Text

Rev 1 to Emergency Operating Procedure EOP 1.0, Std Post- Trip Actions
	ML18053A681
Person / Time
Site:	Palisades
Issue date:	08/11/1988
From:	Beverly Smith; CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:	;
Shared Package
ML18053A680	List: ML18053A679; ML18053A681; ML18053A682; ML18053A683; ML18053A684;
References
	EOP-1.0, NUDOCS 8812060078
	Download: ML18053A681 (23)
	v • d • e

OC1188-0207-NL02

1.2()1 0~50002~55 PDC ENCLOSURE 1 Consumers Power Company Palisades Plant Docket 50-255 December 1, 1988 STANDARD POST TRIP ACTIONS (EOP 1. O) 22 Pages

PALISADES NUCLEAR PLANT EMERGENCY OPERATING PROCEDURE Revision and Approval Summary Pree No EOP 1.0 Revision l Date 8/11/88 TITLE:

STANDARD POST TRIP ACTIONS

1.

Prepared

2.

QA Concurrence

~

~Sd 7/#1_38 03?~ ?/;jl Responsible Individual Pate Date

3. Q-List ~) No

4.

PRC Reviewed Recommend Approval (r;~. gf'l.IYr.

f2 a ~._g -~ ~,s 5--~(._-J-if Responsible Department Head Date 1

3t37 Date

5.

Approved*

6.

Word Processing Incorporated

Nt~

1-10-&f rLJ?J Final Approver Date TCN MRN o-88-166 0-88-221

7.

Periodic Review Date Date Date Date Date pa0885-0016e-89*

PALISADES NUCLEAR PLANT EMERGENCY OPERATING PROCEDURE TITLE:

STANDARD POST TRIP ACTIONS Proc No EOP 1.0 Revision 1 Page 1 of 10 1.0 PURPOSE This procedure provides the immediate actions which must be accomplished after an automatic OR manual Reactor Trip.

This is the entry procedure for all EOPs.

2.0 ENTRY CONDITIONS

1.

Reactor Trip alarm (Window 72 on **EK-09)

2.

CRD bottom lights on

3.

Rapid decrease in reactor power

4.

Red trip lights on CRD 1 through 4 clutch power supplies lit

5.

RPS trip logic lights on

6.

RPS trip setpoint(s) exceeded 7~

Licensed operator evaluation indicates conditions warrant a reactor trip paQ885-0016a-89

tP.a I

PALISADES NUCLEAR PLANT EMERGENCY OPERATING PROCEDURE Proc No EOP 1.0 Revision 1 Page 2 of 10 TITLE:

STANDARD POST TRIP ACTIONS IMMEDIATE ACTIONS Instructions

1.

Push REACTOR TRIP push button (C-02 OR C-06).

2.

IF both Main Feed Pumps are operating, THEN stop one Main Feed Pump.

3.

WHEN Tave is decreasing toward 525°F, THEN stop remaining Main Feed Pump.

4.

Verify Reactivity Control by the following criteria:

a.

Reactor power decreasing AND

b.

Negative startup rate.

AND

c.

Maximum of one (1) full length CRD NOT fully inserted.

_I_

NA NA NA Contingency Actions

1.

None

2.

None

3.

None

4.

IF any criterion NOT met, THEN perform the following as necessary:

a/b.

Commence emergency boration I.

c.l) Push REACTOR TRIP push buttons (C-02 AND C-06).

OR

2)

Open CRD Clutch Power Feeder Breakers (**RPS 42-1 AND

":~':RPS 42-2).

OR

3)

Set all CRD clutch power toggle switches to CLUTCH OFF.

OR

4)

Commence emergency boration.*

pa0885-0016a-89

PALISADES NUCLEAR PLANT EMERGENCY OPERATING PROCEDURE TITLE:

STANDARD POST TRIP ACTIONS Pree No EOP 1.0 Revision 1 Page 3 of 10 I

. Instructions I

Contingency Actions

5.

Verify Vital Auxiliaries-Electric by the following criteria:

a.

Main Turbine Stop AND Governor Valves are closed.

AND

b.

Main Generator Output Breakers open (25F7 AND 25H9).

AND

c.

Busses lC AND lD auto transferred to Start-Up Power.

AND

d.

Busses *LA AND 18 AND lE auto transferred to Start-Up Power.

AND

e.

D/Gs 1-1 AND 1-2 operating at rated frequency.

pa0885-0016a-89

5.

IF any criterion NOT met, THEN perform the following as necessary:

a.

Manually trip. Main Turbine at C-01 OR on turbine pedestal.

b.

Open Main Generator* Breakers at C-01.

c.l) Verify Bus lC OR lD energized by Diesel Generators (D/Gs).

OR

2)

Manually transfer Bus lC OR lD onto Start-Up Power.

OR

3)

Manually energize Bus lC OR lD from D/G(s).

d.l)

Manually transfer Buses AND lB AND lE onto Start-Up Power.

AND

2)

IF Start-Up Power

emains NOT available, THEN close both MSIVs.

e.

Start D/Gs l-1 AND 1-2.

lA

~I PALISADES NUCLEAR PLANT EMERGENCY OPERATING PROCEDURE Proc* No EOP l. 0 Revision l Page 4 of 10 TITLE:

STANDARD POST TRIP ACTIONS I

Instructions

6. Verify PCS Inventory Control by the following criteria:

a. Pressurizer (PZR) level is greater than 20%.

AND

b.

Pressurizer Level Control System (PLCS) maintaining OR restoring level band of 40% to 60%

c. Loop TH at least 25°F subcooled t.

t IF at least one PCP operating.

pa0885-0016a-89 I

Contingency Actions

6.

IF any criterion NOT met, THEN perform the following as necessary:

a/b~ Operate.PLCS to restore PZR level to 40% to 60%.

c. Verify Qualified CETs at least 25°F subcooled.

7.

PALISADES NUCLEAR PLANT EMERGENCY OPERATING PROCEDURE Proc No EOP 1.0 Revision l Page 5 of 10 TITLE:

STANDARD POST TRIP ACTIONS Instructions Verify PCS Pressure Control by the following criteria:

a.

Pressurizer Pressure Control System (PPCS) maintaining PZR pressure between 1650 to 2185 psia.

I

7.

Contingency Actions IF criterion is NOT met, THEN perform the following as necessary:

a.l) Operate PZR heaters AND PZR spray to maintai~

limits of Attachment 2.

2)

IF PZR pressure less than 1605 psia, THEN verify SIAS initiated (Refer to Attachment 3).

3)

IF *PZR pressure less than 1300 psia, THEN stop PCPs as needed to establish one PCP operating in each loop.

(Preferably **P-508 AND

- P'-SOC operating).

4)

IF PZR pressure less than minimum PCP operation limits per THEN stop all PCPs.

pa0885-0016a-89 I

PALISADES NUCLEAR PLANT EMERGENCY OPERATING PROCEDURE TITLE:

STANDARD POST TRIP ACTIONS Proc No EOP 1.0 Revision 1 Page 6 of 10

._L_

Instructions I

Contingency Actions

a.

Verify Core Heat Removal via Forced Circulation by the following criteria:

a.

At least one PCP

-operating.

AND

b.

Loop ~T (TH-Tc) is less than 10°F.

AND

c.

Loop TH at least 25°F subcooled t.

8.

IF Forced Circulation is NOT possible, THEN verify Nat~l Circulation developing by the following criteria:

a.

Core ~T (Qualified CETs-Tc) is less than 50°F.

AND

b.

Loop THS AND Loop Tes constant OR lowering*.

AND

c. Qualified CETs at least 25°F subcooled. -

AND

d.

Difference between Loop THS --

AND Qualified CETs is less than l5°F.

I

~I Loop THs AND Tes will rise for approximately ten to fifteen minutes following Loss of Forced Circulation T IF at least one PCP operating.

pa0885-0016a-89

I

9.

PALISADES NUCLEAR PLANT EMERGENCY OPERATING PROCEDURE Proc No EOP 1.0 Revision 1 Page 7 of 10 TITLE:

STANDARD POST TRIP ACTIONS

- Instructions Verify PCS Heat Removal by the following criteria:

a.

At least one S/G has:

1). Auxiliary Feedwater (AFW) flow available.

AND

2) a) Level being main-tained in normal band (30% to 70%).

AND OR b)

Level greater than

-84% AND being recovered to normal band *

b.

Tave is between 525°F to 545°F.

AND

c.

S/G pressures are between 800 psia to* 980 psia.

I

9.

Contingency Actions IF any criterion is NOT met, THEN perform the following as necessary:

a.

Operate at least one AFW Pump.

b.

Operate Turbine Bypass Valve OR Atmospheric Steam Dump Valves to control Tave between 525°F to 545°F.

c.l)

IF S/G pressure less than.

800 psia, THEN close both MSIVs *

. 2)

IF S/G p~essure less than 500 psia, THEN verify Main Steam Isolation Signal initiated (Refer to Attachment 3)

pa0885-0016a-89

PALISADES NUCLEAR PLANT EMERGENCY OPERATING PROCEDURE TITLE:

STANDARD POST TRIP ACTIONS Proc No EOP 1.0 Revision 1 Page 8 of 10

_I_

- I'nstructions I

Contingency A~tions

10. Verify Containment Isolation by the following criteria:

a.

Containment. pressure less than 1.0 psi*g AND

b.

C-ontainment Area Monitors NOT alarming.

AND

c.

Condenser Off Gas Monitor NOT alarming (**RIA-0631).

AND

d.

Steam Generator Slowdown Monitor NOT alarming

(**RIA-0707).

AND

e.

Main Steam Line Monitors NOT alarming ('f-"*RIA-2323 AND **RIA-2324).

11. Verify Containm~nt Atmosphere by the.following criteria:

a. Containment temperature less than 140°F.

AND

b.

Containment pressure less than 1. 0 psig.

pa0885-0016a-89

10.

IF any criterion is NOT met, THEN perform the following as necessary:

a.

IF CQntainment pressure is greater than 3.T psig, THEN verify Containment Isolation AND SIAS initiated (Refer to Attachment 3.).

b.* IF Containment radif tion.

incre*ses to 1 x 10 R/hr THEN verify Containment Isolation initiated (Refer to Attachment 3.).

c.

None

d.

Verify S/G Slowdowns isolated (Refer to ).

e.

None 11~

IF any criterion is NOT met, THEN perform the following as necessary:

a/b.l) Align Containment Air Coolers for Accident Condition Operation.

2)

IF Containment pressure TS greater than 3.7 psig, THEN open Containmen*t Spray Valves (**CV-3001 AND

- CV-3002) AND start Containment Spray Pumps

I

12.

PALISADES NUCLEAR PLANT EMERGENCY OPERATING PROCEDURE Proc No EOP 1.0 Revision 1 Page 9 of 10 TITLE:

STANDARD POST TRIP ACTIONS

- Instructions I

Verify Vital Auxiliaries-Water

12.

by the following criteria:

a.

At least two Service Water Pumps operating AND both Critical SW Headers in operation.

AND

b.

At least two CCW_

Pumps operating.

Contingency Actions l£. any criterion NOT met, THEN perform the following as necessary:

a.

Start available Service Water Pump.

b.

Start available CCW Pumps.

13.

Verify Vital Auxiliaries-Air by the following criteria:

13.

IF criterion NOT met, THEN perform the following as necessary:

a.

Instrument Air pressure greater than 80 psig.

a.l) Start available Instrument Air Compressors.

\\

2)

IF Feedwater Purity_

Building Air supply is available, THEN open

~~cv-1221

pa0885-0016a-89

4.0 OPERATOR ACTIONS PALISADES NUCLEAR PLANT EMERGENCY OPERATING PROCEDURE TITLE:

STANDARD POST TRIP ACTIONS Proc No EOP 1.0 Revision l Page 10 of 10 I

Instructions I

Contingency Actions

1.

Commence Emergency Shutdown Checklist (Refer to GOP 10).

2.

Refer to EI-1, "Emergency Implementation Procedure".

3.

IF the following conditions are met, THEN go to EOP 2.0, "Reactor Trip Recovery":

a.

All Instructions Column criteria are satisfied.

AND

b.

YOl energized.

AND

c.

Control Room is habitable.

NA

1.

NA

2.

3.

END OF EOP 1.0 STEPS pa0885-0016a-89 None None Go to Attachment l '

Diagnostic Flowchart.

EVENT DIAGNOSTIC FLOW CHART POWER OPERATIONS EVENT YES NO PERFORM "STAN[)ARD POST TRIP ACTIONS" EOP 1.0 YES GOTO "REACTOR TRIP RECOVERY" EOP 2.0 AREALL INSTRUCTIONS COLUMN CRITERIA SATISFIED ANQ.

YOl ENERGIZED?

YES NO CD*.

GO TO "REACTOR TRIP RECOVERY

EOP2.0 ANll REFER TO ONP 25.1 NO Pree No EOP 1.0 Revision 1 Page 1of8 YOU ARE HERE NO GOTO "FUNCTIONAL RECOVERY PROCEDURE" EOP 9.0 ANll REFER TO ONP 25.2

YES YES YES EVENT DIAGNOSTIC FLOW CHART Proo No EOP 1.0 Revision 1 NO NO NO Page 2 of 8 GOTO "FUNCTIONAL RECOVERY PROCEDURE" EOP 9.0

YES YES EVENT DIAGNOSTIC FLOW CHART Pree No EOP 1.0 Revision 1 NO NO Page 3 of 8 GOTO "FUNCTIONAL RECOVERY PROCEDURE" EOP 9.0 CONSIDER "ELECTRICAL EMERGENCY RECOVERY" EOP 3.0

YES YES YES EVENT DIAGNOSTIC FLOW CHART NO NO NO Pree No EOP 1.0 Revision 1 Page 4 of 8

EVENT DIAGNOSTIC FLOW CHART 4

YES NO YES NO CONSIDER "LOSS OF ALL FEEDWATER" EOP7.0 8

Proo No EOP 1.0 Revision 1 Page 5 of 8 CONSIDER "LOSS OF FORCED.

CIRCULATION RECOVEl_lY" EOP8.0

YES EVENT DIAGNOSTIC FLOW CHART YES GOTO "FUNCTIONAL RECOVERY PROCEDURE" EOP 9.0 CONSIDER "EXCESS STEAM DEMAND EVEN"r EOP6.0 NO CONSIDER "LOSS OF COOLANT ACCIDENT RECQVERY" EOP4.0 Proe No EOP 1.0 Revision 1 Page e of 8 NO

~

"C:.

I

~

I

~

CONSIDER "STEAM GENERATOR YES EVENT DIAGNOSTIC FLOW CHART NO TUBE RUPTURE" EOP 5.0 YES NO YES NO Proo No EOP 1.0 Revision 1 Page 7 of 8 CONSIDER "LOSS OF COOLANT ACCIDENT RECOVERY" EOP4.0 GOTO "FUNCTIONAL RECOVERY PROCEDURE" EOP 9.0

GOTO APPROPRIATE EOP (REFER TO NOTE)

YES EVENT DIAGNOSTIC FLOW CHART DIAGNOSIS OF ONE EVENT APPARENT AMl YOl ENERGIZED?

(REFER TO NOTE)

NO Proc No EOP 1.0 Revision 1 Page 8 of 8 GOTO "FUNCTIONAL RECOVERY PROCEDURE" EOP 9.0 NO.IE; IE YOl NQI.ENERGIZED A.ml.LOSS OF ALL AC POWER IS THE ONLY EVENT THAT IS APPARENT, lliENEOP 3.0 MAY BE IMPLEMENTED

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ACTUATION CIRCUIT VERIFICATION Proc No EOl? 1.0 Revision 1 Page 1 of 1

1.

SIAS INITIATION VERIFICATION NOTE:

Loss of Preferred AC Bus Y20 OR Y30 results in Loss of SIAS Initiation Circuit (Y20 =Right Channel; Y30 =Left Channel)

a.

Auto:

Window 42 on **EK-13.

b.

Manual':

Push Left AND Right INJECTION INITIATE pushbuttons on -:d:EC-13.

2.

MAIN STEAM ISOLATION VERIFICATION

3.

NOTE:

a.

Verify closed OR close the following valves:

1)

Both MSIVs

2)

Main Feedwater Regulation AND Bypass Valves on affected S/G(s) only:

>':>~CV-0701 AND *>':CV-0735 (I A' S/G).

OR

- CV-0703 AND ~'"*CV-0734 ('B' S/G)

CONTAINMENT ISOLATION VERIFICATION Loss pf Preferred AC Bus YlO OR Y40 results in Loss of Containment Isolation Circuit (YlO = Left Channel; Y40 = Right Channel)

a.

Auto:

Window 26 on **EK-11.

b.

Manual:

1)

Push Left AND Right HIGH RADIATION INITIATE pushbuttons on **EC-13.

2)

IF CHP initiated, THEN close the following valves:

a)

Both MSIVs b)

CCW Isolation Valves (**CV-0910 AND >b~CV-0911 AND **CV-0940).

4.

S/G SLOWDOWN ISOLATION VERIFICATION

a. Verify closed OR close the following valves:

- CV-0704 (Slowdown Tank to Mix Basin Valve)

- CV-0738 (S/G 'B' Surface Slowdown Valve)

- CV-0739 (S/G 'A' Surface Slowdown Valve)

- CV-0770 (S/G* 'B' Bottom Blowdown Valve)

- CV-0771 (S/G 'A' Bottom Slowdown Valve) pa0885-0016d-89

ML18053A681

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