ML20247M874

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Rev 1 to 2BEP-0, Reactor Trip or Injection Unit 2
ML20247M874
Person / Time
Site: Byron, 05000000
Issue date: 02/01/1989
From:
COMMONWEALTH EDISON CO.
To:
Shared Package
ML20247M747 List:
References
2BEP, 2BEP-0, NUDOCS 8908020243
Download: ML20247M874 (33)
v • d • e


Text

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, ATTACHMENT 15 REV. 1 REACTOR TRIP OR SAFETY INJECTION 2BEP-0 WOG-1A UNIT 2 A. PURPOSE NV - ' N F01V A~ OOLY Thi's 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 rece ery 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 change in 2 seconds o Power range negative rate 1 5% power change in 2 seconds o Overtemperature Delta T 1 116.4% i penalties o Overpower Delta T 1 107.2% - penalties o High PZR 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 < 5268 volts o Turbine trip emergency trip header i 540 psig oil pressure or Turbine stop valves shut o SI manual actuation o containment high pressure SI > 3.4 psig o Low PZR pressure SI i 1829 psIg o Low steamline pressure SI i 640 psig (rate sensitive) o Steen Generator water level low-low 1 17% of narrow range span

2) The following are symptoms of a reactor trip:

o Any Reactor Trip first out annunciator lit.

o Rapid decrease in neutron level indicated by nuclear instrumentation.

APPROVED Step continued on next page FEB 011989 B. o. s. R.

Page 1 of 33 IO331E/0027E/050288) 8908020243 890727 ADOCK0500gg{4 E___.-.-----gDR

^

, e ',

n REV. 1 ~ REACTOR TRIP OR SAFETY INJECTION ~2BEP-0 WOG-1A UNIT 2 l

-Step B 2) (continued)  !"*0]R r I N E, <'

o N11shutdownandcontrolrodsfullyinsertedandrodbottom lights lit.

o Rapid decrease in Unit load to zero power.

3)ThelfollowingmaybesymptomsthatrequireaReactorTripand Safety Injection, if one has not occurred:

o Low PZR pressure i 1829 psig.

o Low steamline pressure 1 640 psig (rate sensitive) o Containment high pressure 1 3.4 psig

4) The following may be symptoms of a Reactor Trip and Safety Injections o Any SI first out annunciator lit.

o All Group 2 cold leg injection monitor lights lit.

o ESF equipment actuated.

o SI actuated BYPASS-PERMISSIVE light lit.

5) This procedure may also be entered from:

o 2BEP ES-0.1, REACTOR TRIP RESPONSE, Step 7, when PZR pressure i 1829 psig.

APPROVED FEB 011989 B.O.S.R.

Page 2 of 33 (0331E/0027E/050288)

9 L

  • REV. 1 REACTOR TRIP OR SAFETY INJECTION 2BEP WOG-1A UNIT 2 f STEP ACTION / EXPECTED RESPON5E RE5FONSE NOT 06TAitiED rnRf1All ON W._Y

^

CAUTION g

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

          • easemanneneanneenemannee*****menee.

NOTE

  • ' With this procedure in effect,
  • notify the Station Director who will*
  • evaluate for GSEP conditions per *
  • BZP 200-A1, BYRON EMERGENCY. ACTION *
  • LEVELS.

e ***mene*** ..neamene.*********e*******

    • eemen*eemen. ***eeneesseeeeeeeeeeee**

e e NOTE

  • Steps 1 through 15 are IMMEDIATE
  • ACTION steps.

ene***********eeeeeeneseemanneeeeeaneeen essene**eemanneenemeeneeseeneeeemeneen*e NOTE

  • " Adverse Containment" as used in *
  • Byron Emergency Procedures is
  • defined as:
  • o Containment pressure GREATER
  • APPROVED
  • --OR-
  • o Contaiment radiation level
  • FEB 011989
  • GREATER THAN 105 R/HR.
  • B.O.S.R. *
  • enemenemannenamenemmenene.....me ** ..e l1l VERIFY REACTOR TRIP: Manually trip the Reactor.
  • Rod bottom lights - LIT IF the Reactor will NOT trip, e Reactor trip and bypass THEN GO TO 2BFR-S.1, breakers - OPEN RESPONSE TO NUCLEAR POWER
  • Neutron flux - DECREASING GENERATION /ATWS, Step 1.

Page 3 of 33 (0331E/0027E/050288)

L l

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I. REV. 1 REACTOR TRIP OR SAFETY INJECTION 2BEP-0 l WOG-1A UNIT 2 1

STEP' ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 1

1 12l YERIFY TURBINE TRIP: Perform the following:

  • All Turbine throttle stop 1) Manually trip the turbine valves - CLOSED 2) H turbine will NOT trip, i e 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 0 GOV LWR simultaneously.

0 E turbine can NOT be run F.0

\ back, THEN place EH pumps in PULL OUT position.

IF Turbine still will NOT Eip, THEN manually initiate.

Main Steamline Isolation and manually close MSIV bypass valves.

l3] VERIFY POWER TO 4KV ESF EUSSES:

a. ESF busses - AT LEAST ONE a. Try to restore power to at ENERGIZED: least one ESF bus 4 o Bus 241 alive light - IF_ power can NOT be LIT restored to at least one

-OR- ESF bus, o Bus 242 alive light - THEN GO TO 2BCA-0.0, LIT LOSS OF ALL AC POWER, Step 1.

b. ESF busses - ALL ENERGIZED: b. Try to restore power to deenergized ESF bus while e Bus 241 alive light - LIT continuing with this

-AND- procedure.

  • Bus 242 alive light - LIT APPROVED FEB 011989 B.O.S.R.

(0331E/0027E/050288)

.. ' ' -;; t ",.

REV. 1 REACTOR TRIP OR SAFETY INJECTION 2BEP-0 WOG-1A UNIT 2 STEP li ACTION / EXPECTED RESPONSE i RESPONSE NOT OBTAINED t

i l5l CHECK IE SI ACTUATED: Check if SI required:

e Any SI first out o PZR pressure less than annunciator - LIT 1829 PSIG.

  • Group 2 Cold Leg -OR-Tr#ction monitor lights o Steamline pressure less

- LIT than 640 PSIG.

-OR-o Containment pressure greater than 3.4 PSIG.

IE SI required, THEN manually actuate.

IF SI NOT required, TiiEN GD TO 2BEP ES-0.1, REACTOR TRIP RESPONSE, Step 1.

FOR W ORY F ON CE

  • =,

l i

1 APPROVED q FEB 011989 B.O.S.R.

(0331E/0027E/050288) ]

l i l

3

REV. 1 REACTOR TRIP OR SAFETY INJECTION 2BEP-0 WOG-1A- UNIT 2

, i STEP ACTION / EXPECTED RESPONSE RESPONSE NQLO@JAINED ni

~

I

'[' bi I lil VERIFY FW ISOLATION:

, !h k 1 il Iy l t i I

a.-FW pumps-DIPPED: a. Manually trip pumps.

e N PUMPS TRIP alarms - LIT

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

- CLOSED:

e 2FWOO2A

  • 2FWOO2B e 2FWOO2C
c. FW reg valves - CLOSED: c. Manually close FW reg .

valves, e 2FW510

  • 2FW520 IF any valve will NOT
  • 2FW530 close, e 2FW540 THEN close its associated FW shutoff valve; o 2FWOO6A o 2FWOO6B o 2FWOO6C o 2FWOO6D
d. FW reg byp valvos - CLOSED: d. Manually close valves.

e 2FW510A e 2FW520A

  • 2FW530A
  • 2FW540A
e. FW isol valves - CLOSED: e. Manually close valves.
  • 2FWOO9A
  • 2FWOO9B
  • 2FWOO9C
  • 2FWOO9D Step continued on next page APPROVED FEB 011989 B.O.S.R.

(0331E/0027E/050288)

REV. 1 REACTOR TRIP OR SAFETY INJECTION 2BEP-0 WOG-1A UNIT 2 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED Step 5 (continued)  !

f. EW 'temprng flow cont valves - f. Manually close' valves.

CLOSED:

  • 2FWO34A
  • 29WO34B
  • 2EWO34C
  • 2FWO34D
g. EW temprng isol valves - g. Manually close valves.

CLOSED:

  • 2EWO35A
  • 2EWO35B
  • 2EWO35C

.* 2EWO35D

h. EW prehtr byp isol valves - h. Manually close valves.

CLOSED:

1 e 2EWO39A

  • 2EWO39B
  • 2FWO39C
  • 2FWO39D
i. FWIV byp isol valves - 1. Manually close valves.

CLOSED:

  • 2FWO43A
  • 2FWO43B e 2EWO43C
  • 2FWO43D APPROVED ffB 011989
s. o. S. R.

(0331E/0027E/050288)

i 5 a -

,g )

l i

REV. 1 REACTOR TRIP OR SAFETY INJECTION 2BEP-0 l WOG-1A UNIT 2 l l

STEP ACTION / EXPECTED RESPON5E RESPONSE NOT OBTAINED j k "

lEl VERIFY ECCS PUMPS RUNNING: Manually start pumps.

e CENT CHG pumps run lights - I e SI pumps run lights - LIT [i u.

. RH pumps run lights - 1IT

/

11] VERIFY CONTAINMENT ISOLATION PHASE A:

a. Cnmt Phase A valves - CLOSED: a. Manually actuate Cnmt Isol Phase A and verify e Group 3 Cnmt Isol valves closed.

monitor lights - LIT lHl YERIF" CONTAINMENT VENTILATION ISOLA" ION:

a. Cnmt Vent Isol valves - CLOSED: a. Manually close valves.

e Group 6 Cnmt Vent Isol monitor lights - LIT l5l VERIFY AF PUMPS RUNNING:

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

lElV MIFY RCFCs RUNNING IN..LlW SliED:

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

lHl VERIFY CC PUMPS RUNNING:

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

lHl VERIFY SX PUMPS RUNNING:

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

APPROVED FEB01i969 B.O.S.R.

Page 8 of 33 i (0331E/0027E/050288)

.,,+ , ,

REV. 1 REACTOR TRIP OR SAFETY INJECTION 2BEP-0 WOG-1A UNIT 2 STEP ACTION / EXPECTED RESPONSE PESPONSE NOT OBTAINED lU]C4ECK IF MAIN STEAMLINES_SHOULD 3E ISOLATE ):

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

following conditions:_

o ANY STEAMLINE PRESSURE LESS THAh OR' EQUAL To_640 PSIG

-OR-o CONTAINMENT PRESSURE GREATER THAN 8.2 PSIG (2PI-CS93f_

THRU 2PI-CS937) b.. Verify Main-Steamline Isolation: b. Manually initiate Main Steamline Isolation and

  • MSIVs CLOSED manually close MSIV bypass e MSIV bypass valves - CLOSED valves.

lEl VERIFY CONTAINMENT SPRAY NOT REQUIRE )'

a..Cnmt pressuro - HAS a. Perform the following:

REMAINED LESS THAN 20 PSIG, (2PI-CS934 THRU 2PI-CS937, or 1) Verify Containment recorder 2PR-937) Spray actuated.

I_F NOT, THEN manually actuate.

2) Verify Cnmt Isol Phase B valves closed:
  • All Group 6 Phase B isol monitor lights LIT.

IF NOT, THEN manually close valves.

3) Stop all RCPs.

1 APPROVED ,

FEB 011989 B.O.S.R.

(0331E/0027E/050288) w-________-_______-__ -

f,. ,.

REV. 1 REACTOR TRIP OR SAFETY INJECTION 2BEP-0 WOG-1A UNIT 2 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OSTAINED

l. l15l VERIFY DIESEL GENERATORS RUNNING:
a. DGs run lights - LIT a. Manually start DGs.

IF DGs can NOT be started manually, THEN locally start per 2 BOA ELEC-3, LOCAL EMERGENCY START OF A DIESEL GENERATOR.

15 ANNOUNCE CONDITION OVER ) AGE, I UNIT 2 REACTOR TRIP - SA ETY INJECTIDN /

,r 17 YERIFY GENERA"OR TRIP '

4 30 SECON3S A4"ER TURBINE TRIP:

a. Unit 2 Main Transformer feed to a. Manually open breakers 345KV Swyd breakers-OPEN: as necessary:
  • ACB 10-11 o ACB 10-11
  • OCB 11-12 o OCB 11-12
b. PMG output breaker - b. Manually open PMG output OPER: ,

breake3

  • 41 Brkr
c. Generator lockout relay trip alarm - LIT APPROVED FEB 011989 B.O.S.R.

Page 10 of 33 (0331E/0027E/050288)

1 REV. 1 REACTOR TRIP OR' SAFETY INJECTION 2BEP-0 WOG-1A- UNIT 2 STEP ACTION / EXPECTED RESPONSE RESPONCE NOT OBTAINED 18 VERIFY ECCS FLOW:

a. High head SI pump flow a'. Manually start CENT CHG indicator (2FI-917) - pumps and align valves as GREATER THAN 50 GPM necessary.
b. RCS pressure (2PI-403A/405) - b. Go TO Step 19.

LESS THAN 1590 PSIG

c. SI pumps discharge flow c. Manually start SI pumps and indicators (2FI-918/922) - align valves as necessary.

GREATER THAN 100 GPM

d. RCS pressure (2PI-403A/405) - d. GO TO Step 19.

LESS THAN 300 PSIG

e. RH pumps discharge flow e. Manually start RH pumps and indicators (2FI-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

~

\

APPROVED

\

FEB 011989 B.O.S.R.

Page 11 of 33 (0331E/0027E/050288)

..p'. ,

REV. l' REACTOR TRIP.OR SAFETY INJECTION 2BEP-0 WOG-1A UNIT 2.

STEP' ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION AF flow must remain GREATER THAN 500 GPM until water level.is GREATER THAN 4% (34% FOR ADVERSE CNMT) for any SG narrow range indication.

20 VERIFY TOTAL AF FLOW:

a. AF flow - GREATER THAN 500 GPM a. IF EG narrow range level AVAILABLE H 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 established greater than 500 GPM, THEN GD TO 2BFR-H.1, R"SPONSE TO LOSS OF SECONDARY HEAT SINK, Step 1.

FOR FORMATON OLY APPROVED FEB 011989 ,

B.O.S.R.

(0331E/0027E/050288)

p REV. 1 REACTOR TRIP OR SAFETY INJECTION 2BEP-0 WOG-1A UNIT 2 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED 21 VERIFY AF VALVE ALIGNMENT:

a. AF isol valves - OPEN: a. Manually OPEN valves.
  • 2AF013A e 2AF013B
  • 2AF013C e 2AF013D e 2AF013E e 2AF013F
  • 2AF013G
  • 2AF013P-
b. AF flow control valves - b. Manually throttle valves THROTTLED OPEN: OPEN.

e 2AF005A

  • 2AF005B e 2AF005C e 2AF005D e 2AF005E
  • 2AF005F
  • 2AF005G e 2AF005H

[ 9 j I E ' ~ O D Ti s M ' f A r t 1 t  !!WUfW!!/it(Ujijr,,)[\f]

APPROVED FEB 011989 B.O.S.R.

(0331E/0027E/050288)

REV. 1 REACTOR TRIP OR SAFETY INJECTION 2BEP-0 WOG-1A UNIT 2 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED CAUTION If a radioactive release to the atmosphere occurs, then Control Room Offices vent fans, OVV01CA and OVV01CB should be verified tripped at panel OVV01J.

22 VERMFY CONTR0_ ROOM VENTILATION SYS"EM ALIGNE1 FOR EM:ERGENCY (*, Ou' OPERATION: w. [u . {fw. ,-

a. Control Room chillers run a. Manually start chiller for lights - LIT: VC train in operation.
  • Train A - MCR CHLR OA
  • 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- OPES

-OR- o OVC32Y/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 OA and

  • Return fan

-OR-

  • 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- APPROVED j o Train B OVC44Y - CLOSED FEB 0 1 989 Step continued on next page B.O.S.R.

1 Page 14 of 33 (0331E/0027E/0E0288)

l t

  • REV. 1 REACTOR TRIP OR SAFETY INJECTION 2BEP-0 WOG-1A UNIT 2 STEP ACTION / EXPECTED RE5?ON5E RESFONSE NOT OBTAiNED

.. Step 22 (continued)

e. Control Room pressure - GREATER e. Refer to BOP VC-14, MAIN THAN +0.125" H90, (MCR/TB CONTROL ROGM PRESSURE LOW, DP, OPDI-VC038) while' continuing with this procedure. _

'*2.

201 \ 0lVA~0\ ON_Y APPROVED EEB 01.1989 B.O.S.R.

Page 15 of 33 (0331E/0027E/050288)

3 ..

-REV. l' ' REACTOR TRIP OR SAFETY INJECTION 2BEP-0 WOG-1A UNIT 2 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED ne*******mene****me*******nnan**********

a a NOTE Only one Aux Bldg Charcoal Booster

  • Fan should be started in each
  • non-accessible area exhaust filter *
  • plenur.s. Only two plenums can be *
  • used at any one time. *
      • ...... ** . **n.. **..*** *e *****.

23 VER?FY AUX BL3G VENTILATION SYS"EM ALIGNF ) FOR EMERGENCY OPERATION:

a. Two non-accessible AB Charcoal a. Start non-accessible Booster Fans run lights - LIT: AB Charcoal Booster Fans.as necessary per BOP VA-5, o OVA 03CA or OVA 03CB for Plenuin A AUX BLDG CHARCOAL BOOSTER o 0VA03CC or OVA 03CD for Plenum B FAN OPERATION.

o .0VA03CE or OVA 03CF for Plenum C annemmenenammeenman***mmanes**** mane *****

NOTE Only one Fuel Bldg Charcoal Booster *

  • Fan should be run at a time. *
            • .. ****** ........... ...=*******.

24 VER :Y FUEL 3LDG VENTI _ATION SYS";EM ALIGN ED FOR EMERGENCY OPERATION:

a. Train A or Train B Fuel a. Start Train A or B Bldg Charcoal Booster Charcoal Booster Fan Fan run light - LIT: per BOP VA-6, FUEL HANDLING BLDG CHARCOAL i o FHB Booster Fan OA BOOSTER FAN OPERATION.
  • OVA 04CA

-OR- F0.1 \ ~0RViK~0,\ 0EY o FHB Booster Fan OB pp e OVA 04CB FEB 011989 B.O.S.R.

(0331E/0027E/050288)

  • [ .... -

REV.=1 REACTOR TRIP OR SAFETY INJECTION 2BEP-0 WOG-1A UNIT 2 STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OSTAINED 25 CHECK RCS AVERAGE' TEMPERATURE:

a. RCS' average temperature - a. IF_ RCS temperature less STABLE AT OR TRENDING TO 557'F than 557'F and decreasing, THEN:
1) Stop dumping steam.
2) IF;cooldown continues, THEN maintain total feed flow greater,than 500 GPM until SG narrow range level. greater than 4% (34% FOR ADVERSE CNMT) in at least one SG.
3) Il cooldown continues, THEN shutdown unnecessary main steam-loads,
4) H cooldown continues, THEN close.MSIV and MSIV bypass valves.

H RCS temperature greater than 557*F and increasing,-

THEN dump steam to condenser:

1) Check condenser available.
2) Place MS header pressure controller in MANUAL and reduce

' - ' " ' " * * " * ' ' =-

m' T O U A7 01 0 T_Y 3) Place steam dumps mode selector switch in STEAM PRESSURE mode.

Step continued on next page APPROVED FEB 011989 B.O.S.R.

(0331E/0027E/050288)

f,2 1,7 v ,

x y- , REV.-1 REACTOR TRIP OR SAFETY INJECTION 2BEP-0

.. WOG-1A" UNIT 2 3 .

e n STEP ACTION / EXPECTED RES?ON5E RESPONSE NOT OBTAiNED cs ,

Step 25a (continued).

~

.'4) Adjust MS header

. pressure controller to

' initiate cocidown. rate less than' 50 *'F/Hr .

E unable to dump. steam to a s.

condenser,

' THEN dump' steam using SG PORVs.

26 CHECK PZR PQRVS AND SPRAY VALVES:

a.-PORVs'- CLOSED: -

a. H PSR pressure less- ,

than 2315 PSIG, THEN manually close' ]

  • 2RY455A'.  ;
  • 2RY456 PORVs. .l H any PORV can NOT be closed, TdEN manually'close Its isol valve:

o -2RY8000A (2RY455A) j

o. 2RY8000B (2RY456) l 1

r -

... g ,, IF PORV isol valve. can 1 1-lI l l L l NOT be closed, L - 0 i .an .

u - TiffN Go TO '2BEP-1, LOSS OF REACTOR'OR SECONDARY COOLANT, Step 1 1.

b. Normal PZR spray valves - b. E PZR pressure less j CI4 SED: than 1260 PSIG, ,

THEN manually close valves: '

  • 2RY45SB -
  • 2KY455C o E spray valve 2RY455B-a can NOT be closed, i THEN stop RCP 2D.

L APPROVED o H spray valve 2RY455C l l- . can NOT be closed, 1 THEN stop RCP 2C.

MB 011989

'B.O.S.R.

1 (0331E/0027E/050288) i L.-_-_ --._-____._--__-.m

i

. A f '*} , j# i,

. . . , 9 _ .: ,

j

~"

REV. 1- ' REACTOR TRIP OR SAFETY INJECTION .2BEP-0 yQ '

~WOG-1A- UNIT.2 1

j u STEP ACTION / EXPECTED RES?ON5E RE5FONSE NOT OBTAiNED CAUTION Seal injection must be maintained to all RCPs to prevent seal damage due to overheating.

F 27 CHECK IF RCPS SHOULD BE STOPPED:

4

a. ECCS flow; a. GO TO Step 28.

o High head SI flow indicator-(2FI-917) -

GREATER THAN 50 GPM

-OR-o -Any SI pump discharge

. flow (2FI-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 available.

2) Place MS header oressure controller in SANUAL and reduce demand signal to zero.
3) Place steam-dumps mode selector switch in STEAM PRESSURE mode.
4) Adjust MS header pressure controller to

$ .- n -- m 1 m 1 maintain desired RCS temperature.

u v u _

pc APPROVED FEB 011989 s.o.S.R-Page 19 of 33 (0331E/0027E/050288)

.REV. 1 REACTOR TRIP OR SAFETY INJECTION 2BEP-0 WOG-1A UNIT 2

\

iTEP-l ACTION / EXPECTED RESPONSE RE5PONSE NOT OSTAiNED 28 GECK IF SG(s) SECONDARY PRESSURE BOUNDARIES ARE INTACT:

a. Check pressures in all SGs: a. GO TO 2BEP-2, FAULTED STEAM GENERATOR ISOLATION, l o NO SG PRESSURE DECREASING Step 1.

IN AN UNCONTROLLED MANNER l o NO SG COMPLETELY DEPRESSURIZED 2S CHECK IF SG TUBES ARE INTACT: GO TO 2EEP-3, STEAM GENERATOR TUBE RUPTURE, l 0 SJAE/ Gland Steam Exhaust Gas Step 1.

radiation - LESS THAN ALERT ALARM SETPOINT:

  • 2PR27J Grid 1 2PS127 l o SG Blowdown Liquid radiation -

LESS THAN ALERT ALARM SETPOINT:

  • 2PR08J Grid 1 2PS108 o Main Steamline radiation -

l LESS THAN ALERT ALARM SETPOINT:

e Main Steamline 2A, MSIV Rm:

e 2RT-AR022 Grid 1 5AA122

o Main Steamline 2B, MSIV Rm:

Page 20 of 33 (0331E/0027E/050288)

c ..;-

( ,

REV.1: REACTOR TRIP OR SAFETY INJECTION 2BEP-0 WOG-1A' UNIT 2' STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED h 30 CHECK IF RCS IS INTACI: Go TO 2BEP-1, LOSS OF REACTOR OR SECONDARY COOLANT, Step 1.

l .o'. Cnet radiation monitors - LESS THAN ALERT ALARM SET?OINTS:

e Cnmt area monitors:

e 2RT-AR014 Grid 4 5AS101 e 2RT-AR014 Grid 4 5AS202 1 e 2RT-AR014 Grid 4 5AS303 e 2RT-AR011 Grid 4 5AS111 e 2RT-AR012 Grid 4'5AS112 e 2RT-AR020 Grid 4 5AS120 e 2RT-AR021 Grid 4 5AS121 l o Cnmt pressure - LES,_SSTHAN 3.4 PSIG o Cnmt recirc sump levels - NORMAL:

e Cnmt sump levels indicator lights - NOT LIT:

b e 2LL-SIO75A e 2LL-SIO75B APPROVED FEB 011989 B. O. S. R.

1 Page 21 of 33 (0331E/0027E/050288)

V:.-

1 REV. 1 REACTOR TRIP OR SAFETY INJECTION 2BEP-0 WOG-1A UNIT 2 STEP ACTION / EXPECTED RESPON5E [ RESPONSE NOT OBTAiNED 31 CHECK IF ECCS FLOW SFAULD BE TERMINATED:

a. Check RCS subcooling a. DO NOT STOP ECCS pumps.

ACCEPTABLE per: GO T6' Step 33.

o ICONIC DISPLAY  ;

-OR- -

o ATTACHMEh"f A

b. Secondary heat sink: b. IF neither condition satisfied, o Total feed flow to SGs - THEN DO NOT STOP ECCS GREATER THAN 500 GPM PUMPS. G6~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.

INCREASING GO TU Step 33.

d. PZR level - GREATER THAN 4% d. DO NOT STOP ECCS PUMPS.

RETURN TO Step 31a.

32 GO TO 2BEP ES-1.1. SI TERMINATION.

STEP 1 I 33 INITIATE MONITORING OF CRITICAL SAFETY FUNCTION STATUS TREES FOR NORyEON ORJ APPROVED FEB 011989 )

B. O. S. R.

Page 22 of 33 j (0331E/0027E/050288) 1 i

.__-__-__ _ __ a

i REV. 1 REACTOR TRIP OR SAFETY INJECTION 2BEP-0 WOG-1A UNIT 2 i

STEP ACTION / EXPECTED RESUN5E RESPONSE NOT OBTAiNED CAUTION Alternate water sources for AF pumps will be necessary if CST level decreases to LESS THAN 3%.

1 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 4% in at least one SG.
b. Control feed-flow to maintain b. IF narrow range level in narrow range level ,BETWEEN 4% aily SG continues to

.AND 50% increase in an uncontrolled manner, THEN GO TO 2BEP-3, STEAM GENERATOR TUBE RUPTURE, Step 1.

i

\ "

ll APPROVED FEB 011989 B.O.S.R.

(0331E/0027E/050288) i

' ?f. I',, ' f. . <

REV. 1 REACTOR: TRIP OR SAFETY INJECTION 2BEP-0' WOG-1A- UNIT 2 1

i STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED _'

n.

CAUTION Following SI reset, auton.atic SI will NOT occur, until reactor trip breakers have been cycled.

CAUTION If offsite power is lost.after SI-reeet, then manual action may be required to. restart safeguards.

equipment.

'35 RESET SI: Reset SI per 2 BOA PRI-5, CONTROL ROOM INACCESSIBILITY,

a. Depress both SI_ reset ATTACHMENT E.

pushbuttons

b. Verify SI ACTUATED permissive light - NOT LIT c._ Verify AUTO SI BLOCKED permissive light - LIT I J APPROVED FEB 011989 B.O.S.R.

Page 24 of 33 (0331E/0027E/050288)

{

.j,j..

.REV. 1 REACTOR TRIP OR SAFETY INJECTION 2BEP-0

.WOG-1A UNIT 2

~

STEP ACTION / EXPECTED RESPONSE ~ RESPONSE NOT OBTAINED

-36 RESET CONTAINMENT ISOLATION:'

a'. Res't e Cnmt Isol Phase A a. Reset per 2 BOA PRI-5,-

CONTROL ROOM

INACCESSIBILITY, ATTACHME24T E.
b. Reset Cnmt Isol Phase B b. Reset per 2 BOA PP,I-5, CONTROL ROOM INACCESSIBILITY ATTACHMENT E
c. Reset Cnmt Vent Isol
d. Check SAC run lights - ANY LIT d. Start one SAC per BOP SA-1, STARTUP AFD OPERATION OF THE SAC's.
e. Open Cnmt instrument air isol valves:

e 2IA065 e 2IA066-

f. Open Cnmt fire protectivn isol valve:

.s e 2FP010 FCl N OHA ON OLY g ,

APPROVED FEB 0 I 1989 B. O. S. R.

Pacje 25 of 33 (0331E/0027E/050288)

__________D

., . 1

.w...

'N

'REV. 1' REACTOR TRIP OR SAFETY INJECTION 2BEP-0 l WOG-1A UNIT.2 l

l STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OST AiNED CAUTION RCS pressure should be monitored.

If RCS pressure decreases to LESS THAN 300 PSIG, then RH pumps must be manually restartted to supply water to the RC3.

37 CHECK IF RH PUMPS SHOULD BE SIOPPED:

a. Check RCS pressure:

.1) Pressure'(2PI-403A/405) - 1) Go TO 2BEP-1, LOSS OF GREATER THAN 300 PSIG REACTOR OR SECONDARY' COOLANT, Step 1.

2) Pressure - STABLE OR 2) GO TO Step 38.

INCREASING

b. Stop RH pumps'and place in standby 38 G ECK SECONDARY RADIATION GO TO 2BEP-3, STEAM NO RMAL: GENERATOR TUBE. RUPTURE, Step 1.
a. Sample SGs' blowdown for activity:
1) Open SG blowdown sample isol valves:

7V e 2SD005A e 2SD005B y)\

,J, ,i . i ' '

  • 2SD005C e 2SD005D
2) Notify Rad Chem to sample SGs' blowdown for activity APPROVED  ;

I FEB 011989 i B.O.S.R. ,

Page 26 of 33 (0331E/0027E/050288)

.,q .

I:

REV. 1 REACTOR TRIP OR SAFETY INJECTION 2BEP-0 WOG-1A UNIT 2 STEP ACTidN/ EXPECTED RESPONSE RESPONSE NOT OBTAINED l39 CH ECK AUXILIARY BUILDING Evaluate cause of abnormal RA)lAT10N: conditions.

a. Aux Bldg vent stack IF cause is loss of RCS effluent monitors (2PR28J) - Inventory outside Cnmt, LESS THAN ALERT ATAP,M SETPOINT: THEN GO TO 2BCA-1.2, LOCA OUTSIDE CONTAINMENT, Step 1.
  • Grid 2 Beta 2PA228
  • Grid 2 Gas Low 2PB128
  • Grid 2 Gas High 2PD428
b. Aux Bldg vent stack I effluent monitors (2PR30J) -

LESS THAN ALERT ALARM SETPOINT:

e Grid 2 Gas Low 2PA136 f

  • Grid 2 Gas Med 2PB230 l
  • Grid 2 Gas High 2PC330
  • Grid 2 Effluent 2PF430
c. ECCS cubicle monitors - LESS THAN ALERT AIARM SETPOINT:

e RH/CS Pump 2A Cubicle (2PR13J):

e Grid 2 Beta 2PA213 e Grid 2 Gas 2PB113

  • RH/CS Pump 2B Cubicle l (2PR14J):
  • Grid 2 Beta 2PA214 e Grid 2 Gas 2PB114 e Rh :DC 2A Cubicle (2PR15J):

u Grid 2 Beta 2PA215 e Grid 2 Gas 2PB115 Step continued on next page c0'1.

i

,F0":RMA. 0T1 OaLY 1

l APPROVED FEB 011989 B. o. S. R.

Page 27 of 33 (0331E/002TE/050288)

.]

[,M, . f .-

')

REV. 1 REACTOR TRIP OR SAFETY INJECTION 2BEP-0 WOG-1A UNIT 2

__ STEP- ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED l-Step 39c-(continued) e RH HX 2B Cubicle (2PR16J):

  • Grid 2 Beta 2PA216 e Grid 2 Gas 2PB116 i

e CENT CHG Pump 2A Cubicle l (2PR17J);

1 e Grid 2 Beta 2PA217

  • Grid 2 Gas 2PB117 e CENT CHG Pump 2B Cubicle 1 (2PR1BJ) e ' Grid 2 Beta 2PA218 e Grid 2 Gas 2PB118
d. Grid 4 Aux Bldg area radiation utonitors - LESS THAN ALERT ALARM SETPOINT j 40 CHECK PRT CONDITLONS: Evaluate cause of abnormal conditions, j
a. Pressure - LESS THAN 6 PSIG d

. IF any PZR safety valve is

b. Level - LESS THAN 80% determined to be the source of leaka e into the PRT,
c. Temperature - LESS THAN 125'F THENGO$02BEP-1,LOSSOF -

REACTOR OR SECONDARY COOLANT, '

Step 1.

c0R N0r/KE0X 01Y i

I APPRCVED -

FEB 011989 ~  !

B. o. S. R.

i i

age 28 of 33 i (0331E/0027E/050288) i f ,.

.c; .

,. 4 s s.;

REV.-1 REACTOR TRIP OR SAFETY INJECTION 2BEP-0  !

WOG-1A UNIT 2 l

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

o 5500 KW continuous duty 8 954 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 /> e 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 /> 9 1050 AMPS maximum.  ;

l 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.

tal CHECK IF DIESEL GENERATORS SHOULD BE STO)PE1:

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

e SAT 242-1 Bus alive light - IF offsite power can NOT MT be. restored, e ACC 2412 - CLOSED THEN notify System Load

  • SAT 242-2 Bus alive light - Dispatcher of existing LIT conditions so an
  • ACB 2422 - CLOSED emergency AC restoration program can be implemented.

Step continued on next page APPROVED FEB 011989 B.O.S.R.

Page 29 of 33 (0331E/0027E/050288)

L /

L.' .? , ~ .

REV. 1 REACTOR TRIP OR SAFETY INJECTION 2BEP-0 i WOG-1A UNIT 2 t

STEP ACTION / EXPECTED RESPONSE RESPONSE NOT OBTAINED Step 41 (continued)

b. NON'-ESF 4 KV Busses: b. IF offsite power can NOT be promptly restored,
  • SAT 242-1 Bus alive light - THEN establish necessary LIT NON-ESF loads to maintain
  • ACB 2432 - CLOSED plant conditions.
  • SAT 242-2 Bus alive light -

LIT 1) Verify locally all

  • ACB 2442 - CLOSED breakers on Bus 243 and 244 OPEN.
2) Place all non-running WS pumps in PULL OUT position.
3) Reset SI recirc sump valves:
  • 2SI8811A e 2SI8811B
4) Energize Bus 243 and 244 from ESF crosstie breakers.

5.) 02en all 480 volt transformer LOW side breakers associated with Bus 243 and 244.

6) Reenergize PZR heaters:

a) Close 4160 volt PZR heater transformer's HIGH side breakers

"" "" '3-0R 'NJ0P' /iOON OLY b) Close 480 volt PZR heater transformer's LOW side breakers at 2PM05J.

APPROVED St.ep continued on next page FEB 011989 l

B.O.S.R.

l (0331E/0027E/050288) l

y

[2),/*3 l. .

k.

REV. 1 REACTOR TRIP OR SAFETY INJECTION 2BEP-0 WOG-1A UNIT 2 STEP ACTION / EXPECTED RESPONSE. RESPONSE NOT OBTAINED Step 41b (continued) 1 c) Operate PZR heater controis at.

necessary to control l

system pressure..

7) Start a WS pump per BOP WS-1, STARTUP AND l -OPERATION OF WS SYSTEM, if necessary.
8) Start.a SAC per BOP.

SA-1i 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 BOP DG-12, DIESEL GENERATOR SHUTDOWN.

42 RETURN TO STEP 25.

_END_

FOR INFORMAT!0!\!

APPROVED FEB 011989 B.O.S.R.

=w = ---

(0331E/0027E/050288)

, , , . .. l

<.yp x.

.- 1 REV. 1 REACTOR TRIP OR SAFETY INJECTION 2BEP-0 t WOG-1A' UNIT 2 l M

(NORMAL) 1 0 H A T \ CX.y 200 300 400 500 600 700 2600 7 #I , ,

'2600

, 7 ,

2500 2400 r i[ [ 2500

  • bOS '

(( [  !

~

2400

) [ ) 2300 2200 j / 2200.

2100

(( [ 2100 m

0 2000 0

(( j 2000 1802 t

[/ [ 1900 0 A C C E P TA B i_ E f[ f 1800 H AIOO G. [l [ 1700

/[ j v 1600 1600 v f j y 1500 j 1500' E 1400 [/ [ -1400 J -1300 // [ 1300 J 1200 ij [ 1200 C-g 1100 1100 LJ [/ /

E 1000

[ f

[ -

10 0 0 E O- 900 J f 900 ' O-

[f g 802 gUEES'E h/ r / NOT 800 700

' J ACCEPTABLE.

- W

(_) // f _

73g g_)

600 j} # ,/ -

600 1 500 jh ' ., ' '

500 400 .

27

./ [ '"

/4----- S AT U R AT I O N----- 400 300 300 N O R M A L --- - I #

/

200- --

-C NMT -

200 100 100 200 300 400 500 bba 700 TEMPERATURE C o F) APPROVED FIGURE 2BEP 0-1 01 2 RCS SUBC00 LING MARGIN B.O.S.R.

Page 32 of 33 (0331E/0027E/050288) 1

)% 'a'. .

REV. 1 REACTOR TRIP OR SAFETY INJECTION 2BEP-0 WOG-1A UNIT 2 ATTACHMENT A A. Determination of Post-Accident RCS Subcooling:

1. Check Cnmt for ADVERSE conditions:

o Cnmt pressure greater than 5 PSIG.

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

e 2RT-AR020 Grid 4 5AS120

2. Check RCS pressure on wide range pressure instruments.

(2PI-403A/405).

3. Determine temperature for RCS pressure using NORMAL or ADVERSE Cnmt curves per Figure 2BEP 0-1.
4. Check average of ten highest core exit TCs from MCB indicators (2TI-IT001/IT002).
5. If average of ten highest core exit TCs less than temperature for RCS pressure, then acceptable subcooling exists.

OMd

CR W OB,b*0%

APPROVED FEB 011989 s.o.S.R.

Page 33 of 33 (0331E/0027E/050288)

FINAC

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