMARY

1BWEP-F.0 WOG-1A FOR 1BWEP-0 SERIES PROCEDURES TRIP RCPs WWFW:

RED PATH

SUMMARY

o CC water to RCP lost-

1. Subcriticality - NUCLEAR (affacted puurps only)

POWER >5%

-OR-o Cnet Phase B actuated

2. Core cooling - CORE EXIT

-OR-TCs >1200*F o

ALL of the following conditions exist:

3. Heat sink-ALL SGs NR LEVEL <4% (34% FOR e

Controlled RCS cooldown NOT-ADVERSE CNMT) AND TOTAL in progress FEEDWATER FLON-<500 GPM

-AND AVAILABLE e

RCS pressure - (1370 PSIG

-AND-

4. Integrity - DECREASE High head SI punip flow indicator

>100*F IN LAST 60 MINUTES e

(1FI-917) >50 GPM flow or AND RCS COLD LEG (246*F SI pumps >100 GPM SI ACTUATION:

5. Containment - CNMT PRESSURE >50 PSIG Actuate SI and GO TO 19wEP-0, REACTOR TRIP OR SAFETY INJECTION, IF CST

_ EVE _ (201. " 4 EN Step 1, if:.

CONSIDE t 4 E F0 _LOWL ui:

o RCS subcooling - NOT ACCEPTABLE o Makeup from: MUDS or PER ICONIC DISPLAY OR

.radwaste ATTACHMENT A.

o Prepare to isolate

-OR-secondary supply side o

PZR level - CANNOT BE MAINTAINED of 3 SGs

> 4% (38% FOR ADVERSE CNMT) o Crosstie unit's CST o Reduce cooldown rate o IF AUX F::D >J4P 3A" TAdK

_ EVE

< 50% TH : WP E t :0R r

'HE

0L _0WI WG:

I : CST LEVR < 31. " 4 EN P ER :ORM TH E FOLLOWM W 3:

Refill the day tank e

a. Verify secondary side of 3 SGs isolated
b. Switch AF suction to SX.

supply (00220/00020/041388)

APPROVID FEB 1 1989

. T='".".*."

REV. 'l REACTOR TRIP OR SAFETY INJECTION 1BWEP-0 WOG-1A UNIT 1 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED lH1 VERIFY ECCS PUMPS RUNNING:

Manually start pumps.

CENT CHG pumps run lights - LIT SI pumps run lights - LIT RH pumps run lights - LIT 121 YERI:Y CONTAINMENT ISOLATION PHASE A:

a. Cnat Phase A valves - CLOSD:
a. Manually actuate.Cnmt Isol Phase A and verify e

Group 3 Cnet Isol valves closed.

monitor lights - LIT

. lHI t/ERIF" CONTAINMENT VENTILATION SOLA" ION:

a. Cnmt Vent Isol valves - CLOSD:
a. Manually close valves, e

Group 6 Cnet Vent Isol monitor lights - LIT 13l YERIFY AF PUMPS RUNNING:

a. AF pumps run lights - LIT
a. Manually start pumps.

lElVEtI:Y RCFCs RUNNING IN LOW S ME1:

a. RCFC low speed run
a. Manually start RCFCs in lights - LIT low speed.

lEl VERIFY CC PUMPS RUNNING:

a. CC pumps run lights - LIT
a. Manually start pumps.

lHl VERIFY SY PUMPS RUNNING:

a. SX pumps run lights - LIT
a. Manually start pumps.

APPROVED FEB1 1989

".M.%".

Page 8 of 33 (0024Q/00020/040488)

REY. 1 OPERATOR ACTION

SUMMARY

1BWEP-F.0 WOG-1A FOR 1BWEP-0 SERIES PROCEDURES TRIP RCPS WHFM:

RFn PATH

SUMMARY

o CC water to RCP lost

1. Suberiticality - NUCLEAR (affocted pumps only)

POWER >5%

-OR-o Cnnt Phase B actuated

2. Core cooling - CORE EXIT

-OR-TCs >1200*F o

ALL of the following conditions exist:

3. Heat sink-ALL SGs NR LEVEL (44 (344 FOR Controlled RCS cooldown M ADVERSE CNMT) AND TOTAL e

in' progress FEEDWATER FIOf <500 GPM

-AND AVAILABLE e

RCS pressure - <1370 PSIG

-AND-

4. Integrity - DECREASE High head SI pump flow indicator

>100*F IN LAST 60 MINUTES e

(1FI-917)'>50 GPM flow or AND RCS COLD LEG <246*F SI pumps >100 GPM SI ACTUATION:

5. Containment - CNMT PRESSURE'>50 PSIG Actuatie SI and GO TO 1BwEP-0, REACTOR TRIP OR SAFETY INJECTION, IF CST _Pf E _ (20%

"W EN Step 1, if:

CONSIDE t 4 E FO LOWL 03:

o RCS subcooling - NOT ACCEPTABLE o Makeup from MUDS-or PER ICONIC DISPLAY OR radwaste ATTACHMENT A.

o Prepare to isolate

-OR-secondary supply side o

-PER level - CANNGT BE MAINTAINED of 3 SGs

> 4% (38% FOR-ADVERSE CNMT) o Crosstie unit's CST o

Reduce cooldown rate o IF AUX F E ED

>J 4P 3A" TAWK EEVE

'f 50% THEd P E t :0R t

'HE

0L 0WI WG!

I: CST LEVEL <3%. "

EN P ER :0RM TH E FOLLOWL 0 3:

Refill the day tank

a. Verify secondary side of 3 SGs isolated
b. Switch AF suction to SX supply (0022Q/0002Q/041388) i APPROVED FEB 1 1989

. 3.**=**.*.

' REV. 1.

REACTOR TRIP OR SAFETY INJECTION 1BwEP-0 WOG-1A UNIT-1 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED l13l: 4ECK IF 4LIN STEAMLINES SHOULD 1E ISOLAT E3:

a. Check one or more of the
a. GO TO Step 14.

following conditions:

o ANY STEAMLINE PRESSURE LESS THAN OR EQUAL TO 640 PSIG

-OR-o CONTAINMENT PRESSURE GREATER THAN 8.2 PSIG (1PI-CS934 THRU IPI-CS937)

b. Verify Main Steamline Isolation:
b. Manually initiate Main Steamline Isolation and MSIVs -' CLOSED manually close MSIV bypass MSIV bypass valves - CLOSED valves.

lEl VERIFY l20NTAIMMENT SPRAY NOT R EQUIRF1:

a. Cnat pressure - HAS a.-Perform the following:

REMAINED LESS THAN.20 PSIG, (1PI-CS934 THRU 1PI-CS937, or

1) Verify Containment recorder IPR-937)

Spray actuated.

g NOT, THEN manually actuate.

2) Verify Cnat Isol Phase B valves closed:

e All Group 6 Phase B isol monitor lights y

LIT.

I H NOT, THEN manually close valves.

3) Stop all RCPs.

APPROVED FEB 1 1989 oIYns asTEw (0024Q/0002Q/040488)

.s

REY. 1

-OPERATOR ACTION

SUMMARY

1BWEP-F.0 WOG-1A FOR 1BWEP-0 SERIES PROCEDURES TRIP RCPS WHFN:

RFD PATH

SUMMARY

o CC water to RCP lost

1. Subcriticality - NUCLEAR (affocted pumps only)

POWER >5%

~ OR-o Cnet Phase B actuated

2. Core cooling - CORE EXIT

-OR-TCs >1200*F o

ALL of the following conditions exist:

3. Heat sink-AL", SGs NR

~

LEVEL (4% (34'n FOR e

Controlled RCS cooldown NOT ADVERSE CNMT) AND TOTAL in progress FEEDWATER FLOW (500 GPM

-AND AVAILABLE.

e RCS pressure - <1370 PSIG

-AND-

4. Integrity'- DECREASE High head SI pump flow indicator

>100*F IN LAST_go MINUTES e

(1FI-917) >50 GPM flow or AND RCS COLD LEG <246*F SI pumps >100 GPM SI ACTUATION:

5. Containment - CMMT PRESSURE >50 PSIG

~

Actuate SI and GO TO 19wEP-0, REACTOR TRIP OR SAFETY INJECTION, IF CST

_EV: _ <2M " 41EN Step 1, if:

CONSIDE t 4 E F0_LOWL dli:

o RCS subcooling - NOT ACCEPTABLE o Makeup from MUDS or PER ICONIC DISPLAY OR radwaste ATTACHMENT A.

o Prepare to isolate o

PZR level - CANNOT BE MAINTAINED.

secondary supply side

-CR-of 3 SGs

> 4% (38% FOR ADVERSE CNMT) o Crosstie unit's CST o

Reduce cooldown rate a IF AUX F::D

>J 4P 3A" TAdK EEVE_

< 50% TH E dP E t :0R t "HE

0L-_0WI dG!

Ii: CST LEVEL (3%. "4EN P.ER :0RM TH F FOLLOW:: WG:

Refill the day tank e

a. Verify secondary side of 3 SGs isolated
b. Switch AF suction to SX supply l:

(00220/00020/041388)

APPROVED FEB1 1989 n2C?*w***

~

1BWEP-0 REACTOR TRIP OR SAFETY. INJECTION REV. 1 UNIT 1

. WOG-1A 1

RESPONSE NOT OBT AINED ACTION / EXPECTED RE3PONSE STEP 1

.l3) VERIFY DIESEL GENERATORS RUNNING:

a. Manually start DGs.

L-

a. DGs run lights - MT a

1 IF DGs can NOT be started manually,lly start per THEN loca 1BwoA ELEC-3, LOCAL '

EMERGENCY START OF A' DIESEL GENERATOR.

16 UNOUNC'E CONDIT"0N OVER ' AGE, J dIT 2'EACTOR

' tIP SA:ETY I WJEC'IOM 17 VERI"Y GENERA"Olt "1IP 30 SEC00S A:"El

' JRBINE TRIP:

a. Manually open breakers L
a. Unit 1 Main Transformer feed to as necessary:

345KV Swyd breakers-OPEN:

o ACB 1-8 e

ACB 1-8 o OCB 7-8 e

OCB 7-8

b. Manually open PMG output
b. PMG output breaker -

breaker.

OPEN:

e 41 Brkr

c. Generator lockout relay trip alarm - LIT APPROVED FEB1 1989 EYYEw Page 10 of 33 (0024Q/0002Q/040488) t

)

1.

^

l REV. 1 OPERATOR ACTION

SUMMARY

1BWEP-F.0 WOG-1A FOR 1BWEP-0 SERIES PROCEDURES l-TRIP RCP'; WHEN:

RED PATH

SUMMARY

o CC water to RCP lost

1. Subcriticality - NUCLEAR (affected pumps only)

POWER >5%

-OR-o Cnmt Phase B actuated

2. Core cooling - CORE EXIl

-OR-TCs >1200*F o

AIL of the following conditions exist:

3. Heat sink-ALL SGs NR LEVEL (4% (34% FOR e

Controlled RCS cooldown NOT ADVERSE CNMT) AND TOTAL in progress FEEDWATER FLOW (500 GPM

-AND AVAILABLE RCS pressure - (1370 PSIG

-AND-

4. Integrity - DECREASE

{

High head SI pump flow indicator

>100*F IN LAST 60 MINUTES e

(IFI-917) >50 GPM flow or AND RCS COLD LEG (246*F SI pumps >100 GPM SI ACTUATION:

5. Containment - CNMT

. PRESSURE >50 PSIG Actuate SI and GO TO IBwEP-0, REACTOR TRIP OR SAFETY INJECTION, IF CST _P/E_' (20%. "4EN Step 1, if:

CONSIDE 4 7 E F0 _ LOW:: 43:

i o

RCS subcooling - NOT ACCEPTABLE o Makeup from MUDS or PER ICONIC DISPLAY OR radwaste

. ATTACHMENT A.

o Prepare to isolate j

-OR-secondary supply side l

o PZR level - CANNOT BE MAINTAINED of 3 SGs i

> 4% (38% FOR ADVERSE CNMT) o Crosstie unit's CST o

Reduce cooldown rate o IF AUX FEED >JiP DA" TAW

_EVEL

< 50% TH EN PE FORM

'HE POL _0 WING:

I: CST LEHL <3%. "4 EN P ER :0RM TH E FOLLOW:: 43:

Refill the day tank

a. Verify secondary side of 3 SGs isolated
b. Switch AF suction to SX supply L

(0022Q/0002Q/041388)

APPROVfD FEB1 1989

& ?E" w***

i f

.REV. 1 REACTOR TRIP OR SAFETY INJECTION 1BWEP-0 WOG-1A UNIT 1 STEP ACTION / EXPECTED RESPONSE.

RESPONSE NOT OBTAINED 18 YERIFY ECCS FLOjd:

a. High head SI pump flow
a. Manually start CENT CHG indicator (1FI-917) -

pumps and align valves as-GREATER THAN 50 GPM necessary.

b. RCS pressure (1PI-403A/405) -
b. GO TO Step 19.

LESS THAN 1590 PSIG

c. SI pumps' discharge flow
c. Manually start SI pumps and indicators (1FI-918/922) -

align valves as necessary.

GREATER,_T_HAN 100 GPM

d. RCS pretsure (1PI-403A/405) -
d. GO TO Step 19.

LESS THAN 300 PSIG

e. RH pumps discharge flow
e. Manually start RH pumps and indicators (1FI-618/619) -

align valves as necessary.

GREATER THAN 500 GPM 19 VERIFY ECCS VALVE ALIGNMENT:

a. Group 2 Cold Leg Injection
a. Manually align valves as monitor lights required for necessary.

ECCS valve alignment - LIT i

APPROVED l

FEB 1, $89 EEE1?*?a (0024Q/0002Q/040488) j

u q

REV. 11 OPERATOR' ACTION

SUMMARY

1BWEP-F.0 WOG-1A o FOR 1BWEP-0 SERIES PROCEDURES TRIP RCPS WWFM; RFD PATH

SUMMARY

o CC water to RCP lost

1. Subcriticality - NUCLEAR

' q-(affected pumps only)

POWER >5ft

-OR-oL ~Comt Phase B actuated'

2. Core cooling - CORE EXIT

-OR-TCs >1200*F

~~

o A.J4 of the following conditicas exist:

3. Heat sink-ALL SGs NR LEVEL (4% (34% POR e

Controlled RCS cooldown NOT ADVERSE CNMT) AND TOTAL in progress FEEDWATER FLOW <500 GPM

-AND AVAILABLE RC", pressure - (1370 PSIG

-AND-

4. Integrity - DECREASE High head SI pump flow indicator.

>100*F IN LAST 60 MINUTES l-jf (1FI-917) >50 GPM flow or AND RCS COLD LEG (246*F l.-

SI pumps >100 GPM SI AcTt!/GH:

5. Containment-- aner PRESSURE >50 PSIQ I-

)

Actuate SI and GO TO 19wEP-0, REACTOR TRIP OR SAFETY INJECTION, IF CST

_Eif E _ (20T, " HN-Step 1, if:

CONSIDFJ 7 E F0t OW G:

~iakeup from MUDS or o_

RCS subcooling - NOT ACCEPTABLE o

.PER ICONIC DISPLAY OR radwaste ATTACHMENT,A.

o Prepare to isolate

-OR-secondary supply side.

o

-PZR level-- CANNOT BE MAINTAINED of 3 SGs

> 4% (38% FOR ADVERSE CNMT) o Crosstie unit's CST o

Reduce cooldown rate i JF AUX F

ED M4P 3A" TA 4K

_ EVE

+ { ,,, I : FST LEVEL <31, "HTN

,(_50% TH E d P E FOR 4

'HE

0L _OWI WG, f,E P

R EORM THE FOLLOW::G:

i e

Refill the day tank r'

I

a. Verify secondary side of 3 SGs isolated
b. Switch AF suction to SX supply (00270/0002Q/041388)

APPROVED.

FEB1 1989 M "===

I

.J l}

f

^

REY. 1 REACTOR TRIP OR SAFETY INJECTION 1BWEP-0

WOG-1A UNIT 1 1

STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED -!

f n

CAUTION AF flow must remain GREATER THAN 2500 GPM until water level is

~

. GREATER THAN 4%;(344;FOR ADVERSE.

QDt") for:any SG narrow range ind:. cation.

j j

20. VERIFY TOTAL AF FLOW:

i

a. AF flow - GREATER THAN 500 GPM
a. IF SG narrow range level' AVAILABLE E greater than 4% (34% FOR ADVERSE CNMT) in any SG, THEN control feed flow to maintain SG narrow range level.

IF SG narrow range level H less than.4% (34% FOR-ADVERSE CNMT) in all SGs, THEN manually start AF pumps and align valves as necessary.

IF AF flow can NOT be a n F.

established greater than I,~.

500 GPM, THEN GO TO 1BwER-H.1,.

RESPONSE TO LOSS OF' SECONDARY HEAT SINK, Step 1.

APPROVED FEB1 1989 E?EE%9?a Page 12 of 33

.(0024Q/0002Q/040488)

r

+

REV.-1!

OPERATOR ACTION

SUMMARY

1BWEP-F.0 lWOG-1A FOR 1BWEP-0 SERIES PROCEDURES a

, l!

TRIP RCPs..WHEN:

RED PATH

SUMMARY

o CC water-to RCPl lost

1. Subcriticality - NUCLEAR (affocted pumps only)

POWER >5%

.cy-.

o Cumt' Phase B actuated-

2. Core cooling -- CORE EXIT

-OR--

TCs >1200*F o

ALL of the following conditions exist:

3. Heat sink-ALL SGs NR

<.2VEa(4% (34% FOR e

Controlled RCS cooldown M ADVE LSE CNMT) AND TOTAL in progress FEED (ATER FLOW <500 GPM

-AND AVAILABLE o'

RCS pressure - (1370 PSIG

-AND-

4. Integrity - DECREASE High head SI pump flow indicator

>100*F IN LAST 60 MINUTES, e

li -

(1FI-917) >50 GPM flow or AND RCS COLD LEG (246*F SI pumps >100 GPM SI ACTUATION:

5. Containment - CMMT PRESSURE >50 PSIG Actuate SI and GO TO 1BwEP-0,.

REACTOR TRIP OR SAFETY INJECTION, IF CST

_Eif E

<2M. " 4 EN Step 1, if:

CONSIDE t 4 E F0 LOWL d 3:

o RCS subcooling - NOT ACCEPTABL,E_

o Makeup from MUDS or PER ICONIC DISPLAY OR radwaste ATTACHMENT A.

o Prepare to isolate

-OR-secondary supply side o

PZR level - CANNOT BE MAINTAINED of 3 SGs

> 4% (38% FOR ADVERSE CNMT) o Crosstie unit's CST o Reduce cooldown rate a IF AUX F E ED

> NP 3A" TAdK LEVE

< 50% TH E dP Et'OR '

'HE

0LLOWI dG!

I

~

'ST LEV EL <3%; "4 EN P ER :0RM TH E FOLLOW" d3:-

e Refill the day tank

a. Verify secondary side of 3 SGs isolated
b. Switch AF suction to SX supply (00220/00020/041388)

APPRoygg FEB1 1989 A21**=*.*.*.

l r.

"REV. 1 REACTOR TRIP OR SAFETY INJECTION 1BWEP-0 WOG-1A UNIT 1-

)

STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 21 VERIFY AF VALVE ALIGNMENT:

a. AF isol valves - OPEN:
a. Manually OPEN valves.

e 1AF013A e

1AF013B e

1AF013C

-e 1AF013D e

1AF013E-e 1AF013F e

1AF013G e

1AF013H

b. AF flow control valves -
b. Manually throttle valves THROTTLED OPEN:

OPEN.

e 1AF005A e

1AF005B e

IAF005C e

1AF005D e

1AF005E

-e 1AF005F e

1AF005G e

1AF005H APPROVED l

FEB1 1989 o

vs as W

Page 13 of 33 (0024Q/0002Q/040488) t_ _ _ _ _ _ _ ___ _ _ _ _ - - - - - - - - -

l

REV. 1-OPERATOR ACTION

SUMMARY

1BWEP-F.0 WOG-1A FOR 1BWEP-0 SERIES PROCEDURES TRIP RCPS WHEN:

RFD PATH

SUMMARY

o CC water to RCP lost

1. Suberiticality - NUCLEAR (affected pumps only)

POWER >5%

-OR-o Cnst Phase B actuated

2. Core cooling - CORE EXIT

-OR-TCs >1200*F o

ALL of the following conditions

{

exist:

3. Heat sink-ALL SGs NR i

LEVEL (4% (34% FOR e

Controlled RCS cooldown NOT

. ADVERSE CNMT) AND TOTAL in progress FEEDWATER FLOW (500 GPM

-AND AVAILABLE e

rcd pressure - <1370 PSIG

-AND-

4. Integrity - DECREASE High head SI pump flow indicator

>100*F IN LAST 60 MINUTES e

(1FI-917) >50 GPM flow or AND RCS COLD LEO <246*F SI pumps >100 GPM SI ACTUATION:

5. Containment - CNMT PRESSURE >50 PSIG Actuate SI and GO TO 1BwEP-0, REACTOR TRIP OR SAFETY INJECTION, IF CST LEVE_ (20%.

'M EN Step 1, if:

CONSIDE 2 "H E FOLLOW' N i:

o RCS subcooling - NOT ACCEPTABLE

o. Makeup from MUDS or PER ICONIC DISPLAY OR radwaste ATTACHMENT A.

o Prepare to isolate

-OR-secondary supply side o

PZR level - CANNOT BE MAINTAINED of 3 SGs

> 4% (38% FOR ADVERSE CNMT) o Crosstie unit's CST o

Reduce cooldown rate a IE. AUX FEED

>JAP DA" TAWK LEVEi

< 50% TH EN P E R :0RM

'HE

0LLOWI WG!

I: CST LEVEL <3%. " HEN P ERFORM THE FOLLOW::NG:

Refill the day tank e

a. Verify secondary side of 3 SGs isolated

)

b. Switch AF suction to SX supply i

J (00220/00020/041388)

APPROVED FEB 1

$89 M*"E~*

1 l

E 4

0 REV. 1.

REACTOR TRIP OR SAFETY INJECTION:

1BWEP-0

'WOG-1A-UNIT 1 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION If a radioactive release to the-atmosphere. occurs,.then Control Room Offices vent fans, OVVOICA and OVV01CB should be verified tripped at panel OVV01J.

22 VER":Y CONT 20_

203M VENTILATION SYS EM A _IGW G

02 EM E RGE QCY OPERATIO W:
a. Control Room chillers run
a. Manually start chiller for

. lights - LIT:

VC tr6.in in operation.

e Train A - MCR CHLR OA e

Train B - MCR CHLR OB

b. M/U air source aligned for
b. Manually align Train A or B emergency operation:

makeup air source to emer-gency source as necessary:

o TRAIN A FILTER light - LIT o

OVC25Y/09Y-OPEN

-OR-o 0VC32Y/16Y.- CLOSED o

TRAIN B FILTER light - LIT o

OVC281Y/282Y - CLOSED o

0VC312Y/313Y - CLOSED

c. VC train in operation, M/U
c. Perform the following:

air filter unit fan run light

- LIT and discharge flow control

1) Place non-operating VC damper - NOT FULLY CLOSED:

train equipment in operation:

o Train A - M/U Fan 0A and e

Supply fan damper 0VC24Y e

Return fan

-OR-e M/U air filter o

Train B - M/U Fan OB and unit fan damper OVC08Y

2) RETURN TO Step 22a.
d. VC train in operation, recire
d. Manually close recirc charcoal absorber bypass damper:

charcoal absorber bypass damper on VC train in o

Train A OVC43Y - CLOSED operation.

-OR-o Train B OVC44Y - CLOSED APPROVED Step continued on next page FEB1 1989 Page 14 of 33 samewooo (0024Q/0002Q/040488)

REV. 1 OPERATOR ACTION

SUMMARY

1BWEP-F.0'

.WOG-1A FOR 1BWEP-0 SERIES PROCEDURES i

TRIP RCPs WHEN; RFD PATH

SUMMARY

o CC water to RCP lost

1. Subcriticality - NUCLEAR (affocted pumps only)

POWER >5%

.-OR-o Cnet Phase B actuated

2. Core cooling - CORE FMIT

-OR-TCs >1200*F o

.ALL of the following conditions exist:

3. Heat sink-ALL SGs NR LEVEL (4% (34% FOR e

Controlled RCS cooldown NOT ADVERSE CNMT) AND TOTAL in progress FEEDWATER FLOW <500 GPM

-AND AVAILABLE e

RCS pressure - <1370 PSIG

-AND-

4. Integrity - DECREASE e

High head SI pump flow indicator

>100*F IN LAST 60 MINUTES (1FI-917) >50 GPM flow or AND RCS COLD LEG (246*F SI pumps >100 GPM SI ACTUATION:

5. Containment - CNMT PRESSURE >50 PSIG Actuate SI and GO TO IBwEP-0, REACTOR TRIP OR SAFETY INJECTION, IF CST

_ EVE _ <20%, "4 EN Step 1, if:

CONSIDE t 4 E FOLLOW" W 3:

o RCS subcooling - NOT ACCEPTABLE o Makeup from MUDS or PER ICONIC DISPLAY OR radwaste ATTACHMENT A.

o Prepare to isolate

-OR-secondary supply side o

PZR level --CANNOT BE MAINTAINED of 3 SGs

> 4% (38% FOR ADVERSE CNMT) o Crosstie unit's CST o

Reduce cooldown rate o' IF AUX

D ')J 4P 3A" Taut LEVE

<-50% TA E WP E t:0R u

'HE

0L'_0WI WG I: 'ST LEV:L <3%.

"'4 EN P ER :0RM TH E FOLLOW:: 4 3:

Refill the day tank e

a. Verify secondary side of 3 SGs isolated i
b. Switch AF suction to SX supply 3

(0022Q/0002Q/041388)

APPROVED FEB1 1989

=EE"2L*.

REVa 1 REACTOR TRIP OR SAFETY INJECTION 1BWEP-0 WOG-1A UNIT 1 STEP ACTION / EXPECTED RESPONSE RE5FONSE NOT 06TAiNED Step 22 (continued)

e. Control Room pressure - GREATER
e. Refer to Bw0P VC-1.4, MAIN THAN +0.125" H90, (MCR/TB CONTROL ROOM PRESSURE LOW, DP, OPDI-VC038) while continuing with this procedure.

APPROVED FEB1 1989 O"asTaw Page 15 of 33 (0024Q/00020/040488)

I L_____--_______-----__

~;

REV. 1 OPERATOR ACTION

SUMMARY

1BWEP-F.0 WOG-1A FOR 1BWEP-0 SERIES PROCEDURES 1

TRIP RCPS WHEN:

RED PATH

SUMMARY

o CC water to RCP lost

1. Subcriticality - NUCLEAR (affected pumps only)

POWER >5%

-OR-o Cnmt Phase B actuated

2. Core cooling - CORE EXIT

-OR-TCs >1200*F l

o ALL of the following conditions exist:

3. Heat sink-ALL SGs NR LEVEL <4% (34% FOR e

Controlled RCS cooldown NOT ADVERSE CNMT) AND TOTAL 1

in progress FEEDWATER FLOW (500 GPM

-AND AVAILABLE e

RCS pressure - <1370 PSIG l

-AND-

4. Integrity - DECREASE i

High head SI pump flow indicator

>100*F IN LAST 60 MINUTES l

e (1FI-917) >50 GPM flow or AND RCS COLD LEG <246*F i

SI pumps >100 GPM SI ACTUATION:

5., Containment - CNMT PRESSURE >50 PSIG Actuate SI and GO TO IBwEP-0, REACTOR TRIP OR SAFETY INJECTION, IF CST LEVEL (20%, " HEN Step 1, if:

CONSIDE R

'H E FOLLOW NG:

o RCS subcooling - NOT ACCEPTABLE o Makeup from MUDS or l

PER ICONIC DISPLAY OR radwaste ATTACHMENT A.

o Prepare to isolate

-OR-secondary supply side o

PZR level - CANNOT BE MAINTAINED of 3 SGs

> 4% (38% FOR ADVERSE CNMT) o Crosstie unit's CST o Reduce cooldown rate IF AUX ::ED )JMP DA" TANK LEVEL

< 50% T 4EN P E RFORM

'HE FOLLOWING:

IF CST LEVEL <3% " HEN PERFORM THE FOLLOWMG:

Refill the day tank e

a. Verify secondary side of 3 SGs isolated
b. Switch AF suction to SX supply (00220/0002Q/041388)

APPRoygg FEB1 1989 Mlln*,

i REY. 1 REACTOR TRIP OR SAFETY INJECTION 1BWEP-0 WOG-1A UNIT 1-4 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED e.......................................

1 NOTE Only one Aux Bldg Charcoal Booster Fan should be. started.in each non-accessible area exhaust filter plenum.

Only two plenums can be

~

used at any one time.

-t

............................e***e 23 VER":Y AllX 11G VENTI ATIGN SYS" EM A_IG d :1 FO R EM E RGE dCY OPERATIOW:

a. Two.non-accessible AB Charcoal
a. Start non-accessible Booster Fans run lights-- LIT:

AB Charcoal Booster Fans as necessary per BwOP VA-5, o

OVA 03CA or OVA 03CB for Plenum A AUX BLDG CHARCOAL BOOSTER o

OVA 03CC or 0VA03CD for Plenum B FAN OPERATION.

o OVA 03CE or OVA 03CF for Plenum C essenemmene****eneesene eemanneeemenennee NOTE Only one Fuel Bldg Charcoal Booster Fan should be run at a time.

e..........................e***e.........

2t4 VER":Y FlJE _ B _D3 VE WTI _ATION SYS" EM A IliNF1

0R EME tGENCY OPERATIOW:
a. Train A or Train B Fuel
a. Start Train A or B Bldg Charcoal Booster Charcoal Booster Fan Fan run light - LIT:

per BwOP VA-6, FUEL HANDLING BLDG CHARCOAL o

FHB Booster Fan 0A BOOSTER FAN OPERATION.

OVA 04CA

-OR-o FHB Booster Fan OB APPROVED OVA 04CB FEB1 1989 sENTT"w (0024Q/00020/040488)

= _ - -

.~

'REV.'1-OPERATOR ACTION

SUMMARY

-1BWEP-F.0 WOG-1A FOR 1BWEP-0 SERIES PROCEDURES-l TRIP RCPs WHEN:

RED PATH

SUMMARY

o

- CC water to RCP lost

1. Subcriticality - NUCLEAR (affocted pumps only)

POWER >5%

-OR-o-

Cnet Phase B actuated

2. Core cooling - CORE EKIT

--OR-TCs >1200*F o

-ALL of the following. conditions

exist:
3. Heat" sink-ALL,SGs NR LEVEL (4% (34' i FOR Controlled RCS cooldown NQT ADVERSE CletT) AND TOTAL in progress FEEDWATER FLOW (500 GPM

-AND AVAILABLE RCS pressure.- <1370 PSIG

-AND-

4. Integrity - DECREASE High head SI pump flow indicator

>100*F IN LAST 60 MINUTES e

(IFI-917) >50 GPM flow or AND RCS COLD LEG <246*F SI pumps >100 GPM SI ACTUATION:

5. Containment - CIDtT PRESSURE >50 PSIG Actuate SI and GO TO 19wEP-0, REACTOR TRIP OR SAFETY INJECTION, IF CST _EifE_ (2M "4EN

, Step 1, if:

CONSIDE t "4 E FO_ M di:

o RCS subcooling - NOT ACCEPTABLE o Makeup from MUDS or PER ICONIC DISPLAY OR radwaste

~

ATTACHMENT A.

o Prtpare to isolate

-OR-secondary supply side

~

o PER level - CANf0T BE MAINTAINED of 3 SGs

~

> 4% (38% FOR ANERSE CIDtT) o Crosstie unit's CST o

Reduce cooldown rate a IF AUX :F:D

> J 4P 3A" TAdit

_ EVE

-5 V I:

IST LEVEL (31 "4 EN

< SOE T 4E dP E t :0R '

'HE :0L_0WIdG: f p f,

PER :0RM TH E FOLLOW" di:

Refill the day tank y- '

a. Verify secondary side of 3 SGs isolated
b. Switch AF suction to SX supply (00220/00020/041388)

AppROVfD FEB1 1989

  • " f*.*.*.*.

REVo 1 REACTOR TRIP OR SAFETY INJECTION

_WOG-1A UNIT 1 1BWEP l a

l STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED l

25 CHFCK RCS AVERAGF TEMPERATURE:

a. RCS average temperature -

STABLE AT OR TRENDING TO 557'F

a. R RCS temperature less than 557'F and decreasing, THEN:
1) Stop dumping steam.
2) H cooldown continues, THEN maintain total Tied flow greater than 500 GPM until SG narrow range level greater than 44 (34% FOR ADVERSE CNNT) in at least one SG.
3) R cooldown continues, THEN shutdown unnecessary. main steam loads.
4) H cooldown continues, THEN close MSIV and MSIV bypass valves.

R RCS temperature greater

.5 than 557'F and increasing, V

THEN dump steam to

[p condenser:

1) Check condenser available.
2) Place MS header f

pressure controller in MANUAL and reduce demand signal to zero.

3) Place steam dumps mode selector switch in STEAM PRESSURE mode.

t Step continued on next page

{

APPROVED I

FEB1 1989 Page 17 of 33 (0024Q/0002Q/040488) samewooo

REV. 1.

OPERATOR ACTION

SUMMARY

1BWEP-F.0 WOG-1A FOR 1BWEP-0 SERIES PROCEDURES TRIP RCPS WHFN:

RFD PATH

SUMMARY

i o

CC vater to RCP lost

1. Subcriticality - NUCLEAR l

(affected pumps only)

POWER >5%

' OR-o Comt Phase B actuated

2. Core cooling - CORE EXIT

-OR-TCs >1200*F o.

ALL of the following conditions Efst:

3. Heat sink-ALL SGs NR LEVEL (4% (34% FOR Controlled RCS cooldown NOT ADVERSE CNMT) AND TOTAL in progress FEEDWATER FI4W (500 GPM

-AND AVAILABLE RCS pressure - <1370 PSIG

-AND-

4. Integrity - DECREASE High head SI pump flow indicator

>100'F IN LAST 60 MINUTES (1FI-917) >50 GPM flow or AND RCS COLD LEG (246*F SI pumps >100 DPM SI ACTUATION:

5. Containment - CNMT PREb6"RE >50 PSIG Actuate SI rnd GO TO 1BwEP-0, REACTOR TR)? OR SAFETY INJECTION, IF CST

_ EVE _ <204. " 4 :N Step 1, if:

CONSIDE t

'M E FOL _0WL W 3:

o RCS subcooling - NOT ACCEPTABLE o Makeup from MUDS or PER ICONIC DISPLAY OR radwaste ATTACHMENT A.

o Prepare to isolate

-OR-secondary supply side o

PER level - CANNOT BE MAINTAINED of 3 SGs

> 4% (38% FOR ADVERSE CNMT) o Crosstie unit's CST o Reduce cooldown rate o IF AUX :E:D >14P JA" TAWK LEVE

< SO% T 4 E WP E t :0R-4

'HE

0LLOWI dG!

I: CST LEV:L <3% " HEN P ER :0RM TH E FOLLOWLNG:

Refill the day tank

]

a. Verify secondary side of 3 SGs isolated
b. Switch AF suction to SX supply J

l

(

l 1

l-1 (00220/0002Q/041388)

As PROVED.

)

l FEB 1

$89

{

ML**.**.*,

REV. 1 REACTOR TRIP OR SAFETY INJECTION 1BWEP-0

~

WOG-1A UNIT 1 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OSTAiNED Step 25a (continued)

4) Adjust MS header pressure controller to initiate cooldown rate less than 50*F/Hr.

E unable to dump steam to condenser, THEN dump steam using SG PORVs.

26 CHECK PZR PORVS AND SPRAY VALVES:

a. PORVs - CLOSED:
a. I_F PZR pressure less than 2315 PSIG, 1RY455A THEN manually close 1RY456 PORVs.

E any PORV can NOT be

closed, THEN manually close its isol valve:

o 1RY8000A (IRY455A) o 1RY8000B (1RY456)

IF PORV isol valve can NOT be closed, THEN GO TO IBwEP-1, LOSS OF REACTOR OR SECONDARY COOLANT, Step 1.

b. Normal PZR spray valves -
b. E PZR pressure less CLOSED:

than 2260 PSIG, THEN manually close valves:

1RY455B e

IRY455C o

g spray valve IRY455B can NOT be closed, THEN stop RCP ID.

i o H spray valve IRY455C j can NOT be closed, l

THEN stop RCP IC.

l APPROVED Page 18 of 33 FEB1 1903

('0024Q/0002Q/040488) gwgs,o,

REV. 1 OPERATOR. ACTION

SUMMARY

1BWEP-F.0 WOG-1A FOR 1BWEP-0 SERIES PROCEDURES m

TRIP RCPS WHEN:

RED PATH

SUMMARY

o' CC water to RCP lost

1. Subcriticality - NUCLEAR (affacted pumps only)

POWER >5%

-OR-o.

Cnet Phase B a'ctuatied -

2. Core cooling - CORE EXIT

-OR-TCs >1200*F o

ALL of the following conditions exist:

3. Heat sink-ALL SGs NR LEVEL (4% (34% FOR Controlled RCS cooldown NgT ADVERSE CNMT) AND TOTAL e

in progress FEEDWATER FLON <500 GPM

-AND' AVAILABLE e

RCS pressure - <1370 PSIG

-AND-

4. Integrity - DECREASE H!gh head SI pump flow' indicator

>100*F IN J4T 60 MINUTES (lFI-917) >50 GPM flow or AND RCS CO2 LEG <246*F SI pumps >100 GPM SI ACTUATION:

5. Containment - C30tT PRESSURE >50 PSIG Actuate SI and GO TO 1BvEP-0, REACTOR TRIP OR SAFETY INJECTION, IF CST

_EifE

' 2M, "

H EN Step 1, if:

CONSIDE t 4 E F0

.0W n 3:

o RCS subcooling - NOT ACCEPTABLE o Makeup from MUDS or PER ICONIC DISPLAY OR radwaste ATTACHMENT A.

o Prepare to isolate

-OR-secondary supply side o

PER level - CANNOT BE MAINTAINED of 3 SGs

> 44 (38% FOR ADVERSE CNMT) o Crosstie unit's CST o

Reduce cooldown rate a IF AUX

F:n

)U 4P 1A" TA dK

_ EVE

< 50% T 4F dP ER:OR 4

'HE

0L 0WI WG:

I :' CST LEV EL (3T., " 4 EN P ER :0RM TH E FOILOWL W3:

Refill the' day tank

a. Verify secondary side of 3 SGs isolated
b. Switch AF suction to SX supply

.(00220/00020/0413ss)

APPROVED FEB 1 1989

.22.'".**.*.

REV. 1 REACTOR TRIP OR SAFETY INJECTION 1BWEP-0 WOG-1A UNIT 1 STEP 4CTION/ EXPECTED RESPON5E RESFONSE NOT OBTAiNED CAUTION Seal injection must be maintained to all RCPs to prevent seal. damage due to overheating.

27 CHECK IF~RCPS SHOULD BE STOPPED:

a. ECCS flow:
a. GO To Step 28.

o High head SI flow indicator (1FI-917) -

GREATER THAN 50 GPM

-OR-o Any SI pump discharge flow (1FI-918/922) -

GREATER THAN 100 GPM

b. RCS pressure - LESS THAN
b. Go To Step 28.

1370 PSIG

c. Stop all RCPs
d. Verify steam dumps in STEAM
d. Perform the following:

PRESSURE mode of operation

1) Check condenser i

available.

i

2) Place MS header pressure controller in MANUAL and reduce demand signal to zero.
3) Place steam dumps mode i selector switch in l

STEAM PRESSURE mode.

4) Adjust MS header i

pressure controller to l maintain desired RCS j

temperature.

j APPROVED FEB1 1989 l

o W U m"w Page 19 of 33 (0024Q/0002Q/040488) 8

REY. 1 OPERATOR ACTION

SUMMARY

1BWEP-F.0 WOG-1A FOR 1BWEP-0 SERIES PROCEDURES l

TRIP RCPs WHEN:

RFn PATH SUMMAitY:

o CC water to RCP' lost

1. Suberiticality - NUCLEAR (affected pumps only)

POWER >5%

-OR-o Cnet Phase B actuated.

2. Core cooling - CORE EXIT

-OR-TCs >1200*F

-o ALL of the following conditions exist:

-3. Heat sink-ALL SGs NR LEVEL (4% (34% FOR e-Controlled RCS cooldown NOT ADVERSE CNMT) AND TOTAL in progress FEEDWATER FLOW <500 GPM

-AND AVAIIABLE RCS pressure - <1370 PSIG e

-AND-

4. Integrity - DECREASE' High head SI pump flow indicator

>100*F IN LAST 60 MINUTES e

(1FI-917) >50 GPM flow or AND RCS COLD LEG (246*F SI pumps >100 GPM SI ACTUATION:

5. Containment - CNMT PRESSURE >50 PSIG Actuate SI and GO TO IBwEP-0, REACTOR TRIP OR SAFETY INJECTION, IF CST

_EVEz <2M, " 4EN Step 1, if:

~

CONSIDE t-4 E FO LOW".dG:

o RCS subcooling'- NOT ACCEPTABLE o Makeup from MUDS or PER ICONIC DISPLAY OR radwaste ATTACHMENT A.

o Prepare to isolate

-OR-secondary supply' side o

PZR level - CANNOT BE MAINTAINED of 3 SGs

> 4% (38% FOR ADVERSE CNMT) o Crosstie unit's CST o

Reduce cooldown rate o IF AUX

D )J 4P SA" TAdK

_ EVE

< 50% T 4 E dP E 1:0R u

'HE

0L _0WI WG:

I: CST LEV EL <3%. 94EN P ER :0RM TH E FOLLOW:: WG:

e Refill the day tank

a. Verify secondary side of 3 SGs isolated
b. Switch AF suction to SX supply (0022Q/0002Q/041388)

APPROVfD FEB1 1989 M*"

I

REV 1

REACTOR TRIP OR SAFETY INJECTION 1BWEP-0 WOG-1A UNIT 1 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAiNED 28 CHECT IF SG(s) SECONDARY PRESSURE 30UN3 ARIES ARE INTACT:

a. Check pressures in all SGs:
a. GO TO 1BwEP-2, FAULTED STEAM GENERATOR ISOLATION,-

l o

NO SG PRESSURE DECREASING Step 1.

IN AN UNCONTROLLED MANNER l

o NO SG COMPLETELY DEPRESSURIZED 29 CHECK IF SG TUBES ARE INTACT:

GO TO 1BwEP-3, STEAM GENERATOR TUBE RUPTURE, l

o SJAE/ Gland Steam Exhaust Gas Step 1.

radiation - LESS THAN ALERT ALARM SETPOINT:

e IPR 27J Grid 1 IPS127 l

SG Blowdown Liquid radiation -

o LESS THAN ALERT ALARM SETPOINT:

e 1PR08J Grid 1 1PS108 o Main Steamline radiation -

LESS TVAN ALERT ALARM SETPOINT:

o Main Steamline 1A, MSIV Rm:

e IRT-AR022 Grid 1 4AA122 e

IRT-AR023 Grid 1 4AA123 e

Main Steamline 1B, MSIV Rm:

]

o 1RT-AR022 Grid 1 4AB222 e

IRT-AR023 Grid 1 4AB223 j

e Main Steamline IC, MSIV Rm:

e IRT-AR022 Grid 1 4AC322 o

1RT-AR023 Grid 1 4AC323 o

Main Steamline ID, MSIV Rm:

APPROVED e

IRT-AR022 Grid 1 4AD422 FEB 1 1989 i

e IRT-AR023 Grid 1 4AD423 M Dw

/

(0024Q/0002Q/040488)

REV. 1~

OPERATOR ACTION

SUMMARY

1BWEP-F.0'

.WOG-1A_

FOR 1BWEP-0 SERIES PROCEDURES j

. TRIP RCPs WWFN; RFD PATH

SUMMARY

o CC water-to RCP lost

1. Subcriticality - NUCLEAR (affected pumps only)

POWER >5%

.-OR-o Cnet Phase B actuated

2. Core cooling - CORE EXIT

-OR-TCs >1200*F i

o ALL of the following conditions

-exist:

3. Heat sink-ALL SGs NR

)

LEVEL (4% (34% FOR

(

Controlled RCS cooldown M ADVERSE CNMT) AND TOTAL e

in progress FEEDWATER FLOW (500 GPM

-AND AVAILABLE e

RCS pressure - (1370 PSIG

-AND-

4. Integrity - DECREASE High. head SI pump flow indicator

>100*F IN LAST 60 MINUTES o

(1FI-917) >50 GPM flow or.

AND RCS CO!, LEG <246*F SI pumps >100 GPM SI ACTUATION:

5. Containment - CNMT PRESSURE >50 PSIG Actuate SI and GO TO IBwEP-0, REACTOR TRIP OR SAFETY INJECTION, IF CST

_ EVE _ (20%. "'4EN Step 1, if:

CONSIDE t 4 E F0_ LOW:: d i:-

o RCS subcooling - NOT ACCEPTABLE o Makeup from MUDS or PER ICONIC DISPLAY OR radwaste ATTACHMENT A.

o Prepare to isolate

-OR-secondary supply side o

PZR level - CANNOT BE MAINTAINED of 3 SGs

> 4% (38% FOR ADVERSE CNMT) o Crosstie unit's CST o Reduce cooldown rate a IF AUX

D >NP
iA" TAWK LEVE

< 50% T 4 E dP E 1:0R+

'HE

0L _0WI WG:

I: CST LEVEL <3%

"d EN P ER :0RM TH E FOLLOW" n 3:

Refill the day tank

a. Verify secondary side of 3 SGs isolated
b. Switch AF suction to SX supply (00220/00020/041388)

APPROVED FEB1 1989

= ?a**.*.*.

REV. 1 REACTOR TRIP OR SAFETY INJECTION 1BWEP-0 WOG-1A UNIT 1 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 30 CHECK IF RCS IS INTACT:

GO TO IBwEP-1, LOSS OF REACTOR OR SECONDARY COOLANT, I

o Cnnt radiation monitors - LESS THAN ALERT ALARM SETPOINTS:

e Cnet area monitors:

1 e

IRT-ARO14 Grid 4 4A0101 e

IRT-AR014 Grid 4 4AS202 e

IRT-AR014 Grid 4 4AS303 e

IRT-AR011 Grid 4 4AS111 e

IRT-AR012 Grid 4 4AS112 e

IRT-AR020 Grid 4 4AS120 e

IRT-AR021 Grid 4 4AS121 I

o Cnat pressure - LESS THAN 3.4 PSIG l

o Cnat recirc sump levels - NORMAL:

o Cnet sump levels indicator lights - NOT LIT:

e ILL-SIO75A e

ILL-SIO75B 1

l l

l l

APPROVED FEB1 1989 oW Uw Page 21 of 33 (0024Q/00020/040488)

1 REV. 1 OPERATOR ACTION

SUMMARY

1BWEP-F.0 WOG-1A-FOR 1BWEP-0 SERIES PROCEDURES TRIP RCPs M :

RFD PATH

SUMMARY

.o CC water to RCP lost

1. Subcriticality - NUCLEAR (affected pumps only)

POWER >5%

. -OR-o Cnet Phase B acturted

2. Core cooling - CORE EXIT

-OR-TCs >1200'F o

ALL of the following conditions exist:

3. Heat sink-AL, SGs NR LEVEL (4% (34' l FOR Controlled'RCS cooldown M ADVERSE CIDETJ AND TOTAL e-in progress FEEDWATER FLOW (500 GPM

-AND AVAILABLE e

RCS pressure -~<1370 PSIG

-AND-

4. Integrity - DECREASE High head SI. pump flow inciicator-

>100*F IN IAST 60 MINUTES

.e (1FI-917) >50 GPM flow or AND RCS COLD LEG <246*F SI pumps >100 GPM SI ACTUATION:

5. Containment - CMMT PRESSURE >50 PSIG Actuate SI and GO TO IBwEP-0, REACTOR TRIP OR SAFETY INJECTION, IF CST

_ EVE _ <2M. "

EN Step 1, if:

. CONSIDE t 4 E FOLLOW:: 03:

o RCS subcooling - NOT ACCEPTABLE o Makeup from MUDS or PER ICONIC DISPLAY OR radwaste ATTACHMENT A.

o Prepare to isolate

-OR-secondary supply side o

PER level - CANNOT BE MAINTAINED of 3 SGs

> 4% (38% FOR ADVERSE ODET) o Crosstie unit's CST o' IF AUX :::n

> J 4P ")A" TA dK

_ EVE V

I: CST LEVEL <3%, "4EN

< 50% T 4 : dPE t :0R1

'HE :0L_0WIdG f n p

P ER :ORM TH E FOLLOW : 43:

Refill the day tank

/

e

a. Verify secondary side of 3 SGs isolated
b. Switch AF suction to SX supply (0022Q/0002Q/041388)

APPROVED FEB 1 1989

.EE.*M

REV. 1 REACTOR TRIP OR SAFETY INJECTION 1BWEP-0 l

WOG-1A UNIT 1 i

STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAiNED 31 CHlECK

F ECCS FLOW SHOULD BE TE RMINATE M
a. Check RCS subcooling
a. DO NOT STOP ECCS pumps.

GO TU Step 33.-

ACCEPTABLE per:

o ICONIC DISPLAY i

-OR-o ATTACHMENT A

b. Secondary heat sink:
b. Il neither condition satisfied, o

Total feed flow to SGs -

THEN DO NOT STOP ECCS GREATER THAN 500 GPM PUMPS.

EU TO Step 33.

AVAILABLE

-OR-o Narrow range level in at least one SG - GREATER THAN 4%

c. RCS pressure - STABLE OR
c. DO NOT STOP ECCS PUMPS.

GO TD Step 33.

INCREASING V

d. DO NOT STOP ECCS PUMPS.

d..PZR level - GREATER THAN B%1 f-RETURN TO Step 31a.

/

32 GO TO 1BwEP ES 1.1. SI TERMINATION, STEP 1 33 INIT" ATE MON"TORING OF C RITICAL SAFE"Y

UNCT :0V STATUS T REES APPROVED FEB1 1989
  1. ME*w Page 22 of 33 (0024Q/0002Q/040488)

I

REV. 1 OPERATOR ACTION

SUMMARY

1BWEP-F.0 WOG-1A FOR 1BWEP-0 SERIES PROCEDURES TRIP RCPs WHFN:

'RFD PATH

SUMMARY

o

.CC water to RCP lost

1. Subcriticality - NUCLEAR (affocted pumps only)

POWER >54 4R-o Comt Phase B actuated

2. Core cooling - CORE EXIT

-OR-TCs >1200'F o

.ALL of the following conditions l

exist:

3. Heat sink-ALL SGs NR LEVEL (4% (34% FOR e

Controlled RCS cooldown NOT ADVERSE CNMT) AND TOTAL in progress FEEDWATER FLOW <500 GPM

-AND AVAILABLE e

RCS pressure - <1370 PSIG

-AND-

4. Integrity - DECREASE High head SI pump flow indicator

>100*F IN LAST 60 MINUTES o

.(1FI-917) >50 GPM flow or AND RCS COLD LEG <246*F SI pumps >100 GPM SI~ ACTUATION:

5. Containment - CNMT PRESSURE >50 PSIG Actuate SI and GO TO IBwEP-0, REACTOR TRIP OR SAFETY INJECTION, IF CST _EW _ (20%

"4 EN Step 1, if:

CONSIDE t "H E FOLLOWL W:3:

o RCS subcooling - NOT ACCEPTABLE o Makeup from MUDS or PER ICONIC DISPLAY OR radwaste ATTACHMENT A.

o Prepare to isolate

-OR-secondary supply side o

PZR level - CANNOT BE MAINTAINED of 3 SGs

> 4% (38% FOR ADVERSE CNMT) o Crosstie unit's CST o

Reduce cooldown rate o IF AUX FEED M4P 3A" TAdK

_ EVE

< SO% THE WP E R :0RT "HE

0L OWI WG I? CST LEVEL <3%

"4'EN P ERIORM TH E FOLLOWL W 3:

Refill the day tank e

a. Verify secondary side of 3 SGs isolated
b. Switch AF suction to SX supply (0022Q/0002Q/041388)

APPROVID.

FEB 1 1989 M***.

REV. 1 REACTOR TRIP OR SAFETY INJECTION 1BWEP-0 WOG-1A UNIT 1 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBT iNED t

CAUTION Alternate water sources for AF pumps will be necessary.if CST level decreases to LESS THAN 3%.

34 CHECK SG LEVELS:

a. Narrow range level - GREATER
a. Maintain total feed flow THAN 4%

greater than 500 GPM until narrow range level Is greater than B in at least one SG.

b. Control feed flow to maintain
b. IF narrow range level in narrow range level - BETWEEN 4%

Ey SG continues to

)

AND 50%

increase in an uncontrolled

manner, THEN GO TO IBwEP-3,-

STEAM GENERATOR TUBE RUPTURE, Step 1.

5 APPROVED l

FEB1 1989 in"*a**w age 23 of 33 (0024Q/00020/040488)

]

A REV. 1 OPERATOR ACTION

SUMMARY

1BWEP-F.0 WOG-1A FOR 1BWEP-0 SERIES PROCEDURES TRIP RCPS WHFE:

RFD PATH

SUMMARY

o CC water to RCP lost

1. Suberiticality - NUCLEAR

]

(affocted pumps only)

POWER >5%

-OR-

)

o Cnmt Phase B actuated.

2. Core cooling - CORE EXIT l

-OR-TCs >1200'F o

ALL of the following conditions exist:

3. Heat sink-ALL SGs NR LEVEL <4% (34% FOR Controlled RCS cooldown NOT ADVERSE CNMT) AND TOTAL in progress FEEDWATER FLOW (500 GPM

-AND AVAILABLE RCS pressure - <1370 PSIG

-AND-

4. Integrity - DECREASE High head SI pump flow indicator

>100*F IN LAST 60 MINUTES (1FI-917) >50 GPM flow or AND RCS COLD LEG <246*F SI pumps >100 GPM SI ACTUATION:

5. Containment - CNMT PRESSURE >50 PSIG Actuate SI and GO TO IBwEP-0, REACTOR TRIP OR SAFETY INJECTION, IF CST LEV _ <20% " HEN Step 1, if:

CONSIDE t

'H E FOLLOWLN3:

o RCS subcooling - NOT ACCEPTABLE o Makeup from MUDS or PER ICONIC DISPLAY OR radwaste

~~

ATTACHMENT A.

o Prepare to isolate

-OR-sect ndary supply side o

PZR level - CANNOT BE MAINTAINED of 3 SGs

> 4% (38% FOR ADVERSE CNMT) o Crosstie unit's CST o Reduce cooldown rate o IF AUX ::FD ?JMP DA" TAWK LEVEL

< 50% TH EN P'E RFORM

'HE

0LLOWING:

I: CST LEVEL <3%,

' HEN P ER-:0RM TH E FOLLOWLNG:

Refill the day tank

a. Verify secondary side of 3 SGs isolated
b. Switch AF suction to SX supply (00220/00020/041388)

APPROVED FEB1 1989 AME*.a.,*a

w q

t k

L REV. 1 REACTOR TRIP OR SAFETY INJECTION 1BWEP-0 WOG-1A.

UNIT 1 i

1 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION

]

Following SI reset, automatic SI will NOT occur, until reactor trip breakors have been cycled.

CAUTION j

If offsite power is lost after BI l

reset, then manual action may be required to restart safeguards.

equipment.

35 RFSET SI:

Reset SI per IBwOA PRI-5, CONTROL' ROOM INACCESSIBILITY,

a. Depress both SI reset ATTACl9ENT E.

pushbuttons b.-Verify SI ACTUATED permissive light - NOT LIT

c. Verify AUTO SI BLOCKED permissive light - LIT APPROVED FEB1 1989

.?M.Tfe (0024Q/0002Q/040488)

. + -

REV.'l OPERATOR ACTION

SUMMARY

1BWEP-F.3 LWOG-1A FOR 1BWEP-0 SERIES PROCEDURES L'

L

' TRIP RCPs WHFN:

RFD PATH

SUMMARY

o-CC water to RCP lost

1. Subcriticality - NUCLEAR 6

-(affocted pumps only)

POWER >5%

-OR-o.

Cnet Phase B actuated 2.' Core cooling - CORE' EXIT

-OR--

TCs >1200*F o

ALL of the following conditions eitIst:

3. Heat sink-ALL SGs NR LEVEL (4% (34% FOR e

Controlled RCS cooldown NOT ADVERSE CNM'?) AND TOTAL in progress; FEEDMATER FWN (500 GPM

-AND AVAILABLE e

RCS pressure - fjl370 PSIG

l. '

-AND-

4. Integrity - DECREASE L

e-.High head SI pump flow indicator

>100*F IN LAST 60 MINUTES (1FI-917) >50 GPM flow or AND RCS COLD LEG <246*F SI pumps >100 GPM

.SI ACTUATION:-

5. Containment - CNMT PRESSURE >50 PSIG Actuate SI and GO TO 19wEP-0, REACTOR TRIP OR SAFETY INJECTION, IF CST

_ EVE

<ML "a EN Step 1,'if:

CONSIDE t 4 E F0

_ M n 3:

o RCS subcooling - NOT ACCEPTABLE o Makeup from MUDS or PER ICONIC DISPLAY OR radwaste ATTACHMENT A.

o Prepare to isolate

-OR-secondary supply side o

PZR level.- CANNOT BE MAINTAINED of 3 SGs

> 44 (38% FOR ADVERSE CNMT) o Crosstie unit's CST o Reduce cooldown rate

- * - IF AUX F E :D ) J 4P 3A" TANK LEVE

< 50% TH E dP : t:0R'

'HE FOL10WI dG:

I:

IST LEV EL ' <3L "4 :N P ER :0RM TH E FOLLOWL G:

Refill the day tank

a. Verify secondary side of'3 SGs isolated
b. Switch AF suction to SX supply 6

(0022Q/0002Q/041388)

APPROVED FEB1 Sag JM.***.*.*.

9

t n

REV. 1 REACTOR TRIP OR SAFETY INJECTION 1BWEP-0

, l-WOG-1A UNIT 1 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED -

36 RESET CONTAINME,NT ISOLATION:

a. Reset Cnmt Isol Phase A
a. Reset per 1BwOA PRI-5, CONTROL ROOM INACCESSIBILITY, ATTACHMENT E.
b. Reset Cnmt Isol Phase B
b. Reset per 1BwOA PRI-5, CONTROL ROOM INACCESSIBILITY ATTACHMENT E.
c. Reset Cnet Vent Isol
d. Check SAC run lights - ANY LIT
d. Start one SAC per BwOP SA-1, STARTUP AND OPERATION,OF THE SAC's.
e. Open Cnmt instrument air isol valves:

e lIA065 IIA 066

f. Open Cnmt fire protection isol valve:

e IFP010 APPROVED FEB1 1989 M N Ew (0024Q/0002Q/040488)

e n

p P

1BWEP-F.0 f

REV. 1 OPERATOR ACTION

SUMMARY

WOG-1A FOR 1BWEP-0 SERIES PROCEDURES

, TRIP RCPS WHEN:

RFD PATH

SUMMARY

o CC water to RCP lost

1. Subcriticality - NUCLEAR (affected pumps only)

POWER >5%

-OR-o Cnat Phase B actuated

2. Core cooling.- CORE EXIT

-OR-TCs >1200*F o

ALL of the following conditions exist:

3. Heat sink-ALL SGs NR LEVEL (4% (34% FOR e

Controlled RCS cooldown NOT ADVERSE CNMT) AND TOTAL in progress FEEDWATER FLOW (500 GPM

-AND AVAILABLE RCS. pressure - (1370 PSIG e

-AND-

4. Integrity - DECREASE _

High head SI pump flow indicator

>100*F IN LAST 60 MINUTES __

a

}

(IFI-917) >50 GPM flow or AND RCS COLD LEG (246*F l

SI pumps >100 GPM SL.AETUATION:

5., Containment - CNMT PRESSURE >50 PSIG-Actuate SI and GO TO 1BwEP-0, REACTOR TRIP OR SAFETY INJECTION, IF CST Pf:

<20%, "l4EN Step 1, if:

CONSIDE t "4 E FO LOW:: W3:

o RCS subcooling - NOT ACCEPTABLE o Makeup from MUDS or PER ICONIC DISPLAY OR radwaste ATTACHMENT A.

o Prepare to isolate

-OR-secondary supply side o

PZR level - CANNOT BE MAINTAINED of 3 SGs

> 4% (38% FOR ADVERSE CNMT) o Crosstie unit's CST' o

Reduce cooldown rate a TF AUX F::D ZNP LA" TAWK EVE I_10% TH E W P EUORP

'HE

0L 10WI 4G:

I': CST LEV EL <3%, ":4EN P ER :0RM TH E FOLLOWLWG:

Refill the day tank o

a. Verify secondary side of.3 SGs isolated
b. Switch AF suction to SX supply 4

(0022Q/0002Q/041388)

APPROVED.

FEB1 1989 2 %***.*.*.

{

l t

REV.L 1 REACTOR TRIP OR SAFETY INJECTION 1BWEP-0 WOG-1A UNIT 1 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAiNED I

l 3

CAUTION RCS pressure should be monitored.

4 If RCS pressure" decreases to LESS THAN 300.PSIG, then RH pumps must be manually restarted to supply water to the RCS.

j

37. CHECK IF RH PUMPS SH0tJLD BE STOPPED:
a. Check RCS. pressure:
1) Pressure (1PI-403A/405) -
1) GO TO IBwEP-1, LOSS OF GREATER THAN 300 PSIG REACTOR OR SECONDARY COOLANT, Step 1.
2) Pressure - STABLE OR
2) GO T0 step 38.

i' INCREASING

~

b. Stop RH pumps and place in standby 38 CHECK SEC1NDARY RADIATION NORMAL.:

Go TO IBwEP-3, STEAM GENERATOR TUBE RUPTURE, Step 1.

a. Sample SGs' blowdown for activity:
1) Open SG blowdown sample isol valves:

e ISD005A e

ISD005B e

ISD005C 1SD005D

2) Notify Rad Chem to sample SGs' blowdown for activity APPROVED FEB1 1989 eA"#%%'.*w (00240/00020/040488) i

REV. 1 OPERATOR ACTION

SUMMARY

1BWEP-F.0 I

WOG-1A FOR 1BWEP-0 SERIES PROCEDURES j

IRJP RCPs WWFN:

RFD PATH

SUMMARY

o CC water to RCP lost

1. Subcriticality - NUCLEAR (affocted pumps only)

POWER >5%

-~

-OR-o Cnet Phase B actuated

2. Core cooling - CORE EXIT

-OR-TCs >1200'F o

ALL of the following conditions exist:

3. Heat sink-ALL SGs NR LEVEL (4% (34% FOR e

Controlled RCS cooldown NOT ADVERSE CNMT) AND TOTAL in progress FEEDWATER FLOW <500 GPM

-AND AVAILABLE RCS pressure - (1370 PSIG

-AND-

4. Integrity - DECREASE High head SI pump flow indicator

>100*F IN LAST 60 MINUTES,,

(IFI-917) >50 GPM flow or AND RCS COLD LEG <246*F SI pumps >100 GPM SI ACTUATION:

5. Containment - CMMT PRESSURE >50 PSIG Actuate SI and GO TO IBwEP-0, REACTOR TRIP OR Sa?I H INJECTION, IF CST

_ EVE _ <20%, "K:g Step 1, if:

CONSIDE R i 2 FO LOW N 3:

o RCS subcooling - NOT ACCEPTABLE o Makeup from MUDS or PER ICONIC DISPLAY OR radwaste ATTACHMENT A.

o Prepare to isolate

-OR-secondary supply side o

PZR level - CANNOT BE MAINTAINED of 3 SGs

> 4% (38% FOR ADVERSE CNMT) o Crosstie unit's CST o Reduce cooldown rate o IF AUX ::ED )JMP 3A" TAQK LEVEL

'HE

0LLOWING1 ',,t I : CST LEV:L <3%,

7EN

< S0% T i :lWP : tFOR 1 p

fi P ER :ORM TH E FOLLOWL 4G:

Refill the day tank

/

a. Verify secondary side of 3 SGs isclated
b. Switch AF suction to SX supply

)

(00220/00020/041388)

APPRoygg FEB1 1989 M*.*.*.**

J l

!v e

REV. 1

' REACTOR' TRIP OR SAFETY INJECTION 1BWEP-0 WOG-1A UNIT 1 STEP ACTION / EXPECTED RESPONSE

. RESPONSE NOT OBTAINED l39 CH ECK AUXILI ARY BUILDING Evaluate cause of abnormal' 1A)lATION:

conditions.

a. Aux Bldg vent stack IF cause is loss of RCS effluent monitors (IPR 28J) -

Inventory outside Cnmt, LESS THAN ALERT ALARM SETPOINT:..

THDi GO TO 1BwCA-1.2, LOCA OUTSIDE CONTAIlOGBIT, Step 1.

e Grid 2 Beta 1PA228 e

Grid 2 Gas Low IPB128 e

Grid 2 Iodine IPC328 Grid 2 Gas High IPD428 e

b. Aux Bldg vent stack effluent monitors (IPR 30J) -

LESS THAN ALERT ALARM SETPOINT:

e Grid 2 Gas Low ~,A130 o

Grid 2 Gas Med IPB230 o

Grid 2 Gas High IPC330 e

Grid 2 Effluent IPF430

c. ECCS cubicle monitors - LESS THAN ALERT ALARM SETPOINT:

RH/CS Pump 1A Cubicle e

(IPR 13J):

~

Grid 2 Beta IPA 2I3 e

Grid 2 Gas IPB11p 2

.c e

a. -

RH/CS Pump 1B Cutiicle e

(IPR 14J):

i e'

Grid 2 Betia 1PA214 I

e Grid 2 Gas IPB114

)

e RH HX 1A Cubicle (IPR 15J):

e Grid 2 Beta 1PA215 e

Grid 2 Gas IPB115 Step continued on next page FEB1 1989 O"asYaw Page 27 of 33 (0024Q/0002Q/040488) n

m REV. 1-OPERATOR ACTION

SUMMARY

1BWEP-F.0 WOG-1A FOR 1BWEP-0 SERIES PROCEDURES TRIP RCPs WHFN; RFD PATH

SUMMARY

o CC water to RCP lost

1. Subcriticality - NUCLEAR (affected pumps only)

POWER >5%

-OR-i o

Cnat Phase B actuated

2. Core cooling - CORE EXIT

-OR-TCs >1200*F o

ALL of the following conditions i

exist:

3. Heat sink-ALL SGs NR i

LEVEL (4% (34% POR

}

e Controlled RCS cooldown NOT ADVERSE CNMT) AND TOTAL in progress FEEDWATER FLOW <500 GPM

)

-AND AVAILABLE i

e RCS pressure - <1370 PSIG

{

-AND-

4. Integrity - DECREASE

]

High head SI pump flow indicator

>100*F IN LAST 60 MINUTES j

(1FI-917) >50 GPM flow or AND RCS COLD LEG (24;6*F SI pumps >100 GPM SI ACTUATION:

5. Containment - CNMT PRESSURE >50 PSIG Actuate SI and GO TO IBwEP-0, REACTOR TRIP OR SAFETY INJECTION, IF CST lei/El <20%.

4:M i

CONSIDER "HE" FO _LOWL WG:

Step 1, if:

o RCS subcooling - NOT ACCEPTABLE o Makeup from MUDS or PER ICONIC DISPLAY OR radwaste ATTACHMENT A.

o Prepare to isolate

-OR-secondary supply side o

PZR level - CANNOT BE MAINTAINED of 3 SGs

> 4% (38% FOR ADVERSE CNMT) o Crosstie unit's CST o

Reduce cooldown rate IF AUX F::D

)J4P DA" TAWK LEVEL o

< 50% TH.E WP E 1 :ORM

~HE ':0LLOWI:WG:

I: CST LEV:L <3%, " HEN PER:ORM TH E FOLLOWLNG:

Refill the day tank e

a. Verify secondary side of 3 SGs isolated
b. Switch AF suction to SX supply (00220/00020/041388)

APPROVED FEB1 1989 O*"=**.*.

L, REY. 1 REACTOR TRIP OR SAFETY INJECTION 1BWEP-0 WOG-1A UNIT 1 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED Step'39c (continued)

RH HX IB Cubicle (IPR 16J):

Grid 2 Beta IPA 216 Grid 2 Gas IPB116 CENT CHG Pump 1A Cubicle (IPR 17J):

f Grid 2 Beta IPA 217 Grid 2 Gas IPB117 CENT CHG Pump 1B Cubicle i

(IPR 18J)

Grid 2 Beta IPA 218 Grid 2 Gas IPB118

d. Grid 4 Aux Bldg area radiation monitors - LESS THAN ALERT ALARI(-SETPOINT l 40 CHECK PRT CONDITIONS:

Evaluate cause of abnormal conditions.

a. Pressure - LESS THAN 6 PSIG IF any PZR safety valve is
b. Level - LESS THAN 80%

determined to be the source of leakage into the PRT,

c. Temperature - LESS THAN 125'F THEN GO TO IBwEP-1, LOSS OF REACTOR OR SECONDARY COOLANT, Step 1.

e APPROVED FEB1 1989 E$sTw (0024Q/0002Q/040488)

_ = _ _

REV. l' OPERATOR ACTION

SUMMARY

1BWEP-F.0 WOG-1A FOR 1BWEP-0 SERIES PROCEDURES TRIP RCPS WWFN:

RED PATH

SUMMARY

.o

'CC water to RCP lost

1. Subcriticality - NUCLEAR (affacted pumps only)

POWER >5%

-oR-o Cnat Phase B' actuated

2. Core cooling - CORE EXIT

-OR-TCs >1200'F o

ALL of the folleving conditions exist:

3. Heat sink-ALL SGs NR LEVEL (4% (34% FOR e

Controlled RCS cooldown NOT ADVERSE Ct0tT) AND TOTAL in progress FEEDWATER FLOW <500 GPM

-AND AVAILABLE e

RCS pressure - <1370 PSIG

-AND-

4. Integrity - DECREASE High head SI pump flow indicator

>100*F IN LAST 60 MINUTES e

(1FI-917) >50 GPM flow or AND RCS COLD LEG <246*F SI pumps >100 GPM SI ACTUATION:

5. Containment - CistT PRESSURE >50 PSIG Actuate SI and GO TO 1BwEP-0, REACTOR TRIP OR SAFETY INJECTION, IF CST

_EV:

(201, N EN Step 1~,

if:

CONSIDE t 4 E FO LOWL 6:

o RCS,subcooling - NOT ACCEPTABLE o Makeup from MUDS or PER ICONIC DISPLAY OR radwaste ATTACHMENT A.

o Prepare to.isolete

-OR-secondary supply side o-PER level - CANNOT BE MAINTAINED of 3 SGs

> 4% (38% FOR ADVERSE CNMT) o Crosstie unit's CST 1

o Reduce cooldown rate

.o IF AUX ::::D

>MP BA" TAdK

_ EVE

< c4% T 4: dP E t :0RP

'HE

0L _0WI WG:

I : CST LEVEL <31.

  • 4EN P ER :ORM TH E FOLLOW:: WG:

Refill the day tank

a. Verify secondary side of 3 SGs isolated l'
b. Switch AF suction to SX o

supply (00220/0002Q/041388)

APPROVED FEB 1 1989

&==

REV. 1 REACTOR TRIP OR SAFETY INJECTION 1BWEP.

WOG-1A UNIT 1 i

STEP ACTION / EXPECTED RESPON5E RESPONSE NOT OBTAINED CAUTION Do NOT exceed DG loading requirements:.

o 5500 KW continuous duty 4 954 AMPS maximum o

5935 KW continuous for 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> 6 1030 AMPS maximum o

6050 KW continuous for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> S 1050 AMPS maximum.

CAUTION If possible, PZR heaters should be loaded on only one ESF bus at a time.

Additional NON-ESF loads should be loaded on the other ESF bus.

41 CHECK I: DIES E L 13ENERATORS SHOULD 3E STO))E3:

a. Verify ESF 4KV busses-ENERGIZED
a. Try to restore offsite BY OFFSITE POWER:

power to ESF busses.

SAT 142-1 Bus alive light -

IF offsite power can NOT e

LIT be restored, o

ACB 1412 - CLOSED THEN notify System Load SAT 142-2 Bus alive light -

Dispatcher of existing LIT conditions so an e

ACB 1422 - CLOSED emergency AC restoration program can be implemented.

Step continued on next page APPROVED FEB1 1989 MTYEw (0024Q/0002Q/040488)

A

REV. 1 OPERATOR ACTION

SUMMARY

1BWEP-F.0 WOG-1A FOR 1BWEP-0 SERIES PROCEDURES TRIP RCPS WHEN:

RFD PATH

SUMMARY

o CC water to RCP lost

1. Subcriticality - NUCLEAR (affected pumps only)

POWER >5%

-OR-o Comt Phase B actua,ted

2. Core cooling - CORE EXIT

-OR-TCs >1200*F o

ALL of the following conditions exist:

3. Heat sink-ALL SGs NR LEVEL <4% (34% POR e

Controlled RCS cooldown NOT ADVERSE CNMT) AND TOTAL in progress FEEDWATER FLOW (500 GPM

-AND AVAILABLE RCS pressure - (1370 PSIG e

-AND-

4. Integrity - DECREASE High head SI pump flow indicator

>IOo*F IN LAST 60 MINUTES (1FI-917) >50 GPM flow or AND RCS COLD LEG <246*F SI pumps >100 GPM SI ACTUATION:

5. Containment - CNMT PRESSURE >50 PSIG Actuate SI and GO TO 1BwEP-0, REACTOR TRIP OR SAFETY INJECTION, IF CST

_ EVE _ <20%, "H:EN Step 1, if:

CONSIDE R

'H E FOLLOWLNG:

o RCS subcooling - NOT ACCEPTABLE o Makeup from MUDS or PER ICONIC DISPLAY OR.

radwaste ATTACHMENT A, o

Prepare to isolate

-OR-secondary supply side o

PZR level - CANNOT BE MAINTAINED of 3 SGs

> 4% (38% FOR ADVERSE CNMT) o Crosstie unit's CST o Reduce cooldown rate

  • IF AUX FEED PUMP DA" TAW LEVEL

< 50% TH EN PE RFORM

~HE 0LLOWING:

IT CST LE'!lEL <3%. " HEN P ERl:0RM TH E FOLLOW':NG:

Refill the day tank

a. Verify secondary side of 3 SGs isolated
b. Switch AF suction to SX supply (0022Q/0002Q/041388)

APPROVgg FEB1

$89

=2 L*n*,**

i REV. 1 REACTOR TRIP OR SAFETY INJECTION 1BWEP-0 WOG-1A UNIT 1 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED step 41 (continued)-

b. NON-ESF 4 KV Busses:
b. IF offsite power can NOT be F

SAT 142-1 Bus alive-light -

~-

promptly restored, THEN establish necessary LIT NON-ESF loads to maintain ACB 1432 - CLOSED plant conditions.

SAT 142-2 Bus alive light -

LIT

1) Verify locally all ACB 1442 - CLOSED breakers on Bus 143 and 144 OPEN.
2) Placs all non-running WS pumps in PULL OUT position.
3) Roset SI recirc sump valves:'

ISI8811A 18I8811B

~

4) Energize Bus 143 and 144 from ESF crosstie breakers.
5) Open all 480 volt transformer LOW side breakers associated with Bus 143 and 144.
6) Reenergize PZR heaters:

a) Close 4160 volt PZR heater transformer *s HIGH side breakers at IPM01J.

b) Close 480 volt PZR heater transformer's LOW side breakers at IPM0$J.

Step continued on next page APPROVED (0024Q/0002Q/040488)

M$sYmw

REV. 1 OPERATOR ACTION

SUMMARY

1BWEP-F.0 WOG-1A FOR 1BWEP-0 SERIES PROCEDURES TRIP RCPS WHFW:

RFD PATH

SUMMARY

o CC water to _RCP lost

1. Subcriticality - NUCLEAR (affocted pumps only)

POWER >5%

-OR-o Cnet Phase B actuated

2. Core cooling - CORE EXIT

-OR-TCs >1200*F o

ALL of the following conditions exist:

3. Heat sink-ALL SGs NR LEVEL <4% (34% POR Controlled RCS cooldown NOT ADVERSE CNMT) AND TOTAL in progress FEEDWATER FLOW (500 GPM

-AND AVAILABLE RCS pressure - <1370 PSIG

-AND-

4. Integrity - DECREASE High head SI pump flow indicator

>100*F IN LAST 60 MINUTES (1FI-917) >50 GPM flow or AND RCS COLD LEG <246*F SI pumps >100 GPM SI ACTUATION:

5. Containment - CNKT PRESSURE >50 PSIG Actuate SI and GO TO IBwEP-0, REACTOR TRIP OR SAFETY INJECTION, IF CST

_EifE _ (20%, "4 EN Step 1, if:

C.ONSIDEt "HE FOtLOW"d3:

o RCS subcooling'- NOT ACCEPTABLE o Makeup from MUDS or PER ICONIC DISPLAY OR radwaste ATTACHMENT A.

o Prepare to, isolate

-OR- -

secondary supply side o

PZR level - CANNOT BE MAINTAINED of 3 SGs

> 4% (38% FOR ADVERSE CNMT) o Crosstie unit's CST o

Reduce cooldown rate o IF AUX F

D )J 4P DA" TA R EEVE L

< SOE TH : dPE R :0RM

'HE

0LLOWI WG I':

'ST LEVEL <3%,

'H EN P ER :0RM THE FOLLOW::N 3:

Refill the day tank

a. Verify secondary side of 3 SGs isolated
b. Switch AF suction to SX l

supply 1

1 1

l l

I (0022Q/0002Q/041388)

)

APPROVID.

3 i

FEB1 1989

~

)

1

)

REY. 1 REACTOR TRIP OR SAFETY INJECTION 1BWEP-0 WOG-1A UNIT 1 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED i

Step 41b (continued) c) Operate PER heater controls at necessary to control system pressure.

7) Start a WS pump per BwOP WS-1, STARTUP AND OPERATION OF WS SYSTEM, J

if necessary.

8} Start a SAC per BwOP SA-1, STARTUP AND OPERATION OF THE SAC's.

9) Energize other NON-ESF loads as necessary,
c. Stop any unloaded DG and place in standby per BwCP DG-12, DIFSEL GENERATOR SHUTDOWN.

42 RETURN TO STEP 25

-END-APPROVLC FEB1 1989 oYUrE$ sew Page 31 of 33 (0024Q/0002Q/040488) m

[,

~~

REV. 1 OPERATOR ACTION

SUMMARY

1BWEP-F.0 WOG-1A FOR 1BWEP-0 SERIES' PROCEDURES

' TRIP RCPE WWFM:

RFD PATH

SUMMARY

j

.o CC water to JtCP lost

1. Suberiticality - NUCLEAR (affocted pumps only)

PONER >5%

--OR-o Comt Phase B actuated

2. Core cooling - CORE EXIT

-OR.

TCs >1200*F o

E 'of the following conditions exist:

3. Heat sink-ALL SGs NR LEVEL <4% (34% FOR Controlled RCS cooldown M ADVERSE CNMT) AND TOTAL e

in progress FEEDWATER FLOW (500 GPM

-AND AVAILABLE RCS pressure - (1370 PSIG e:

-AND-

4. Integrity

. DEMEME High head SI pump flow indicator

>100*F IN LAST 60 MINU'QIS e

(1FI-917) >50 GPM flow or AND RCS COLD LEO (246'd _

SI pumps >100 GPM SI ACTUATION:.

5. Containment - CNMT PRESSURE >50 PSIG

~_

Actuatie SI and GO TO IBwEP-0, REACTOR TRIP OR SAFETY INJECTION, IF CST

_Et/E _ dM. "

EN I.

Step 1, if:

CONSIDE t

'M E F0

_0WL n 3:

.o RCS subcooling - NOT ACCEPTABLE o Makeup from MUDS or PER ICONIC DISPLAY OR radwaste ATTACHMENT A.

o Prepare to isolate

-OR-secondary supply side o

PER level - CANNOT BE MAINTAINED of 3 SGs

> 4% (38% FOR ADVERSE CNMT) o Crosstie unit's CST o

Reduce cooldown rate a IF A'JY

D ).11P 3A" TA4M

_ EVE y

( 50'1T 4 E dP E t :0R '

'HE

0LuoWI dG: Jf I : 'ST LEVEL <31. ""EN PER:0RM THE FOLLOWL i 3:

Refill the day tank e

a. Verify secondary side of 3 SGs isolated
b. Switch AF suction to SX supply (00220/00020/041388)

APPROVED.

FEB1 1989 eEll."e.*.*.*.

REY. 1 REACTOR TRIP OR SAFETY INJECTION 1BWEP-0 I

WOG-1A UNIT 1

)

CNORMAL) 200 300 400 500 600 700 2600

'260,0 3.

2500

[ [ [

2500 2400

[ [ f 2400 2300

) f j 2300 2200

// /

2200 2100

[ / [

2100 2000

,[ f j 2000 m

(.D 1900 f / /

19 0 0 C)

H w

,f 'r f

1800 H 1800 nCCEPTABLE J

9 1700 l

[,[ [

1700 a

g g

v 1600

/ /./

1600 v 1500 J f

/

1500 1400 1400 J 1300

// /

1300 J C 1200

/,# r/

1200 W W

ri O

1100

, 7 1102 g

~

g 2

1000

~

j/ [

- 1000 2 g

1 900

// /

900 0-D EkBE r >

/

8 NOT B00 800 C

T I

/ /

J ACCEPTABLE.

W g

U 700 j// /

700 U

M 600 j,

p f

600 k

500 j,

500 4OO g

f4 SATURATION 400 300 -

f

-J-300 NORMAL UP

/

200 --- - C NMT 200 100 100 1

200 300 400 500 600 700 TEMPERATURE C

F3 APPROVED FIGURE IBWEP 0-1 RCS SUBC00 LING MARGIN

gegoof, Page 32 of 33 (0024Q/0002Q/040488)

- REV. -1 OPERATOR ACTION

SUMMARY

1BWEP-F.0

~ t

'WOG-1A

.FOR 1BWEP-0 SERIES PROCEDURES S

TRIP RCPS WHEN:

RFD PATH

SUMMARY

o CC water to RCP lost

1. Suberiticality - NUCLEAR (affocted pumps only)

POWER >5%

' OR-o Cnet Phase B actuated

2. Core cooling - CORE EXIT

-OR-TCs >1200*F o

ALL of the following conditions exist:

3. Heat sink-ALL SGs NR LEVELc4% (34% FOR e

Controlled RCS cooldown NOT ADVERSE CNMT) AND TOTAL in progress FEEDWATER FLON <500 GPM

-AND AVAILABLE e

RCS pressure - <1370 PSIG

-AND-

4. Integrity DECREASE High head SI pump flow indicator

>100*F IN LAST 60 MINUTES e

(1FI-917) >50 GPM flow or AND RCS COLD LEO (246*F SI pumps >100 GPM SI ACTUATION:

5. Containment - CNMT PRES $URE >50 PSIG Actuate SI and GO TO IBwEP-0, REACTOR TRIP OR SAFETY INJECTION, IF CST

_ pre _ <20%

"4 EN Step 1, if:

CONSIDE t 4 E-F010WE W 3:

o RCS subcooling - NOT ACCEPTABLE o Makeup from MUDS or PER ICONIC DISPLAY OR radwaste ATTACHMENT A.

o Prepare to isolate

-OR-secondary supply side o

PER level ' CANNOT BE MAINTAINED of 3 SGs

> 4% (38% FGk ADVERSE CNMT) o Crosstie unit's CST o Reduce cooldown rate a IF AUX F ::D

> J4P BA" TA WK

_ EVE

< 50% TH E dP E t:ORP'

'HE

0L_0WIdG1 I: CST LEVEL <31. "4 EN PER:0RM TH E FOLLOWL W.3:

Refill the day tank e

l

a. Verify secondary side of 3 SGs isolated
b. Switch AF suction to SX supply l

l (0022Q/0002Q/041388)

APPROVID FE81 1989 M*W,*.*.

REV. 1 REACTOR TRIP OR SAFETY INJECTION 1BWEP-0 WOG-1A UNIT 1 l

ATTACHMENT A A.

Determination of Post-Accident RCS Subcooling:

1. Check.Cnmt for ADVERSE conditions: - - -

o Cnmt pressure greater than 5 PSIG.

-OR-5 o Cnmt radiation greater than 10 R/hr:

e IRT-AR020 Grid 4 4AS120 e

IRT-AR021 Grid 4 4AS121

2. Check RCS pressure on wide range pressure instruments (1PI-403A/405).
3. Determine temperature for RCS pressure using NORMAL or ADVERSE Cnmt curves per Figure IBwEP 0-1.
4. Check average of ten highest core exit TCs from MCB indicators (ITI-IT001/IT002).

'5. If average of ten highest core exit TCs less than temperature for RCS pressure, then acceptable subcooling exists.

ARPROVED.

FEB1 1989 fe!%#f.

(0024Q/0002Q/040488)

REV. l' OPERATOR ACTION

SUMMARY

1BWEP-F.0 WOG-1A FOR 1BWEP-0 SERIES PROCEDURES TRIP RCPS WWFN:

RED PATH

SUMMARY

ol CC water to RCP lost

-1. Subcriticality.- NUCLEAR

-(affected pumps only)

POWER >5%

.-OR-o Cnet Phase B actuated

2. Core cooling -' CORE EXIT

-OR--

TCs >1200*F o

ALL of the following conditions exist:

3. Heat sink-ALL SGs NR LEVEL (4% (34% FOR-e Controlled RCS cooldown NOT ADVERSE CIEW) AND TOTAL in progress FEEDNATER F:Di <500 GPM

-AND AVAILABLE-e RCS pressure - <1370 PSIG

-ANP-

4. Integrity - DECREASE High head SI pump flow indicator

>100*F IN LAST 60 MINUTES o

(1FI-917).>50 GPM flow or AND RCS COLD LEG (246*F SI pumps >100 GPM I

SI ACTUATION:

5., Containment - CNMT j

DRE88URE >50 PSIG t

Actuate SI and GO TO 19wEP-0, l

l REACTOR TRIP OR SAFETY INJECTION, IF CST

_ EVE - (20L "CEN Step 1, if:

CONSIDE t" 4 E FO tOWL vi:

o

.RCS subcooling - NOT ACCRPTABLE o Makeup from MUD 8 or PER ICONIC DISPLAY OR radwaste ATTACHMENT A.

o Prepare to isolate secondary supply side

-OR-o PER level - CANNOT BE MAINTAINED of 3 SGs

> 4% (38% FOR ADVERSE CNMT) o Crosstie unit's CST l

o Reduce cooldown rate a IF AUX :F:D )J 4P ?A" TA M LEVE l

< SOE T 4E dP E t :0R '

'HE

0L 10WI dG:

I: CST LEVEL (3L "1EN P ER :0RM TH E FOLLOWL 4 3:

)

e Refill the day tank l

a. Verify secondary side l

of 3 SGs isolated

b. Switch AF suction to SX supply (00220/0002Q/041388)

A99 ROVED FEB 1 1989 23.***.*.*.

I L

3 l

~

..

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