ML18051A546

Rev 14 to Emergency Operating Procedure EOP 1, Reactor Trip.

ML18051A546
Person / Time
Site:	Palisades
Issue date:	08/15/1983
From:	CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Shared Package
ML18051A543	List: ML18051A542 ML18051A544 ML18051A545 ML18051A546 ML18051A547 ML18051A549 ML18051A550 ML18051A551 ML18051A552
References
TASK-15-02, TASK-15-2, TASK-RR EOP-1, NUDOCS 8308230385
Download: ML18051A546 (5)

Text

ENCLOSURE 2 ATTACHMENT 1 CONSUMERS POWER COMPANY PALISADES PLANT DOCKET 50-255 Emergency Operating Procedure EOP 1 "Reactor Trip" (Abridged)

August 15, 1983 4 Pages

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PALISADES NUCLEAR PLANT Proc No EOP 1 EMERGENCY OPERATING PROCEDURE Revision 14 Page 1 of 4 TITLE: REACTOR TRIP

• This procedure applies to a reactor trip initiated from one or more normal inputs to the Reactor Protective System, with standby power available at the time of the trip.

1.0 SYNPTOMS

a. Any one or more of the Reactor Protection Trip (RPS) alarms.  :.**~

• ~

b. Control Rod lower electrical limit lights (green). ~

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c. Control Rod positions indicate near zero.

d. Various other alarms may be present, depending on the situation u

causing the trip.

2.0 AUTOMATIC Turbine/Generator trip causes:

a. Fast transfer of station power to startup power.

b. Cooling tower fanstrip .

• 3.0 3.1

c. MSR inlet valves closed. '1d*E-9A *'*kCV-0594, *b'*E-9B *'d*CV-0595,

-1d*E-9C '1d*CV-0596 and '1d*E-9D -1d*CV-0597.

IMMEDIATE Insure the Full Length Control Rods are indicating fully inserted and that reactor power is decreasing.

3.2 Verify turbine trip and generator breakers opened; manually trip the turbine, then generator, if necessary.

3.3 Verify both Emergency Diesel Generators have started.

3.4 Trip one Main Feed Pump if both are running.

3.5 Trip the other Main Feed Pump as T-avg nears 525°F.

3.6 If safety injection has been initiated, trip all Primary Coolant Pumps after insuring that the Reactor has been tripped~ 5 seconds. Follow up with this procedure and Natural Circulation Procedure, ONP 21 .

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PALISADES NUCLEAR PLANT Proc No EOP 1 EMERGENCY OPERATING PROCEDURE Revision 14 Page 2 of 4 TITLE: REACTOR TRIP CAUTION:

\

Do not exceed 112 amps on **P-8A (motor driven Auxiliary Feedwater Pump).

3.7 Insure and/or establish Auxiliary Feedwater flow to restore normal level in the Steam Generators.

4.0 SUBSEQUENT 4.1 Transfer plant power sources from station power transformers to startup transformers. Observe switchyard power conditions closely for instabilities du~ to the loss of plant output, which could r~sult in a loss of the startup power source.

STATION POWER BREAKERS OPEN BUS lA  ;'**252--101 lB  ;'d*252--201 IC  ;'d'152--105 ID  ;';-;152--203

• IE  ;'d'152--302 STARTUP POWER BREAKERS CLOSE BUS IA **252--I02 1B  ;';-;';-252--202 IC  ;';-;152"".-I06 ID  ;'d'152--202 IE  ;':;152--303

4. 2 Insure Steam Dumps, ;':;'*E-SOA ;'.-;'*CV-0781 and ;'d*CV-0782, ;';-;':£-SOB ;'d*CV-0779 and ;';-;'*CV-0780 and/or Bypass Valve ;b'*CV-0511 open and are controlling steam pressure to 900 psia.

4.3 To restore Pressurizer pressure and level insure:

a. Maximum charging and minimum letdown flow established.

b. Pressurizer heaters on (proportional).

c. Pressurizer Spray Valves closed.

4.4 Insure PORV's and/or Pressurizer Relief Valves are closed by oberving and verifying the following:

a. PORV Position Indication is closed .

b. PORV Isolation Valves indicate closed - ;';-;'*MO-I042A, ;b'*M0-1043A.

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PALISADES NUCLEAR PLANT Proc No EOP 1 EMERGENCY OPERATING PROCEDURE Revisior>> 14 Page 3 of 4 TITLE: REACTOR TRIP

c. Observe Relief Valve Line Discharge temperatures.

d. Quench Tank level, pressure and temperature indicates normal conditions.

e. Acoustic Monitor Panel ;'c;'*EC-51 is clear of alarms.

4.5 Insure Turbine Stop Valves and MSR Inlet CV's are closed, ;'~'cE-9A

'd*CV-0594, ;h'*E-9B -,b'*CV-0595, ;'d*E-9C .,.,-

.cV-0596 and -,'d*E-9D .,.,.,.,CV-0597.

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4.6 Insure Steam Dump Valves, **E-50A **CV-0781 and **CV-0782, **E-50B  ::~~

'd*CV-0779 and .,.,.,'*CV-0780. close proportionally as T-avg is reduced.

4.7 On low S/G press of 500 psi insure:

a. MSIV's close .,*,.,*,E-50A, ;'d*CV-0510, ;'d*E-50B and .,.,.,.,CV-0501.

b. Feedwater regulating valves close, ;'~'*E-50A, ;'c;'*CV-0701, ;'c;'*E-50B,

h'*CV-0703 (observe valve position indication only).

c. Feedwater regulation bypass valves close ;h'cE-50A, ;'d*CV-0735 and

-,'d*E-50B, -,'d*CV-0134 (observe valve position indication onI-j)-.

• NOTE: Dryout of a Steam Generator(s) will be noticeable from:

a.

b.

Wide Range Steam Generator level less than -125%.

Decrease in Steam Generator(s) pressure below P sat of the Primary

c. Abnormal increase in Primary System temperature and pressure

d. Increase in letdown flaw If dryout should occur, the affected Steam Generator is to be considered inoperable.

4.8 REFER TO SITE EMERGENCY IMPLEMENTATION PROCEDURE EI-1. ACTIVATE SITE EMERGENCY PLAN IF NECESSARY.

4.9 Insure all Cooling Tower fans have tripped.

NOTE: The valves listed below will automatically reclose upon SIS reset if both of their associated hand switches are in the closed position.

Valve reclosure may be undesired since cooling water to the indicated equipment will be terminated. If necessary, either of the two hand switches may be placed in the open position to prevent the associated valve from reclosing upon SIS reset.

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PALISADES NUCLEAR PLANT Proc No EOP 1 EMERGENCY OPERATING PROCEDURE Revision 14 Page 4 of 4

• TITLE: REACTOR TRIP Control Room  ;';-;'*EC- 3 3 Panel Valve Handswitch '* Handswi tch Service

'd*CV-0825  ;'d*HS-0825A  ;'.-;'*HS-0825B SW to E ESF Rm Clr

'.-kCV-0878  ;'d*HS-0878A  ;'d*HS-0878B SW to W ESF Rm Clr

.......:.-cv-093 7  ;'.-;'*HS-09 3 7A M*HS-0937B ccw to SDC Hx

'*kCV-09 38  ;'.-;'*HS-0938A  ;'d*HS-0938B ccw to SDC Hx

'd*CV-0913 ;b'*HS-0913A  ;'dHS-0913B ccw to seal CLG

'd*CV-0950 ;b\-HS-0950A  ;'n'*HS-0950B ccw to seal CLG 4.10 If safety injection has actuated, reset only after all of the following conditions are met, insuring that hot and cold leg temperatures are at least 50°F subcooled per Attachment #2 (also posted in the Control Room) using all available instrumentation including all hot and cold leg temperatures, several incore thermocouples, PCS Pressure.

(a) The cause of the low-pressure condition is known and corrected.

(b) The reactor is shutdown and will remain shutdown.

(c) Pressurizer level is greater than 20% and is returning to normal.

(d) T-avg is stable or increasing and is less than 545°F.

(e) Pressurizer pressure is greater than 1700 psia and is returning to normal.

If after a reset of the Safety Injection System 50°F subcooling cannot be maintained, restart the High Pressure Safety Injection System.

4.11 If standby power. is .available and stable shutdown conditions are assured, shutdown one Emergency Diesel Generator. Shutdown the second Emergency Diesel Generator after the Main Turbine is on turning gear.

4. 12 After safety injection has been reset and equipment returned to "post SIS reset" condition per Attachment 1, refer to ONP 21, Step 4.0(4) to restart PCPs.

4.13 As makeup is needed to ;'n'*T-2 (Condensate Storage Tank) for Auxiliary Feedwater Pumps, refer to SOP 12.

4.14 Complete this procedure by executing Emergency Shutdown Checklist G CL 10.

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