ML111861756

Rev K to Operating Procedure E-0-07, Fire in Dedicated Fire Zone

ML111861756
Person / Time
Site:	Kewaunee
Issue date:	08/04/1998
From:	Braun D Wisconsin Electric Power Co
To:
Shared Package
ML111861753	List: ML111861752 ML111861756
References
E--7, E-0-07, NUDOCS 9810020270
Download: ML111861756 (38)

Text

WISCONSIN PUBLIC SERVICE CORPORATION NO.

E 07 REV K

KEWAUNEENUCLEARPOWERPLANT TITLE FIRE IN DEDICATED FIRE ZONE OPERATING PROCEDURE DATE AUG 04 1998 PAGE 1 of 38 REVIEWED BY APPROVED B NUCLEAR YES PORC REVIEW YES SRO APPROVAL OF YES SAFETY RELATED REQUIRED TEMPORARY CHANGES ENO MPN REQUIRED El NO

1.0 INTRODUCTION

1.1 The purpose of this procedure is to PLACE the plant in Hot Shutdown and cooldown to Cold Shutdown using Control Room and local manual operations in the event of a fire at the Dedicated Shutdown Panel or in a Dedicated Fire Zone.

Normal Control Room operations are no longer effective.

All dedicated equipment and offsite power will be unavailable or unreliable.

2.0 SYMPTOMS OR ENTRY CONDITIONS 2.1 A fire that causes the inability to monitor or control Dedicated Shutdown System equipment and instrumentation from the Control Room.

2.2 This procedure will be entered from E-FP-08.

3.0 AUTOMATIC ACTIONS 3.1 No automatic actions are assumed to occur.

9810020270 980928 PDR ADOCK 05000305 P

PDR

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of 38 OPERATOR ACTIONS II CONTINGENCY ACTIONS 4.0 DETAILED PROCEDURE CAUTION A hydrogen fire/explosion hazard may exist at generator due to loss of seal.oil system.

NOTE:

The Emergency Plan Implementing Procedures should be reviewed to evaluate if the emergency response organization should be activated.

1 MANUALLY TRIP THE REACTOR

a. Reactor Trip and Bypass Breakers -

OPEN

b. Neutron flux - DECREASING 2

MANUALLY TRIP THE TURBINE:

a. Both Turbine Stop Valves CLOSED IF Reactor does NOT trip. OPEN breakers 13301 and 14301. Bus 33/43 Supply.

IF breakers 13301 and 14301 do NOT open, locally OPEN Reactor Trip Breakers.

Manually RUN BACK Turbine and PLACE both EH Oil Pumps in PULLOUT.

IF Turbine Control Valves can NOT be closed, manually INITIATE Main Steam Isolation.

3 REQUEST CAS OPERATOR TO FAIL OPEN ALL SECURITY AND VITAL AREA DOORS AND INITIATE COMPENSATORY ACTIONS (Control Room Supervisor):

a. DISTRIBUTE key rings and two way radios.

I I

Mumma II

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of 38 OPERATOR ACTIONS CONTINGENCY ACTIONS 4

ALIGN SERVICE WATER HEADER B (Control Operator A):

a. CLOSE SW-4B/CV-31085, SW Header B to Turbine Bldg Hdr, by POSITIONING Turbine Bldg SW Header Selector switch to ISOL

b. CLOSE SW-3B/CV-31040, Service Water Header B Isolation

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of 38 OPERATOR ACTIONS I

5 ENERGIZE BUS 6 FROM DIESEL GENERATOR B (Control Operator A):

a. POSITION Bus 6 Voltage Restoring Mode Selector switch to MAN

b. POSITION following control switches to PULLOUT:

• 0

• 0

• 0 Safety Injection Pump B Containment Spray Pump B Residual Heat Removal Pump B Auxiliary Feedwater Pump B Bkr 16111.

Bkr 16211, Bkr 1-602.

Bkr 1-611, Bkr 1-601, Bkr 1-610, Bus 51 & 61 Tie Bus 52 & 62 Tie Bus 5 & 6 Tie TAT To Bus 6 RAT To Bus 6 MAT To Bus 6

c. POSITION Air Compressor B control switch to OFF CAUTION IF cooling water is NOT established in 2-3 minutes after Diesel start, damage will occur.

d. START Diesel Generator B

d. IF Diesel Generator B can NOT be started from Control Room.

REQUEST Control Operator B to locally START Diesel Generator B per A-0GM-1OB.

e. POSITION 43 switch for Bkr 1-603 to MAN

f. POSITION Bkr 1-603 Sync switch to ON NOTE:

Control Room Bus 6 Voltage indication may be unreliable. Use Diesel Generator B Voltage for indication of Bus 6 voltage.

g. CLOSE Bkr 1-603, DG B To Bus 6

h. START Service Water Pump B1 by HOLDING control switch to START for 5 seconds

h. IF Service Water Pump B1 NOT start. START Service Pump B2 by HOLDING cont!

switch to START for 5 5 CONTINGENCY ACTIONS

• 0 0*

• 0

• 0

• 0

• 0

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of 38 I.

OPERATOR ACTIONS 6

ESTABLISH COMPONENT COOLING FLOW TO BOTH RXCPS (Control Operator A):

a. VERIFY Component Cooling Pump B RUNNING

b. VERIFY CC-6B/MV-32122, Comp Cooling Heat Exchanger B Outlet OPEN

c. VERIFY SW-1OB/MV-32012, Aux Bldg SW Header B Isolation OPEN

d. VERIFY CC-61OB/CV-31128.

RXCP B Thermal Barr Comp Cooling Return OPEN

e. POSITION CC-61OA/MV-321127.

RXCP A Thermal Barr CC Alternate Control-switch to OPEN F

CONTINGENCY ACTIONS

a. START Component Cooling Pump B.

b. OPEN CC-6B.

c. OPEN SW-1OB.

d. OPEN CC-6108.

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OPERATOR ACTIONS I

7 DE-ENERGIZE BUSES 1, 2. 3. 4.

and 5 (Control Operator A):

a. STOP Diesel Generator 1A.

b. POSITION following control switches to PULLOUT:

Bkr Bkr Bkr Bkr Bkr Bkr Bkr Bkr Bkr Bkr Bkr Bkr 1-101, 1-104, 1-201, 1-204, 1-307, 1-301, 1-407, 1-401, 1-509.

1-503, 1-511, 1-501.

RAT To Bus 1 MAT To Bus 1 RAT To Bus 2 MAT To Bus 2 RAT To Bus 3 MAT To Bus 3 RAT To Bus 4 MAT To Bus 4 DG A To Bus 5 RAT To Bus 5 MAT To Bus 5 TAT To Bus 5

• Bkr 1-510.

Bus 5 & 6 Tie 8

PERFORM FOLLOWING LOCAL ACTIONS (Control Room Supervisor):

a. REMOVE fuses in RR-171:

1) Ckt 13 (PR-2B normal control)

b. REMOVE fuses in RR-174:

1) Ckt 27 (SI-101A/B)

2) Ckt 28 (SI-201A/B. SI-202A/B)

c. REMOVE fuses in RR-176:

1) Ckt 12 (PR-2A)

2) Ckt 39 (RC-49)

I CONTINGENCY ACTIONS

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of 38 OPERATOR ACTIONS I CONTINGENCY ACTIONS 9

PERFORM FOLLOWING LOCAL ACTIONS (Control Operator B):

a. Locally CLOSE:

1) MU-2A, Condensate Makeup Control Station Inlet

2) MU-28, Cond Emergency Makeup Control Station Inlet

b. REMOVE fuses in S-101:

1) Ckt 3 (RC-46)

b. REQUEST Control Room Supervisor to OPEN BRA-104, Ckt 6 Bkr (SD-101)

2) Ckt 19 (CVC-15)

Ba

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E-0-07 KEWAUNEENUCLEARPOWERPLANT TITLE FIRE IN DEDICATED FIRE ZONE EMERGENCY OPERATING PROCEDURES DATE AUG 04 1998 PAGE 8

of 38 OPERATOR ACTIONS CONTINGENCY ACTIONS 10 ESTABLISH ALTERNATE INSTRUMENT AIR (Control Operator B):

CAUTION The following control valves are supplied with dedicated air via local air accumulators and have limited air capacity. Accumulators will NOT refill until normal instrument air is restored.

a.

• t***

t** ***

Alternate Valve Minimum Design Cycles Accumulator 40 gallons LD-300 Excess Letdown Isolation 10 cycles of LD-300 AND LD-301 Excess Ltdn Flow.Control 10 cycles of LD-301 AND LD-302 Excess Ltdn Divert to RCDT 10 cycles of LD-302 40 gallons SW-30B1 SW Strn 1BI Backwash 7 cycles of SW-30B1 AND SW-30B2 SW Strn 1B2 Backwash 7 cycles of SW-30B2 30 gallons PR-2B Pressurizer PORV 5 cycles of PR-2B 18 gallons SW-4B Turb Bldg SW Hdr Isolation 1 open/close cycle 1.8 gallons AAC-15 Relay Room Air Supply AAC-16 Relay Room Air Exhaust 3 open cycles of AAC-15 3 open cycles of AAC-16

a. IF Air Dryer IC is in service, locally OPEN following valves:

• SA-2B. Cmpr lB Rcvr Outl

• SA-3, Station and IA Isol

• IA-300, 1 1/2" Alt IA

• NG-62. Air Dyr IC N2 Bckup Isol

• N2 Bottle Valve

b. Verify Bottle Reducer set at 60 psig

a. IF Air Dryer 1A is in service, locally OPEN following valves:

• SA-2B. Cmpr 1B Rcvr Outi

• SA-100A, Air Dyr 1A Sply Viv

• IA-300. 1 1/2" Alt IA CONTINUED

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of 38 OPERATOR ACTIONS I CONTINGENCY ACTIONS NOTE:

Step 10.a. shall be completed prior to proceeding with Step 1O.b.

c. IF Air Dryer 1C is in service.

locally CLOSE following valves:

• SA-100A, Air Dyr 1A Sply Vlv

• SA-62, SA to IA Isol

• SA-110, Air Dyr lB Dyr Air Inlt

• SA-101B, Air Dyr 1B Mos-Spr Init

• SA-107A1, Air Dyr 1A Fltr 1A1 Outl

• SA-107A2, Air Dyr 1A Fltr 1A2 Outl

• IA-1A, 2" IA Hdr Stop

• IA-5A, IA Dyr 1A Air Purge

• 0

• 0 IA-200,,3/4" IA to TSC IA-400, 1 1/2" Dedicated IA Isol

c. IF Air Dryer 1A is in service.

locally CLOSE following valves:

• SA-3, Station and IA Isol

• SA-110, Air Dyr 18 Dyr Air Inlt

• SA-120, Air Dyr 1A Dyr Bypass CV Inlt

• SA-170, Air Dyr lB Dyr Cross-Connect

• 0

• 0

• 0 IA-1C. IA Sply From Air Dyr IC IA-1A. 2" IA Hdr Stop IA-5A, IA Dyr 1A Air Purge

• IA-200, 3/4" IA to TSC

• IA-400, 1 1/2" Dedicated IA Isol

d. REQUEST Control Operator A to START Air Compressor B

e. Locally CLOSE NG-62, Air Dyr IC N2 Bckup Isol

f. Locally CLOSE N2 Bottle Valve CONTINUED 10 CONTINUED

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CONTINGENCY ACTIONS 10 CONTINUED

g. IF air accumulators for valves located inside Containment become depleted, INITIATE maintenance actions to ALIGN the Alternate Instrument Air Header to Containment as follows:

1) In BAST Room. LOOSEN jam nut on handwheel for IA-101/CV-31309, IA to Cntmt Isol

2) Locally CLOSE IA-101

3) In BAST Room. OPEN IA-101-1, Ded & Alt Hdr to Cntmt Isol

4) In ICS Pump area, OPEN IA-310, Alternate IA Hdr to Cntmt Isol

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E-0-07 KEWAUNEENUCLEARPOWERPLANT TITLE FIRE IN DEDICATED FIRE ZONE EMERGENCY OPERATING PROCEDURES DATE AUG 04 1998 PAGE 11 of 38 OPERATOR ACTIONS.

I CONTINGENCY ACTIONS 11 ESTABLISH S/G B AS HEAT SINK (Control Operator A):

a. INITIATE Train A and Train B Main Steam Isolation

1) CLOSE MS-1B/CV-31016, S/G B Main Steam Isolation Valve

2) CLOSE MS-1A/CV-31015, S/G A Main Steam Isolation Valve

b. START Auxiliary Feedwater Pump B

c. CLOSE AFW-10B/MV-32028. AFW Train B Crossover Valve

d. CLOSE BT-2B/MV-32079. S/G B Blowdown Isolation Valve B1

e. CLOSE BT-3A/MV-32078. S/G A Blowdown Isolation Valve A2

f. OPERATE SD-3B/CV-31174, S/G B PORV, to maintain Loop B WR Temperature at 5500F

g. OPERATE AFW-2B/CV-31316, AFWP Flow Control, to maintain S/G Level 4-50% on LI-473

h. REOUEST Control Operator B to locally CLOSE SD-3A/CV-31170, S/G A PORV:

2) REQUEST Control Operator B to locally POSITION MS-1A Trip Lever to TRIP.

8 B

h. Locally CLOSE SD-2A. S/G A PORV Isolation Valve.

1) INSERT pin to engage SD-3A handwheel

2) OPEN SD-3A Diaphragm Bypass Valve

3) CLOSE NG-235. N2 Supply to SD-3A

4) CLOSE IA-470. IA to SD-3A

5) VERIFY S-3A, CLOSED I

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CONTINGENCY ACTIONS 12 VERIFY RCS ISOLATED (Control Operator A):

a. CLOSE CVC-211/MV-32124, RXCP Seal Water Return Isolation

a. CLOSE CVC-212/MV-32115, RXCP Seal Water Return Isolation

b. CLOSE LD-3/CV-31104.

Letdown Isolation

c. CLOSE LD-300/CV-31236.

Excess Letdown Isolation CAUTION RCS Pressure shall be maintained below 2200 psig. to allow use of Safety Injection Pump B for RCS Make-up.

13 ESTABLISH RCS PRESSURE CONTROL

a. DE-ENERGIZE all Pressurizer Heaters and allow Przr Pressure to decrease to 2150 psig

b. POSITION Przr Level Control Channel Selector switch to NORMAL 2-3

c. OPERATE Pressurizer Heater Group B to maintain Przr Pressure 2100-2200 psig on PI-430 (white channel)

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CONTINGENCY ACTIONS NOTE:

SI-9B indicating lights may NOT function correctly.

14 ESTABLISH RCS MAKEUP CONTROL (Control Operator A):

a. ALIGN Safety Injection Pump B for RCS makeup via SI-15A:

1) OPEN SI-4B/MV-32110, RWST Supply To SI Pumps

2) OPEN SI-5B/MV-32108, SI Pump B Suction Isolation

3) OPEN SI-208/MV-32131. SI Recirculation To RWST

4) OPEN SI-209/MV-32130, SI Recirculation To RWST

5) OPEN SI-15A/MV-32093. Safety Injection To Reactor Vessel

6) OPEN SI-9B/MV-32095, Safety Injection To Reactor Vessel

b. START Safety Injection Pump B and run pump as necessary to maintain Przr Level 20-50% on LI-427 and LI-428

2) Locally OPEN SI-5B.

3) Locally OPEN SI-208.

4) Locally OPEN SI-209.

CONTINUED I

I

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E 07 KEWAUNEENUCLEARPOWERPLANT TITLE FIRE IN DEDICATED FIRE ZONE EMERGENCY OPERATING PROCEDURES DATE AUG 04 1998 PAGE 14 of 38 OPERATOR ACTIONS I CONTINGENCY ACTIONS CAUTION Pressurizer Heater Group B shall be utilized as the primary means of RCS pressure control.

PR-2B Air Accumulator is sized to allow a total of 5 cycles of PR-2B.

c. IF Przr Level is <2%

AND Przr Pressure is >2200 psig. THEN OPEN PR-2B to initiate SI Rx Vessel Flow as follows:

1) POSITION PR-2B/CV-31109, Przr PORV Alternate Control Station control switch to OPEN

2) WHEN Przr Level increases to

>20%. CLOSE PR-2B by returning control switch to NORMAL

d. Locally CLOSE SI-8B, SI Pump 1B X-Connect To SI Pump 1A CONTINUED Eli 14 CONTINUED

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CONTINGENCY ACTIONS CAUTION Do NOT operate SI Pump B more than 30 minutes on miniflow.

e. MAINTAIN Przr. Level 20-50%

1) VERIFY time interval between level adjustments is <30 min a) CLOSE SI-158/MV-32098, Safety Injection to Reactor Vessel b) On MCC 1-52B, OPEN SI-15B supply breaker c) CYCLE SI-15A to maintain Przr Level

1) STOP Safety Injection Pump 8 and run pump as necessary to maintain Przr level.

GO TO Step 4.0. DETAILED PROCEDURE. Step 15.

a) CYCLE SI-9B to maintain Przr Level.

GO TO Step 4.0. DETAILED PROCEDURE, Step 15.

14 CONTINUED

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E-0-07 KEWAUNEENUCLEARPOWERPLANT TITLE FIRE IN DEDICATED FIRE ZONE EMERGENCY OPERATING PROCEDURES DATE AUG 04 1998 PAGE 16 of 38 OPERATOR ACTIONS 15 VERIFY NATURAL CIRCULATION (Control Operator A):

a. Loop B Hot Leg WR Temperature STABLE or DECREASING

b. RCS Subcooling based on Loop B Hot Leg WR Temperature and Przr Pressure -

>500F

c. S/G B Pressure - STABLE or DECREASING

d. Loop B Cold Leg WR Temperature AT SATURATION TEMPERATURE for S/G B Pressure I

CONTINGENCY ACTIONS INCREASE dumping steam from S/G B using SD-3B/CV-31174. S/G B PORV.

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E-0-07 KEWAUNEE NUCLEAR POWER PLANT TITLE FIRE IN DEDICATED FIRE ZONE EMERGENCY OPERATING PROCEDURES DATE AUG 04 1998 PAGE 17 of 38 OPERATOR ACTIONS 11 CONTINGENCY ACTIONS NOTE:

WHEN 12,700 gallons has been added from the RWST (approximately 5% level decrease), 1% Cold Shutdown Boron Conc should be attained.

16 ESTABLISH COLD SHUTDOWN BORON CONCENTRATION (Control Operator A):

a. At MCC 1-52B. OPEN CC7653/MV-32082. Excess Ltdn Hx CC Return, supply breaker

b. In North Pen Rm, VERIFY CC-653 OPEN

c. Near Aux Bldg Mezz Fan Coil Units, POSITION SW-1306B Manual Override to FAIL OPEN

d. POSITION LD-301/CV-31090, Excess Letdown Control Selector switch to MAN

e. POSITION LD-302/CV-31235, Excess Letdown To VCT/RCDT.

to RD TANK

f. OPEN LD-300/CV-31236. Excess Letdown Isolation

g. ADJUST LD-301. Excess Letdown Manual Control, as necessary to establish required letdown flow

h. OPERATE SI-15A as necessary to maintain Przr Level 20-50%

a. Locally OPEN Bkr 15206, MCC-528

& 52C supply bkr on Bus 1-52.

b. Locally OPEN CC-653.

h. OPERATE SI-9B as necessary to maintain Przr Level 20-50%. IF SI-9B is NOT available, use Safety Injection Pump B.

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E-0-07 KEWAUNEE NUCLEAR POWER PLANT TITLE FIRE IN DEDICATED FIRE ZONE EMERGENCY OPERATING PROCEDURES DATE AUG 04 1998 PAGE 18 of 38 OPERATOR ACTIONS 17 VERIFY STATUS OF SUPPORT EQUIPMENT (Control Operator A):

a. START standby Service Water Pump 81/82 by HOLDING control switch to START for 5 seconds

b. START Cntmt Fan Coil Unit C

c. START Cntmt Fan Coil Unit D

d. OPEN the following:

1) SW-903C/MV-32058, Cntmt Fan Coil Unit C SW Return Isol ation

2) SW-903D/MV-32059, Cntmt Fan Coil Unit D SW Return Isolation

e. START Control Room A/C Fan B

f. VERIFY the following RUNNING:

• Turbine Building Fan Coil Unit B

• Aux Bldg Basement Fan Coil Unit 8

• Battery Room B Fan Coil Unit

g. VERIFY Screenhouse Fan B cycles with temperature

h. VERIFY Diesel Generator B Room Vent Fan RUNNING

i.

POSITION Nuclear Recorder Pen 1/2 Selector switches to S1 and S2.

j.

REOUEST Plant Electricians determine feasibility of returning both CROM Cooling Fans to service F

CONTINGENCY ACTIONS

• Locally START Battery Room B Fan Coil Unit.

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CONTINGENCY ACTIONS CAUTION IF S/G A Wide Range Level is <10%

AND S/G A Pressure is > 1030psig, OR S/G A Pressure is < S/G B Press THEN DO NOT initiate AFW flow to Steam Generator A NOTE:

Cables for S/G A Level and Pressure indication are NOT protected.

Indication may NOT be available.

18 ESTABLISH S/G A LEVEL CONTROL (Control Operator A)

a. OPERATE T/D AFW Pump as necessary to maintain S/G A Level 4-50%

IF S/G A is NOT available. GO TO Step 4.0, DETAILED PROCEDURE, Step 20.

a. IF T/D AFW Pump is NOT available:

1) Locally OPEN supply bkr for AFW-1OA, AFW Pump 1A Disch X-over MV.

2) Locally CLOSE AFW-1OA.

3) OPEN AFW-108.

4) Locally THROTTLE AFW-10A to establish 25gpm on FI-13201.

AFW to S/G 1A, in Aux Bldg Bsmt.

5) WHEN S/G A Level reaches 50%. CLOSE AFW-10B.

6) REPEAT Steps 3 and 5.as necessary to maintain Level 4-50%.

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E 07 KEWAUNEENUCLEARPOWERPLANT TITLE FIRE IN DEDICATED FIRE ZONE EMERGENCY OPERATING PROCEDURES DATE AUG 04 1998 PAGE 20 of 38 OPERATOR ACTIONS 19 ESTABLISH S/G A PRESSURE CONTROL (Control Operator B):

a. ESTABLISH direct communication.

between SD-3A and Control Room

b. Depressurize S/G A to match the pressure in S/G B:

1) Locally OPEN SD-3A.

2) WHEN pressure in S/G A is equal to S/G B, CLOSE SD-3A.

c. WHEN S/G A Pressure is 100 psig

> S/G B Pressure. REPEAT steps 19.a and 19.b.

20 MAINTAIN STABLE PLANT CONDITIONS

a. Loop B Cold Leg WR Temperature 550 0 F

b. Loop B Cold Leg WR Temperature and Przr Pressure - Within Limits of Figure E-0-07-1

c. Przr Level -

20%-50%

d. S/G B Level -

>4%

e. S/G A Level, IF available -

>4%

CONTINGENCY ACTIONS

b. GO TO Step 11.

c. GO TO Step 12.

d. GO TO Step 11.

e. GO TO Step 18.

21 VERIFY COLD SHUTDOWN BORON CONCENTRATION NOTE:

WHEN 12.700 gallons has been added from the RWST (approximately 5%

level decrease), 1% Cold Shutdown Boron Conc should be attained.

a. RCS Boron Sample > Cold Shutdown Boron Concentration

a. GO TO Step 16.

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E 07 KEWAUNEE NUCLEAR POWER PLANT TITLE FIRE IN OEDICATED FIRE ZONE EMERGENCY OPERATING PROCEDURES DATE AUG 04 1998 PAGE 21 of 38 EP~C OPERATOR ACTIONS I I CONTINGENCY ACTIONS REQUEST Plant Electricians determine feasibility of returning both CROM Cooling Fans to service 22

- w

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E-0-07 KEWAUNEE NUCLEAR POWER PLANT TITLE FIRE IN DEDICATED FIRE ZONE EMERGENCY OPERATING PROCEDURES DATE AUG 04 1998 PAGE 22 of 38 OPERATOR ACTIONS 23 SUPPORT SYSTEMS PERIODIC CHECKS (Control Operator A):

a. VERIFY Condensate Storage Tanks Level -

>4% (3000 Gal)

b. Locally VERIFY 1B Instrument Air Receiver Pressure (PI-11084) - >60 psig

c. VERIFY Service Water Header B Pressure - >60 psig

d. VERIFY D/G lB Fuel Oil System and Station Batteries operating correctly

e. IF required to supply fresh air to the Control Room:

1) OPEN ACC-1B/MD-32368, Control Room Fresh Air Inlet Damper 8

2) Locally OPEN ACC-5/CD-34007.

Control Room Outside Air Bypass Damper

3) Locally OPEN ACC-20/CD-34061, Cont Rm to Turb Bldg Steam Exclusion Dmpr

4) Locally OPEN ACC-21/CD-34062. Cont Rm to Turb Bldg Steam Exclusion Dmpr CONTINGENCY ACTIONS

a. PERFORM the following:

1) Locally OPEN OW-20, RMST Supply, to cross-connect RMU tanks to CSTs OR

2) OPEN SW-601B/MV-32030, Service Water to AFW Pump B Isol..

IF the T/D AFW Pump is operating, OPEN SW-502/MV-32031, Service Water to T/D AFW Pump Isol.

b. VERIFY air system lined up per Step 10.

d. CONSULT plant electrical and I&C personnel.

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CONTINGENCY ACTIONS NOTE:

IF the plant can be maintained in a stable Hot shutdown condition, plant management should be consulted to determine the feasibility of restoring off-site power prior to commencing any further plant status changes.

24 RCS COOLDOWN TO COLD SHUTDOWN DESIRED

a. GO TO Step 25

a. GO TO Step 20.

CAUTION WHEN cooling down using Loop B, do NOT cool down too rapidly; S/G A may become-a heat source.

IF S/G A pressure control and AFW flow are NOT established. Loop A will stagnate and only means of heat removal will be losses to ambient.

25 INITIATE RCS COOLDOWN:

a. MAINTAIN cooldown rate

<250 F/hr

b. ADJUST SD-3B to achieve required cooldown rate

c. MAINTAIN S/G B Level 50%

d. MAINTAIN Loop B Cold Leg WR Temperature and Przr Pressure Within Limits of figure E-0-07-1 or E-0-07-2

e. IF S/G A is available, MAINTAIN temperature difference between Loop A and Loop B <20aF by locally OPENING SD-3A as necessary to equalize S/G A and B pressures

.e. MAINTAIN 500 F RCS Subcooling based on S/G A saturation temperature. IF S/G A Pressure indication is NOI available.

REQUEST maintenance assistance to establish alternate indication.

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E 07 KEWAUNEE NUCLEAR POWER PLANT TITLE FIRE IN DEDICATED FIRE ZONE EMERGENCY OPERATING PROCEDURES DATE AUG 04 1998 PAGE 24 of 38 OPERATOR ACTIONS I CONTINGENCY ACTIONS 28 BLOCK SI 26 VERIFY RCS LOOP B WR TEMPERATURE -

GO TO Step 25.

<5500 F CAUTION Pressurizer Heater Group B shall be utilized as the primary means of RCS pressure control.

PR-2B Air Accumulator is sized to allow a total of 5 cycles of PR-2B.

27 DEPRESSURIZE RCS TO 1950 PSIG:

a. DE-ENERGIZE Pressurizer Heater Group B

b. IF faster response is required.

OPEN PR-2B using Przr PORV Alternate Control Station

c. WHEN Przr Pressure is equal to 1950 psig, STOP RCS depressurization

d. ENERGIZE Pressurizer Heater Group B as necessary to maintain 1950 psig CAUTION IF RCS Pressure increases above 2000 psig. SI will need to be blocked again after pressure goes below 2000 psig.

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E 07 KEWAUNEENUCLEARPOWERPLANT TITLE FIRE IN DEDICATED FIRE ZONE EMERGENCY OPERATING PROCEDURES DATE AUG 04 1998 PAGE 25 of 38 i I OPERATOR ACTIONS 29 MAINTAIN RCS CONDITIONS:

a. Przr Pressure -

1950 psig

b. Przr Level 50%

c. RCS cooldown rate - <250F/hr

d. Loop B Cold Leg WR Temperature and Przr Pressure - Within Limits of Figure E-0-07-1 or E-0-07 -2 30 MONITOR RCS COOLDOWN:

a. RCS Loop B WR Temperature DECREASING

b. S/G A Pressure -

STABLE or DECREASING

c. RCS subcooling -

>50aF and INCREASING

1) REFER to Table E-0-07-1

2) Use Loop B Hot Leg WR Temperature I CONTINGENCY ACTIONS

WISCONSIN PUBLIC SERVICE CORPORATION NO.

E-0-07 KEWAUNEENUCLEARPOWERPLANT TITLE FIRE IN DEDICATED FIRE ZONE EMERGENCY OPERATING PROCEDURES DATE AUG 04 1998 PAGE 26 of 38 OPERATOR ACTIONS 31 INITIATE RCS DEPRESSURIZATION:

a. VERIFY CRDM Fans - Both ON I CONTINGENCY ACTIONS

a. Until 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> soak is completed, MAINTAIN RCS subcooling > 2000F and GO TO Step 31.d.

1) REFER to Table E-0-07-01

2) Use Reac Coolant LP B Hot Leg Temp Ind

b. MAINTAIN RCS subcooling -

>50 0 F

1) REFER to Table E-0-07-1

2) Use Reac Coolant LP B Hot.

Leg Temp Ind

c. MAINTAIN Reac Coolant LP B Cold Leg Temp and Pzr Press -

Within limits of Figure E-0-07-2

d. DE-ENERGIZE Pressurizer Heater Backup Group 18 32 CONTINUE RCS COOLDOWN AND DEPRESSURIZATION:

a. MAINTAIN cooldown rate

<250 F/hr

b. MAINTAIN Subcooling requirements of Step 31

b. STOP depressurization and RE-ESTABLISH subcooling.

c. MAINTAIN Loop B Cold Leg WR Temperature and Przr Pressure Within Limits of Figure E-0-07-1 or E-0-07-2

d. MAINTAIN Przr Level 50%

WISCONSIN PUBLIC SERVICE CORPORATION NO.

E-0-07 KEWAUNEE NUCLEAR POWER PLANT TITLE FIRE IN DEDICATED FIRE ZONE EMERGENCY OPERATING PROCEDURES DATE AUG 04 1998 PAGE 27 of 38 OPERATOR ACTIONS 33 VERIFY PRZR LEVEL -

NO UNEXPECTED LARGE VARIATIONS 34 DETERMINE IF SOAK IS REQUIRED:

a. CRDM Fans -

Less than both running

b. Reac Coolant LP B Cold Leg Temp

- <3900 F

c. MAINTAIN following conditions for at least 18 hour2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br />s:

1) Przr Press - >1400psig

2) Reac Coolant LP B Cold Leg Temp - Between 390oF and minimum temperature allowed per E-0-07-1 I CONTINGENCY ACTIONS PRESSURIZE RCS within limits of Figure E-0-07-1 or E-0-07-2 to collapse potential voids in system and CONTINUE cooldown.

a. Soak NOT required.

step 35.

GO TO

b. MAINTAIN Pzr Press >1400psig GO TO Step 32.

WISCONSIN PUBLIC SERVICE CORPORATION NO.

E-0-07 KEWAUNEE NUCLEAR POWER PLANT TITLE FIRE IN DEDICATED FIRE ZONE EMERGENCY OPERATING PROCEDURES DATE AUG 04 1998 PAGE 28 of 38 OPERATOR ACTIONS II CONTINGENCY ACTIONS CAUTION Pressurizer Heater Group B shall be utilized -as primary means of RCS pressure control.

PR-2B Air Accumulator is sized to allow a total of 5 cycles of PR-2B.

NOTE:

IF S/G A is NOT depressurized periodically. S/G A U-Tubes will void during depressurization. This will result in a rapidly increasing Przr Level.

35 DEPRESSURIZE RCS TO 950 PSIG:

a. DE-ENERGIZE Pressurizer Heater Group B

b. IF faster response is required, OPEN PR-2B using Przr PORV Alternate Control Station

c. WHEN Przr Pressure is equal to 950 psig. STOP RCS depressurization

d. ENERGIZE Pressurizer Heater Group B as necessary to maintain 950 psig I

I I

WISCONSIN PUBLIC SERVICE CORPORATION NO.

E-0-07 KEWAUNEE NUCLEAR POWER PLANT TITLE FIRE IN DEDICATED FIRE ZONE EMERGENCY OPERATING PROCEDURES DATE AUG 04 1998 PAGE 29 of 38 OPERATOR ACTIONS CONTINGENCY ACTIONS CAUTION Any valve manipulation requiring Containment -entry will require coordination with Health Physics and approval per EP-AD-11.

36 DETERMINE IF ACCUMULATORS SHOULD BE ISOLATED:

a. Przr Pressure - <1000 psig

b. ISOLATE SI Accumulators A/B and ALIGN SI for <1000 psig

1) REOUEST plant electrician CLOSE the following valves from respective-MCCs and LOCK OPEN supply breakers:

a) SI-20B/MV-32096. SI Accumulator 18 Disch Isol (MCC-628) b) SI-20A/MV-32091. SI Accumulator lA Disch Isol (MCC-52B) c) SI-300B/MV-32112, RHR Pump Suct Isol (MCC-62E)

a. DO NOT isolate Accumulators GO TO Step 35.

1) IF power is NOT available, LOCK OPEN supply breakers and locally CLOSE valves.

WISCONSIN PUBLIC SERVICE CORPORATION NO.

E 07 KEWAUNEENUCLEARPOWERPLANT TITLE FIRE IN DEDICATED FIRE ZONE EMERGENCY OPERATING PROCEDURES DATE AUG 04 1998 PAGE 30 of 38 OPERATOR ACTIONS CONTINGENCY ACTIONS CAUTION Pressurizer Heater Group B-shall be utilized -as primary means of RCS pressure control.

PR-2B Air Accumulator is sized to allow a total of 5 cycles of PR-2B.

NOTE:

IF S/G A is NOT depressurized periodically. S/G A U-Tubes will void during depressurization.

This will result in a rapidly increasing Przr Level.

37 DEPRESSURIZE RCS TO 420 PSIG:

a. DE-ENERGIZE Pressurizer Heater Group B

b. IF faster response is required.

OPEN PR-2B using Przr PORV Alternate Control Station

c. WHEN Przr Pressure is equal to 420 psig, STOP RCS depressurization

d. ENERGIZE Pressurizer Heater Group B as necessary to maintain 420 psig 38 DETERMINE IF RHR SYSTEM CAN BE PLACED IN SERVICE:

a. Loop B Hot Leg WR Temperature

<4000 F

b. Przr Pressure -

<425 psig

a. GO TO Step 32.

b. GO TO Step 37.

WISCONSIN PUBLIC SERVICE CORPORATION NO.

E-0-07 KEWAUNEE NUCLEAR POWER PLANT TITLE FIRE IN DEDICATED FIRE ZONE EMERGENCY OPERATING PROCEDURES DATE AUG 04 1998 PAGE 31 of 38 OPERATOR ACTIONS 39 PLACE RHR TRAIN B IN SERVICE:

a. REQUEST plant electrician INSTALL jumpers to bypass RCS pressure interlocks. THEN CLOSE supply breakers for the following valves:

1) RHR-1B/MV-32132, Loop B Hot Leg to RHR Pump (MCC-62B Ext)

2) RHR-2B/MV-32133, Loop B Hot Leg to RHR Pump (MCC-62B Ext)

b. Locally VERIFY the following.

valves CLOSED, THEN OPEN supply breakers:

1) RHR-300B/MV-32135, RHR Pump B Supply To SI Pump B (MCC-62H)

2) RHR-400B/MV-32126, RHR Pump B Supply to ICS Pump B (MCC-62H)

c. Locally OPERATE RHR-8B/CV-31115, RHR Hx 1B Outlet CV. as follows:

1) CLOSE IA-31115-1

2) CLOSE IA-31115-2

3) BLEED OFF air pressure at pressure regulators

4) LOOSEN jam nut on valve stem

5) POSITION RHR-8B to 10% OPEN I CONTINGENCY ACTIONS CONTINUED

WISCONSIN PUBLIC SERVICE CORPORATION NO.

E-0-07 KEWAUNEENUCLEARPOWERPLANT TITLE FIRE IN DEDICATED FIRE ZONE EMERGENCY OPERATING PROCEDURES DATE AUG 04 1998 PAGE 32 of 38 CONTINUED

d. At MCC-62E. OPEN-supply breaker for CC-400B/MV-32120, CC Supply to RHR Heat Exchanger lB, THEN Locally OPEN CC-4008

e. VERIFY Component Cooling Return Flow (F-619) indicates <3650 gpm CONTINGENCY ACTIONS

e. Locally CLOSE CC-400A.

NOTE:

Power to RHR-1B and RHR-2B indicating lights is NOT protected.

IF position indication is NOT available, valve opening can be verified locally by RHR Pump B discharge pressure increasing to RCS pressure.

f. OPEN RHR-1B/MV-32132 and RHR-2B/MV-32133, RCS Loop B Supply To RHR Pumps

g. OPEN SI-302B/MV-32101. RHR Pump B Injection To Reactor Vessel

h. VERIFY RHR System Boron Concentration within 100 ppm of the RCS

i.

REQUEST plant electricians visually inspect RHR Pump B and RHR Pump B Pump Pit Fan Coil Unit power cables

j.

START Residual Heat Removal Pump B

1) VERIFY RHR Pump B Pump Pit Fan Coil Unit. ON

f. Locally OPEN RHR-18 and RHR-2B.

g. IF SI-302B can NOT be opened from Control Room, OPEN SI-302B supply bkr (MCC 1-62B Ext) and locally OPEN SI-302B.

j.

IF required. REOUEST plant electricians to INSTALL RHR Pump B power jumper.

1) IF required. REOUEST plant electricians to INSTALL RHR Pump B Pump Pit Fan Coil Unit power jumper.

k. At MCC-62E, LOCK OPEN supply bkr for SW-1300B/MV-32010, SW From CC Hx lB, THEN Locally OPEN SW-1300B 39 OPERATOR ACTIONS

WISCONSIN PUBLIC SERVICE CORPORATION NO.

E-0-07 KEWAUNEE NUCLEAR POWER PLANT TITLE FIRE IN DEDICATED FIRE ZONE EMERGENCY OPERATING PROCEDURES DATE AUG 04 1998 PAGE 33 of 38 OPERATOR ACTIONS 40 CONTINUE RCS COOLDOWN TO BELOW 200OF WITH RHR SYSTEM:

a. MAINTAIN RCS cooldown rate

<250 F/hr

b. Locally THROTTLE RHR-8B to achieve cooldown rate

c. Locally OPERATE RHR-101/CV-31116. RHR Hx Bypass CV. as follows:

1) Fail RHR-101 closed:

a) CLOSE IA-31116-2 b) CLOSE IA-31116-1 c) BLEED OFF air pressure at.

pressure regulator

2) VERIFY RHR-110, RHR Return To RWST, CLOSED

3) OPEN RHR-10B, Cross Connect Valve

4) OPEN RHR-100B, Heat Exchanger Bypass Line

5) LOOSEN jam nut on RHR-101 valve stem

6) POSITION RHR-101 to establish 1000-2000 gpm on FI-928. RHR Pump B Flow

d. MAINTAIN Loop B Cold Leg WR Temperature and Przr Pressure Within Limits of Figure E-0-07-1 or E-0-07-2

e. MAINTAIN Przr Level -

20-50%

I CONTINGENCY ACTIONS

b. Locally THROTTLE RHR-9B, 1B RHR Hx Outlet.

CONTINUED

WISCONSIN PUBLIC SERVICE CORPORATION NO.

E 07 KEWAUNEENUCLEARPOWERPLANT TITLE FIRE IN DEDICATED FIRE ZONE EMERGENCY OPERATING PROCEDURES DATE AUG 04 1998 PAGE 34 of 38 OPERATOR ACTIONS F

CONTINGENCY ACTIONS

f. WHEN Loop 8 WR Temperature is

<2000 F, ALIGN Containment Spray System as follows:

1) In N and E Pen Room, LOCK CLOSED ICS-7A and ICS-78, Cntmt Spray Pump 1A/18 to Cntmt Vessel

2) REQUEST plant electrician RACK OUT Containment Spray Pump A and B supply breakers CAUTION Depressurizing RCS before entire RCS is <2000F may result in additional void formation in the RCS.

41 CONTINUE COOLDOWN OF INACTIVE PORTION OF RCS:

a. Steam Generator U-Tubes CONTINUE dumping steam from both Steam Generators

b. Upper head region - Both CROM Cooling Fans. ON

b. WAIT 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> after RCS temperature reaches 2000F before depressurizing RCS to

<350 psig.

42 DETERMINE :IF RCS DEPRESSURIZATION IS PERMITTED:

a. Entire RCS - <2000F

a. DO NOT depressurize RCS.

GO TO Step 40.

40 CONTINUED

WISCONSIN PUBLIC SERVICE CORPORATION NO.

E-0-07 KEWAUNEE NUCLEAR POWER PLANT TITLE FIRE IN DEDICATED FIRE ZONE EMERGENCY OPERATING PROCEDURES DATE AUG 04 1998 PAGE 35 of 38 OPERATOR ACTIONS I CONTINGENCY ACTIONS 43 DEPRESSURIZE RCS TO 100 PSIG:

a. DE-ENERGIZE Pressurizer Heater Group B

b. OPEN PR-2B using Przr PORV Alternate Control Station to reduce RCS pressure

c. WHEN Przr pressure is equal to 100 psig, STOP RCS depressurization

d. ENERGIZE Pressurizer Heater Group B as necessary to maintain 100 psig 44 STABILIZE PLANT AT 180 0 F AND 100 PSIG

-END-

WISCONSIN PUBLIC SERVICE CORPORATION NO.

E-0-07 KEWAUNEE NUCLEAR POWER PLANT TITLE FIRE IN DEDICATED FIRE ZONE EMERGENCY OPERATING PROCEDURES DATE AUG 04 1998 PAGE 36 of 38 TABLE E-0-07-1 REACTOR COOLANT SYSTEM SUBCOOLING PRESSURIZER T-SAT 50 DEG 200 DEG PRESSURE SUBCOOLING SUBCOOLING PSIG DEG F DEG F DEG F 2300 2250 2200 2150 2100 2050 2000 1950 1900 1850 1800 1750 1700 1650 1600 1550 1500 1450 1400 1350 1300 1250 1200 1150 1100 1050 1000 950 900 850 800 750 700 650 600 550 500 657 654 650 647 644 640 637 633 630 626 622 618 614 610 606 602 598 593 588 584 579 574 569 563 558 552 546 540 534 527 520 513 505 497 489 480 470 607 604 600 597 594 590 587 583 580 576 572 568 564 560 556 552 548 543 538 534 529 524 519 513 508 502 496 490 484 477 470 463 455 447 439 430 420 457 454 450 447 444 440 437 433 430 426 422 418 414 410 406 402 398 393 388 384 379 374 369 363 358 352 346 340 334 327 320 313 305 297 289 280 270 LOOP TEMPERATURE I

I

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E 07 KEWAUNEE NUCLEAR POWER PLANT TITLE FIRE IN DEDICATED FIRE ZONE EMERGENCY OPERATING PROCEDURES DATE AUG 04 1998 PAGE 37 of 38 RCS PRESSURE (PSIG) 2400 2200 2000 1800 1600 1400 1200 1000 800 600 400 200 0

100 200 300 400 RCS COLD LEG TEMPERATURE (OF) 500 600 700 Figure E-0-07-1 Cooldown Operating Region WITHOUT Full CROM Cooling

-25oF/HR MAXIMUM COOLO0WN RATE 18-HOUR SOAK ACCEPTABLE OPERATING 30 -HOUR SOAK REGION FOR COOLDOWN 0

WISCONSIN PUBLIC SERVICE CORPORATION NO.

E-0-07 KEWAUNEENUCLEARPOWERPLANT TITLE FIRE IN DEDICATED FIRE ZONE OPERATING PROCEDURE DATE AUG 04 1998 PAGE 38 of 38 RCS PRESSURE (PSIG) 2200 25oF/HR 2200 MAXI[MUM--

COOLDOWN RATE 2000 1800 ACCEPTABLE 1800-

-OPERATING REGION FOR COOLDOWN 1600 1400 1200 1000 800 400 200102030 00 101 0

100 20030040050600 700.

RCS COLD LEG TEMPERATURE (*F)

Figure E-0-07-2 Cooldown Operating Region With Full CRDM Cooling