ML18053A681

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


Text

ENCLOSURE 1 Consumers Power Company Palisades Plant Docket 50-255 December 1, 1988 STANDARD POST TRIP ACTIONS (EOP 1. O) 22 Pages OC1188-0207-NL02

1.2()1 0~50002~55 PDC

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

1. Prepared 2. QA Concurrence

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

3. --

Q-List ~) No Recommend Approval

4. PRC Reviewed f2 a ~._g -~ ~,s 5--~(._-J-if (r;~ .gf'l.IYr .

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 Proc No EOP 1.0 EMERGENCY OPERATING PROCEDURE Revision 1 Page 1 of 10 TITLE: STANDARD POST TRIP ACTIONS 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

PALISADES NUCLEAR PLANT Proc No EOP 1.0 EMERGENCY OPERATING PROCEDURE Revision 1 Page 2 of 10 TITLE: STANDARD POST TRIP ACTIONS tP.a IMMEDIATE ACTIONS Contingency Actions I Instructions _I_

1. Push REACTOR NA 1. None TRIP push button (C-02 OR C-06).
2. IF both Main Feed Pumps NA 2. None are operating, THEN stop one Main Feed Pump.
3. WHEN Tave is decreasing NA 3. None toward 525°F, THEN stop remaining Main Feed Pump.
4. Verify Reactivity Control 4. IF any criterion NOT met, THEN by the following criteria: perform the following as necessary:
a. Reactor power decreasing a/b. Commence emergency boration I.
  • b.

AND Negative startup rate.

AND

c. Maximum of one (1) c.l) Push REACTOR TRIP push full length CRD buttons (C-02 AND C-06).

NOT fully inserted.

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 Pree No EOP 1.0 EMERGENCY OPERATING PROCEDURE Revision 1 Page 3 of 10 TITLE: STANDARD POST TRIP ACTIONS I . Instructions I Contingency Actions

5. Verify Vital Auxiliaries- 5. IF any criterion NOT met, Electric by the following THEN perform the following as criteria: necessary:
a. Main Turbine Stop AND a. Manually trip. Main Turbine at Governor Valves are closed. C-01 OR on turbine pedestal.

AND

b. Main Generator Output b. Open Main Generator* Breakers Breakers open (25F7 AND at C-01.

25H9).

AND

c. Busses lC AND lD auto c.l) Verify Bus lC OR lD transferred to Start-Up energized by Diesel Power. Generators (D/Gs).

OR .;

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

OR

3) Manually energize Bus lC OR lD from D/G(s).
d. Busses *LA AND 18 AND lE d.l) Manually transfer Buses lA auto transferred to AND lB AND lE onto Start-Up Power. Start-Up Power.

AND AND 2) IF Start-Up Power

emains NOT available, THEN close both MSIVs.
e. D/Gs 1-1 AND 1-2 e. Start D/Gs l-1 AND 1-2.

operating at rated frequency.

pa0885-0016a-89

PALISADES NUCLEAR PLANT Proc* No EOP l. 0 EMERGENCY OPERATING PROCEDURE Revision l Page 4 of 10 TITLE: STANDARD POST TRIP ACTIONS I Instructions I Contingency Actions

6. Verify PCS Inventory Control 6. IF any criterion NOT met, by the following criteria: THEN perform the following as necessary:

Pressurizer (PZR) level is a/b~ Operate.PLCS to restore a.

greater than 20%. PZR level to 40% to 60%.

AND

b. Pressurizer Level Control System (PLCS) maintaining OR restoring level band of 40% to 60%
c. Loop TH at least 25°F c. Verify Qualified CETs at subcooled t . least 25°F subcooled.

~I t IF at least one PCP operating.

pa0885-0016a-89

PALISADES NUCLEAR PLANT Proc No EOP 1.0 EMERGENCY OPERATING PROCEDURE Revision l Page 5 of 10 TITLE: STANDARD POST TRIP ACTIONS Instructions I Contingency Actions

7. Verify PCS Pressure Control 7. IF criterion is NOT met, by the following criteria: THEN perform the following as necessary:
a. Pressurizer Pressure a.l) Operate PZR heaters AND Control System (PPCS) PZR spray to maintai~

maintaining PZR pressure limits of Attachment 2.

between 1650 to 2185 psia.

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 I

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 Attachment 2 THEN stop all PCPs.

pa0885-0016a-89

PALISADES NUCLEAR PLANT Proc No EOP 1.0 EMERGENCY OPERATING PROCEDURE Revision 1 Page 6 of 10 TITLE: STANDARD POST TRIP ACTIONS

._L_ Instructions I Contingency Actions

a. Verify Core Heat Removal via 8. IF Forced Circulation is NOT Forced Circulation by the possible, THEN verify Nat~l following criteria: Circulation developing by the following criteria:
a. At least one PCP a. Core ~T (Qualified CETs-Tc)

-operating. is less than 50°F.

AND AND

b. Loop ~T (TH-Tc) is b. Loop THS AND Loop Tes less than 10°F. constant OR lowering*.

AND AND

c. Loop TH at least 25°F c. Qualified CETs at least subcooled t. --- 25°F subcooled. -

AND

d. Difference between Loop THS --
  • AND Qualified CETs is less than l5°F.

Loop THs AND Tes will rise for approximately ten to fifteen minutes following Loss of Forced Circulation I

~I T IF at least one PCP operating.

pa0885-0016a-89

PALISADES NUCLEAR PLANT Proc No EOP 1.0 EMERGENCY OPERATING PROCEDURE Revision 1 Page 7 of 10 TITLE: STANDARD POST TRIP ACTIONS I - Instructions I Contingency Actions

9. Verify PCS Heat Removal by the 9. IF any criterion is NOT met, following criteria: THEN perform the following as necessary:
a. At least one S/G has: a. Operate at least one AFW Pump.
1) . Auxiliary Feedwater (AFW) flow available.

AND

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

OR b) Level greater than

-84% AND being recovered to normal band *

  • b.

AND Tave is between 525°F to 545°F.

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

AND

c. S/G pressures are between c.l) IF S/G pressure less than.

800 psia to* 980 psia. 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 Proc No EOP 1.0 EMERGENCY OPERATING PROCEDURE Revision 1 Page 8 of 10 TITLE: STANDARD POST TRIP ACTIONS

_I_ - I'nstructions I Contingency A~tions

10. Verify Containment Isolation 10. IF any criterion is NOT met, by the following criteria: THEN perform the following as necessary:
a. Containment. pressure less a. IF CQntainment pressure than 1.0 psi*g is greater than 3.T psig, THEN verify Containment AND Isolation AND SIAS initiated (Refer to Attachment 3.).
b. C-ontainment Area Monitors b.* IF Containment radif tion .

NOT alarming. incre*ses to 1 x 10 R/hr THEN verify Containment AND Isolation initiated (Refer to Attachment 3.).

c. Condenser Off Gas Monitor c. None NOT alarming (**RIA-0631).

AND

d. Steam Generator Slowdown d. Verify S/G Slowdowns Monitor NOT alarming isolated (Refer to

(**RIA-0707). Attachment 3).

AND

e. Main Steam Line Monitors e. None NOT alarming ('f-"*RIA-2323 AND **RIA-2324).
11. Verify Containm~nt Atmosphere 11~ IF any criterion is NOT met, by the.following criteria: THEN perform the following as necessary:
a. Containment temperature a/b.l) Align Containment Air less than 140°F. Coolers for Accident Condition Operation.

AND

b. Containment pressure less 2) IF Containment pressure than 1. 0 psig. TS greater than 3.7 psig, THEN open Containmen*t Spray Valves (**CV-3001 AND
  • pa0885-0016a-89

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

- Instructions I Contingency Actions I

12. Verify Vital Auxiliaries-Water 12. l£. any criterion NOT by the following criteria: met, THEN perform the following as necessary:
a. At least two Service a. Start available Water Pumps operating AND Service Water Pump.

both Critical SW Headers in operation.

AND

b. At least two CCW_ b. Start available Pumps operating. CCW Pumps.
13. Verify Vital Auxiliaries-Air 13. IF criterion NOT met, THEN by the following criteria: perform the following as necessary:
a. Instrument Air pressure a.l) Start available greater than 80 psig. Instrument Air Compressors.
2) IF Feedwater Purity_

Building Air supply is available, THEN open

~~cv-1221 *

  • pa0885-0016a-89

\

PALISADES NUCLEAR PLANT Proc No EOP 1.0 EMERGENCY OPERATING PROCEDURE Revision l Page 10 of 10 TITLE: STANDARD POST TRIP ACTIONS 4.0 OPERATOR ACTIONS I Instructions I Contingency Actions Commence Emergency Shutdown NA 1. None

1. ---

Checklist (Refer to GOP 10).

2. Refer to EI-1, "Emergency NA 2. None Implementation Procedure".
3. Go to Attachment l '
3. IF the following conditions are met, THEN go to EOP 2.0,

--- Diagnostic Flowchart.

"Reactor Trip Recovery":

a. All Instructions Column criteria are satisfied.

AND

b. YOl energized.

AND

c. Control Room is habitable.

END OF EOP 1.0 STEPS

-*pa0885-0016a-89

Pree No EOP 1.0 EVENT DIAGNOSTIC FLOW CHART Attachment 1 Revision 1 Page 1of8

  • POWER OPERATIONS EVENT YES NO PERFORM "STAN[)ARD POST TRIP ACTIONS" EOP 1.0 YOU ARE HERE AREALL INSTRUCTIONS COLUMN CRITERIA NO SATISFIED ANQ.

YOl ENERGIZED?

GOTO "REACTOR TRIP RECOVERY" EOP 2.0 YES NO YES NO CD*. GOTO "FUNCTIONAL RECOVERY PROCEDURE" EOP 9.0 GO TO "REACTOR TRIP RECOVERY ANll EOP2.0 REFER TO ONP 25.2 ANll REFER TO ONP 25.1

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

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

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

Proo No EOP 1.0 EVENT DIAGNOSTIC FLOW CHART Attachment 1 Revision 1 Page 5 of 8 4

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

CONSIDER YES NO "LOSS OF FORCED .

CIRCULATION RECOVEl_lY" EOP8.0

Proe No EOP 1.0 EVENT DIAGNOSTIC FLOW CHART Attachment 1 Revision 1 Page e of 8 YES NO

~

YES NO "C:.I

~

I

~

~

~

. GOTO CONSIDER "FUNCTIONAL RECOVERY "LOSS OF COOLANT PROCEDURE" EOP 9.0 ACCIDENT RECQVERY" EOP4.0 CONSIDER "EXCESS STEAM DEMAND EVEN"r EOP6.0

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

Proc No EOP 1.0 EVENT DIAGNOSTIC FLOW CHART Attachment 1 Revision 1 Page 8 of 8 DIAGNOSIS OF ONE EVENT YES APPARENT NO AMl YOl ENERGIZED?

GOTO (REFER TO NOTE) GOTO APPROPRIATE "FUNCTIONAL EOP RECOVERY (REFER TO NOTE) 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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Proc No EOl? 1.0 Attachment 3 Revision 1 Page 1 of 1 ACTUATION CIRCUIT VERIFICATION

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
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)
3. CONTAINMENT ISOLATION VERIFICATION NOTE: 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
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