ML18051A549

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Rev 13 to Emergency Operating Procedure EOP 7, Main Steam Line Break/Main Feedwater Line Break Outside Containment
ML18051A549
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-7, NUDOCS 8308230391
Download: ML18051A549 (6)
v • d • e


Text

NU080983-NL01 ENCLOSURE 2 ATTACHMENT 3 CONSUMERS POWER COMPANY PALISADES PLANT DOCKET 50-255 Emergency Operating Procedure EOP 7 "Main Steam Line Break/Main Feedwater Line Break Outside Containment" (Abridged)

August 15, 1983 5 Pages

PALISADES NUCLEAR PLANT EMERGENCY OPERATING PROCEDURE TITLE:

MAIN STEAM LINE BREAK/MAIN FEEDWATER LINE BREAK OUTSIDE CONTAINNENT Proc No EOP 7

'Revision 13 Page 1 of 3 1.0 SYMPTOMS 2.0 Any one or more of the following symptoms may be present:

a.
b.
c.

An obvious loud noise indicative of a high energy line break containment.

An extreme release of steam within the Auxiliary Building.

Main Feedwater flow, Main Steam flow mismatch on the Steam Generator.

d.

Rapid drop in pressure on the Steam Generators.

e.

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

f.

Safety Injection actuation alarm.

AUTOMATIC ACTIONS

a.

Reactor trip.

b.

Turbine/Generator trip.

c.

Safety Injection System actuation.

d.

Main Steam Isolation Valves close on Steam Generator low pressure (500 psia) ;',,'*E-SOA ;b'*CV-0510 and ;'d*E-SOB ;'d*CV-0501.

e.

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

';;'*E-SOA and/ or ;';*kCV-0703 on ;b'*E-SOB.
f.

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

';;'*CV-0735 on ;b'*E-SOA and/ or ;',,'*CV-07 34 on ;';;'*E-5 OB.
3. 0 UINEDIATE ACTIONS 3.1 Verify Reactor trip, carry out EOP 1, "Immediate Actions".

3.2 Check Safety Injection System initiated, manually initiate if necessary.

3.3 Check that both Main Steam Isolation Valves have closed on Steam Generator low pressure (500 psia) **E-SOA - **CV-0510 and **£-SOB -

'd*cv-oso1.

pa0380-0017a-89-93

3.4 3.5 3.6 3.7 4.0 4.1 4.2 4.3 4.4 4.5 4.6 PALISADES NUCLEAR PLANT EMERGENCY OPERATING PROCEDURE TITLE:

MAIN STEAM LINE BREAK/MAIN FEEDWATER LINE BREAK OUTSIDE CONTAINMENT

!}

Proc No EOP 7 Revision 13 Page 2 of 3 Check that the Feedwater Regulating Valves have closed on Steam Generator low pressure 500 psia (valve position indication only) <'d*E-50A

- *'d*CV-0701 and ;'d*E-50B - ;'*<'*CV-0703.

Check that.the Feedwater Regulating Bypass Valves have closed on Steam Generator low pressure 500 psia (valve position indication only) **E-50A

- *<'*CV-0735 and <'0 '*E-50B - *'d*CV-0734.

Place Turbine Generator Turning Gear Motor ;\\-;'*K-2 Control Switch in "PULL TO LOCK".

ACTIVATE SITE EMERGENCY PLAN.

REFER TO SITE EMERGENCY IMPLEHENTATION PROCEDURE EI-1.

SUBSEQUENT ACTIONS Verify proper actuation of safety injection, Attachment 1.

Verify accident diagnosis per Attachment 2.

Switch Control Room ventilation to recirculation mode to preveht steam intake from outside air.

(Place ;'*<'*HS-1801 to the isolate position.)

Determine which Steam Generator has suffered the break by observing pressure and levels in the Steam Generator.

When the damaged Steam Generator has been identified, immediately stop Auxiliary Feedwater flow to the affected Generator.

Verify that the Component Cooling Water System is still intact and is cooling by observing the Component Cooling Water Header pressure and/or components that are being cooled by the system.

4.7 If Component Cooling Water is lost, follow ~p with "Loss of Component Cooling Water" EOP 4.

4.8 Once the blowdown has essentially stopped, dispatch personnel to open the outside doors to start venting steam from the building.

4.9 When the pressurizer level starts to recover and approaches an indicated level of 30%, start removing the charging pump(s) **P-55A, <'o\\-P-55B and/or <'*~P-55C from operation as necessary by placing the respective handswitches 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

b'*P-55B and/or ;b'*P-55C should be placed to the manual position to obtain manual operation of these pumps, as necessary.

pa0380-0017a-89-93

PALISADES NUCLEAR PLANT EMERGENCY OPERATING PROCEDURE Proc No EOP 7 Revision 13 Page 3 of 3 4.10

. 4.11 4.12 4.13 4.14 TITLE:

HAIN STEAM LINE BREAK/MAIN FEEDWATER LINE BREAK OUTSIDE CONTAINHENT As soon as stable conditions are obtained, most efforts should be directed to restoring operati~n of ~he Component Cooling Water System (if it was lost during the accident).

If the Component Cooling Water System has been verified intact and is supplying cooling water to the containment, open ~~~CV-2009 if it was shut, to establish letdown flow.

If the failed fuel monitor U*;'*RIA-0202) alarms, immediately is~late letdown and sample the Primary Coolant System (ONP 11).

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

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

A Survey should be made after the buildings have been vented to inspect for any damage which may have occurred during the break.

4.15 If conditions allow, reset SIS.

Refer to EOP-1 for required conditions to be met prior to reset.

~

  • 4.16 When 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.

pa0380-0017a-89-93

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CHECKSHEET FOR NINIHUH SAFEGUARDS Equ{pment fed from bus C and/or D/G 1-1 EOP 7, Rev 0 ATTACHNENT 1 2400V

1.

1 HP Safety Injection Pump running ;b'*P-66B ----

2.

1 LP Safety Injection Pump running ;'.-kP-67B ----

3.

1 Component Cooling Water Pump running ;b't'P-52A or *'l*P-52C

4.
5.
6.
7.

1 Service Water Pump running P-7B ----

1 Auxiliary Feedwater Pump running *'i'*P-8A 480V 1 Charging Pump 'i'rl*P-55C ----

4 HP Safety Injection Valves open

c.

0 u

  • 't'M0-3007 _____ ~'t'J*I0-3009 ____ *-!*N0-3011 ____ 'id*M0-3013 z 2 LP Safety Injection Valves open ;'d*N0-3008
  • "kM0-3010 --- 8.
9.

2 Boric Acid gravity feed stops open **110-2169 ____ *":*~10-2170 __ __.I-_

10.

1 Containment Air Cooler recirculation fan 'i'>kV-4A ----

11.

Volume Control Tank Outlet Isolation Valve closed -!.-kM0-2087 ----

OR

'4

~

ll(ita

~

0 Equipment fed from bus D and/or D/G i-2 Z

2400V

12.

1 HP Safety Injection Pump running 'i'rkP-66A or ~~P-66C

~~

13.

1 LP Safety Injection Pump running ;'.~*P-67A ___ _

14.

1 Component Cooling Water Pump running -!.-kP-52B ___ _

15.

1 Service Water Pump running 'i'.-kP-7A or ;'rkP-7C 480V

16.

L. Charging Pumps,.,,,P-55A and *"P-55B ___ _

17.

4 Redundant HP Safety Injection Valves open

-:d*H0-3062

  • 'l*M0-3064 mr~to-3066
~
.no-3068

~---

18.

2 LP Safety Injection Valves open ;'rkN0-3012 ____ *".\\-M0-3014 ___ _

19.

1 Boric Acid Pumped Feed Stop Valve open -!.-:*N0-2140 ----

20.

1 Boric Acid Pump running 'i'rl*P-56A ___ _

21.

3 Containment Air Cooler Recirculation fans running

-;;-,':V-lA

  • -:*v-2A
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Completed By:

Signature Reviewed By:

Shift Supervisor r. * *.

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. *. ' :* ! " : * ' t ~ u

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'~~ l LO Date Date

EOP 7 ATTACHMENT 2 ACCIDENT IDENTIFICATION LARGE BREAKS PRESSURIZER PRESSURE DECREASING RAPIDLY OBSERVE STEAM GENERATOR PRESSURES ABNORMALLY LOW IN ONE OR BOTH STEAM GENERATORS OBSERVE CONTAINMENT PRESSURE

' I STEAM BREAK INSIDE CONTAINMENT I SEE EOP 6 I pa0380-0017c-89 TEAM BREAK OUTSIDE CONTAINMENT I SEE~OP 7 I STEAM GENERATOR PRESSURES INITIALLY NORMAL OR RISING LOCA OR S.G. TUBE RUPTURE OBSERVE CONTAINMENT PRESSURE RADIATION AND SUMP LEVEL LOCA VERIFY HIGH RADIATION AIR EJECTOR DISCHARGE I SEE EOP 8. 1 I 1

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