ML18051A547

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Rev 14 to Emergency Operating Procedure EOP 6, Main Steam Line Break/Main Feedwater Line Break Inside Containment
ML18051A547
Person / Time
Site: Palisades Entergy icon.png
Issue date: 08/15/1983
From:
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Shared Package
ML18051A543 List:
References
TASK-15-02, TASK-15-2, TASK-RR EOP-6, NUDOCS 8308230387
Download: ML18051A547 (9)
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Text

ENCLOSURE 2 ATTACHMENT 2 CONSUMERS POWER COMPANY PALISADES PLANT DOCKET 50-255 Emergency Operating Procedure EOP 6 "Main Steam Line Break/Main Feedwater Line Break Inside Containment" (Abridged) 8308230387 830815 PDR ADOCK 05000255 p

PDR NU080983-NL01 August 15, 1983 8 Pages

PALISADES NUCLEAR PLANT EMERGENCY OPERATING PROCEDURE TITLE:

MAIN STEAM LINE BREAK/MAIN FEEDWATER LINE BREAK INSIDE CONTAU..1'1ENT Proc No EOP 6 Revision 14 Page 1 of 3 1. 0 STI1PTOMS 2.0 Any one or more of the following symptoms may be present:

a.

Main feedwater flow - main steam flow mismatch on the Steam Generators **E-50A and **E-50B.

b.

Rapid drop in pressure on the Steam Generators.

c.
d.
e.
f.
g.
h.

The affected Steam Generator will go to essentially 0 pressure, the intact Steam Generator will return to pressure.

Containment High Pressure Alarm.

Safety Injection Actuation Alarm.

Containment Spray Actuation Alarm (Containment Spray Valve open).

Containment Isolation Alarm.

No increase in cQntainment radiation on Containment IsolaUion Area Radiation Monitors.,.,.,.,RIA-1805,.,*,;,RIA-1806,.,.,.,',RIA-1807 and ;h'*RIA-1808 (other area radiation monitors inside the Containment may show an increase in radiation because of environmental effects_) __ _

AUTOMATIC ACTIONS

a.

Reactor trip.

b.

Turbine/Generator trip.

c.

Safety Injection actuation.

d.

Containment Spray actuation.

e.

Containment Isolation.

f.

Main Steam Isolation Valves close on Containment High Pressure (5.3 psig), Steam Generator low pressure (500 psia) **E-50A **CV-0510 and

-,'d:E-50B -,'d*CV-0501.

g.

Feedwater Regulating Val~es close on Steam Generator Low Pressure to the Steam Generator with the low pressure (500 psia) **CV-0701 on

    • E-50A and/or **CV-0703 on **E-508.
h.

Feedwater Regulating Bypass Valves close on Steam Generator Low Pressure to the Steam Generator with the low pressure (500 psia)

    • CV-0735 on **E-50A and/or **CV-0734 on **E-508.

pa0380-0016a-89-93

  • 3.0 3.1 3.2 3.3 3.4 3.5 3.6 3.7 PALISADES NUCLEAR PLA1~T EMERGENCY OPERATING PRDCEDL?-E TITLE:

MAIN STEAM LINE BREAK/HAIN FEED\\.iATER LINE BREAK INSIDE CDNTAIN1'1ENT IM.MEDIATE ACTIONS Verify reactor trip, carry out EDP 1, "Immediate Actions".

Proc No EDP 6 Revision 14 Page 2 of 3 Check Safety Injection initiated, manually initiate if necessary.

Check Containment Spray initiated.

Check that the Main Steam Isolation Valves have closed on Containment High Pressure (5.3 psig), Steam Generator low pressure (500 psia).

  • '**'*E-50A *';-;'*CV-0510 and *b'*E-50B *b'*CV-0501.

Check that the Feedwater Regulating Valves have closed on St~am Generator low pressure 500 psia, (valve posi~ion indication only)

    • E-50A **CV-0701 and **E-50B **CV-0703.

Check that the Feedwater Regulating Bypass T~-alves have closed on Steam Generator low pressure 500 psia (valve posi~ion indication only)

    • E-50A **CV-0735 and **ESOB **CV-0734.

Check Containment Isolation ini tiate<il. *

3. 8 Place Turbine Generator Turning Gear Hotor -::.-.:-K-2 Control Switch in "PULL
  • ~

TO LOCK".

3

  • 9 ACTIVATE SITE E~IERGENCY PLAt~.

REFER TO SIT::: I.f1ERGEXCY U1PLEHENTATION PROCEDURE EI-1.

4.0 NOTE:

4. 1 4.2 4.3 4.4 SUBSEQUENT ACTIONS Steam Generator and Pressurizer level indicaLion will be affected by containment pressure and temperature during accident conditions.

Use Attachments 1 thru 5 to calculate actual le...-el conditions.

Verify actuation of the following:

a.

Safety Injection (Attachment 6).

b.

Containment Spray (Attachment 7).

c.

Containment Isolation (Attachment 8).

Verify accident diagnosis per Attachment 9.

Place Iodine Removal System **T-0102 Control Valve Switches, **CV-0437A and *'**'*CV-0437B to the "Defeat Auto" o * ~

  • p SlLlO::l.

Determine which Steam Generator has the bre.::K by observing pressures and levels in the Steam Generators.

pa03SO-OOI6a-89-93

4.5 4.6 4.7 4.8 PALISADES NUCLEAR PLANT EHERGENCY OPERATING PROCEDURE TITLE:

.HAIN STEAM LINE BREAK/MAIN FEEDWATER LINE BREAK

Check Containment Air Coolers functioning properly.

If containment pressure is less than or equal to 20 psig, then Stop the Containment Spray Pump (s),.,.,.,P-54/\\,,*,,*,P-54B and,*,,*,P-54C.

If the containment pressure starts to increase, restart the Containment Spray Pump(s) as necessary to stop the pressure increase.

As soon as conditions allow (containment pressure is less than or equal to four (4) psig) reset CHP, insure ""'""'P-54A, """'*P-54B and,*,,*,P-54C are off then close Containment Spray Header Valves **CV-3001 and **CV-3002.

When the pressurizer level starts to recover and approaches an indicated level of 30% start removing the Charging Pump(s) ""'""'P-SSA, "P-SSB and/or

    • P-55C from operating as necessary by placing the respective hand switches to the stop position.

The Charging Pumps can be started and stopped as necessary to control the pressurizer level near normal zero power level of 42% (indicated level).

The Selector Switches for """~P-55B and/or **P-SSC should be placed to the manual position to obtain manual operation of these pumps, as necessary.

4.9 If conditions allow, reset SIS.

R~fer to EOP-1 for required conditions to be met prior to reset.

4.10 NOTE:

4.11 4.12 4.13 When CHP and/or SIS has been reset and component cooling water has been verified going to the Containment, open ;'d'CV-2009 to establish letdown flow.

If the Failed Fuel.Honi tor 'b'*RIA-0202 alarms, immediately isolate letdown and sample the Primary Coolant System per ONP 11.

Do not attempt to operate LPSI valve ;'d'.t-10-3008 if the water level in the containment is greater than 85% indicated.

When conditions allow, place the Charging and Letdown in automatic per SOP 2A.

After letdown has been established for approximately 15 minutes, have a PCS boron sample taken to verify Cold Shutdown Boron Concentration.

When the Containment pressure and the Primary Coolant System pressure, temperature and inventory are under control, exit this procedure and initiate cooldown of the PCS using the Natural Circulation Procedure ONP 21.

pa0380-0016a-89-93

CHECKSHEET FOR MINHfill1 SAFEGUARDS Equipment fed from bus C and/or D/G 1-1 ("k;'*K-6AG) 2400V

1.

1 HP Safety Injection Pllinp running ;'d*P-66B

2.

1 LP Safety Injection Pump running ;HP-67B

3.

1 Component Cooling Water Pump running ;'d*P-52A

4.

1 Service Water Pump running ;'d*P-7B

5.

1 Auxiliary Feedwater Pump running ;',;'*P-8A 480V

6.

1 Charging Pump ;'.-;'*P-55C

7.

4 HP Safety Injection Valves open or ;'d*P-52C Proc No EOP 6 Revision 14 Page 1 of 1

'.-;'*M0-3007
',;"MO-3009
'd*M0-3011
',;"M0-3013
8.

2 LP Safety Injection Valves open ;';-;'*:t-10-3008

'd*M0-3010
9.

2 Boric Acid gravity feed stops open **M0-2169

10.

1 Containment Air Cooler recirculation fan **V-4A

11.

Volume Control Tank Outlet Isolation Valve closed ;';-;';-:t-10-2087 OR Equipment fed from bus D and/or D/G 1-2 (;'d*K-6BG) 2400V

12.

1 HP Safety Injection Pump running ;'d*P-66A or ;'dP-66C

13.

1 LP Safety Injection Pump running ;'**'*P-6 7 A

14.

1 Component Cooling Water Pump running ;'d*P-52B

15.

1 Service Water Pump running ;';-;'*P-7 A or ;'d.-p-7C 480V

16.

2 Charging Pumps ;'d*P-55A and ;';.;P-55B

17.

4 Redundant HP Safety Injection Valves open

'>;'*M0-3062

<'d*M0-3064

"""M0-3066

"""M0-3068

18.

2 LP Safety Injection Valves open ;',-<'*M0-3012

'
;'*M0-3014
19.

1 Boric Acid Pumped Feed Stop Valve open ;';-;'*MO-2140

20.

1 Boric Acid Pump running ;'d*P-56A

21.

3 Containment Air Cooler Recirculation fans running

',-;'<V-lA
  • '**'*V-3A Completed By:

I

.. ~

Signature Date Reviewed By:

I pa0380-0016g-89-93 Shift Supervisor Date

1.

Complete Attachment 6.

CHECKSHEET FOR MINIMUM SAFEGUARDS WITH CONTAI1~1ENT HIGH PRESSURE

2.

2 Containment Spray Valves open ;':-;',CV-3001 and ;'d:CV-3002

3.

4 Containment Air Cooler High Capacity Service Water Valves open Proc No EOP 6 Revision 14 Page 1 of 1

/E

-id:CV-0864

.,*:-;*,cv-086 7

'
-;',CV-0873
4.

2 Iodine Removal Valves (open after 1 minute time delay)

-i:;'*CV-0437 A

'dCV-0437B and From 2400 V bus lC and/or Diesel Generator 1-1 **K-6AG
5.

2 Containment Spray Pumps ;'d:P-54B

.,*,.,*,P-54C or From 2400 V bus lD and/or Diesel Genera.tor; 1-2* "'"K-6BG

6.

1 Containment Spray Pump.,-,.,*,P-54A Completed By

/

Signature Date Reviewed By

/

Shift Supervisor Date pa0380-0016h-89-93

CONTAINtlENT ISOLATION CHECKLIST Proc No EOP 6 Revision 14 Page 1 of 2 All containment isolation CV's have latching circuits, the hand switches have to be placed to closed position prior to'open position.

VALVE NO

'd<CV-1808

-,',-,',CV-1814

-,'d<CV-1806

'o'<CV-1501
  • Jr-,'<CV-1101
b'<CV-1807
b'<CV-1813

-,',*CV-1805

'drCV-1502

.,,_.,.,cv-1102

.,.,-,',CV-1064

.,.,.,',CV-1103

.,.,.,.,CV-1002

-,',-,',CV-1036

b'<CV-1104

-,'d<CV-0940

'd;CV-1007

.,,_.,.,CV-1038

-,',-,'<CV-1045 pa0380-0016i-89-93 DESCRIPTION Containment Purge Exhaust Isolation Valve Air Room Supply Containment Purge Exhaust Isolation Valve Containment Htg Steam Return Containment Vent Hdr Containment Purge Exhaust Isolation Valve Air Room Supply Containment Purge Exhaust Isolation Valve Containment Htg Steam Return Containment Vent Hdr Clean Waste Receiver Tanks Vent Containment Sump Drain (SIS or CHR)

Component Cooling water Return Primary System Drain Tank Outlet Clean Waste Receiver Tanks Recirc Outlet Clean Waste Receiver Tanks Outlet Containment Sump Drain (SIS or CHR)

Component Cooling Water Return Primary System Drain Tank Outlet Clean Waste Receiver Tanks Recirc Outlet Clean Waste Receiver Tanks Outlet Clean Waste Receiver Tanks Vent u

7

~-

Completed By:

/

I CLOSED Signature Date Time

VALVE NO

-ld*CV-0770

-,'.-:*cV-0767

"'""'*CV-0768 id*CV-1503

b"CV-0738

"'""'"CV-0739

b"CV-0939

-ld*CV-1037

-,b"CV-1358

'd*CV-1001

-,'d*CV-19 11

-ld*CV-2009

"'""*CV-2083

-ld*CV-0155 io"CV-0501

b'<
CV-0510 pa0380-0016i-89-93 CONTAINMENT ISOLATION CHECKLIST DESCRIPTION Steam Generator **E-50B Bottom Blowdown Steam Generator **E-50A Bottom Blowdown Steam Generator -ld*E-50A Bottom Blowdown Steam Generator ;'d*E-50B Bottom Blowdown Containment Htg Steam Inlet Steam Genterator -,',"'E-50B Top Blowdown Steam Generator ;';;'*E-50A Top Blowdown Component Cooling Water Inlet (SIS)

Shield Cooling Surge Tank Fill Clean. Waste Receiver Tanks Inlet Clean Waste Receiver Tanks Recirculation Pree No EOP 6 Revision 14 Page 2 o

(>, u u

z 0 --,_

Inle:;

CLOSED Recirculation Inlet s>

Nitrogen Supply Primary System Drain Tank Primary System Sampling z

Primary System Sampling Letdown Stop Controlled Bleedoff Demineralized Water Supply Main Steam Isolation Valve (on CHP)

Main Steam Isolation Valve (on CHP)

Completed By:

I I

Signature Date Time Pages 1 and 2 Reviewed By:

Shift Supervisor I

Date e

I Time

Proc No EOP 6 Revision 14 Page 1 of 1 ACCIDENT IDENTIFICATION LARGE BREAKS PRESSURIZER PRESSURE DECREASING RAPIDLY.

OBSERVE STEAt1 GENERATOR PRESSURES I

,---~~--- ------_~--------------~---=*~--~

I STEAM GENERATOR PRESSURES ABNOR1'1ALLY LOW IN ONE OR BOTH STEAM GENERATORS J

STEAM LINE RUPTURE OBSERVE CONTAINMENT PRESSURE INITIALLY NORMAL OR RISING I

,I LOCA OR S.G. TUBE RUPTURE I

'U OBSERVE CONTAINHENT PRESSURE RADJ:ATION*AND SUMP LEVEL

~---------------

I INCREASING I NORMAL

_I_N_C_RE----"'A~SI_N_G_I

.~l_N_O_ru~~1A-L-~

\\

/

\\/

STEAfl BREAK I STEAM BREAK INSIDE I

OUTSIDE CONTAHn-IENT CONTAH~MENT I

I

,y I SEE EOP I

6 I I I SEE EOP 7 I pa0380-0016j-89-93

\\

LOCA

,l I SEE EOP 8. 1 i t

I VERIFY HIGH '

RADIATION AIR EJECTOR DISCHARGE

,l S.G.TUBE RUPTURE

\\/

I SEE EOP 8. 2 l

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