ML19224B258

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Emergency Procedure 2202-1.4,Revision 8:loss of Reactor Coolant Flow/Reactor Coolant Pump Trip
ML19224B258
Person / Time
Site: Crane Constellation icon.png
Issue date: 02/08/1979
From:
Metropolitan Edison Co
To: Mullinix W
NRC/IE
References
2202-1.4, TM-0032, TM-32, NUDOCS 7906140304
Download: ML19224B258 (5)


Text

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TMI DOCUMENTS

  1. hh DOCUMENT NO:

COPY MADE ON h

f 0F DOCUMENT PROVIDED BY METROPOLITAN EDISON COMPANY.

Wilda R. Mullinix, NRC 79061403o4 195 076

QD

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CONTROLLS G 2202-i.4 Revision 8

((j..j [:g[L T j _.C 02/08/79 THREE MILE ISLAND NUCLEAR STATION

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UtlIT #2 EMERGENCY PROCEDURE 2202-1.4 APR 2 3 7D LOSS OF RC FLOW /RC PUMP TRIP Table of Effective Pages Pace Dats Revision Pace Date Revision Pace Date R evision 1.0 10/12/78 6

26.0 51.0 2.0 10/12/78 6

27.0 52.0 3.0 10/12/78 6

28.0 53.0 4.0 02/08/79 8

29.0 54.0 5.0 30.0 55.0 6.0 31.0 56.0 7.0 32.0 57.0 8.0 33.0 58.0 9.0 34.0 59.0 10.0 35.0 60.0 11.0 36.0 61.0 12.0 37.0 62.0 13.0 38.0 63.0 14.0 39.0 64.0 15.0 40.0 65.0 16.0 41.0 66.0 17.0 42.0 67.0 18.0 43.0 68.0 19.0 44.0 69.0 20.0 45.0 70.0 21.0 46.0 71.0 22.0 47.0 72.0 23.0 48.0 73.0 24.0 49.0 74.0 25.0 50.0 75.0 Unit 1 StaH Recommends Approval Unit 2 Staff Recommends Approval Approval Date

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Approval M

Date

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Cognizant Oept. Head Cognizant Dept. Head Unit 1 PORC Recommends Approval Unit 2 PORC Recommends Approval I/ ]/7 ?

SJW" Date N

Date Chairman of PORC Chairman of PORC

-t Unit 1 Superintendent Approval Unit 2 Superintende'71t Approval

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,% e:trec Date 77 Date l

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Manager Generation Quality Assurance Ap6roval

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Date

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195 0 &^"-~"

A.

2202-1.4 Revision 6 10/12/78 THREE MILE ISLAND NUCLEAR STATION APR 2 3 1979 UNIT #2 EMERGENCY PROCEDURE 2202-1.4 LOSS OF RC FLOW /RC PUMP TRIP 1.0 SYMPTOMS 1.1 Annunciator Alarm for Auto Trip of R.C.P.

1.1.1 Instantaneous Phase Overcurrent 1.1.2 Time Delay Phase Overcurrent 1.1.3 Thermal Overload 1.1.4 Running Undervoltage 1.1.5 Phase Balance 1.1.6 Differential Overcurrent.

1.1.7 Loss of Seal Injection and I.C. Cooling Water.

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1.2 R.C. Pump Light above Control Switch. goes from red to green.

1.3 Condi tiens requiring manual trip of R.C. Pump.

1.3.1 Motor Guide bearing temperature exceed 185 F.

RCP Computer Point Upper Bearing Lower Bearing lA 0434 0438 2A 0435 0439 1B 0436 0440 2B 0437 0441 1.3.2 Motor thrust bearing temperature exceed 200 F.

RCP Computer Point Downthrust Upthrust 195 078 1.0

3 s

2202-1.4 Revision 6 10/12/78

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lA 0426 0430 APR 2 3 1979 2A 0427 0431 18 0428 0432 2B 0429 0433 U

1.3.3 Motor stator temp exceeds 302 F (150 C).

RCP Computer Point 1A 0442 2A 0443 18 0444 2B 0445 1.3.4 RCP seal staging water temp exceeds 185 F.

RCP Computer Point lA 0418 2A 0419 1B 0420 2B 0421 1.3.5 Air cooler leak detector alarms.

1.3.6 Shaft vibration exceeds:

a.

26 mils for 1 or 2 pump per loop operation or b.

30 mils for first 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of 1 pump per loop operation.

1.3.7 Either seal cavity pressure exceeds 2500 psig.

1.3.8 Loss of total seal injection and Intermediated Closed Cooling Flow.

1.3.9 Seal staging flow plus seal leakage flow exceeds 1.91 g.p.m.

1.3.10 Loss of cooling water to the motors.

1.3.11 Motor stand vibration 5 3 mills.

2.0 IMMEDIATE ACTION 2.1 Automatic Action.

195 079 2.0

Y.

2202-1.4 Revision 6 l/

l 10/12/78 UR23 yy 2.1.1 Loss of one (1) RC Pump or one (1) pump per loop will result in a runback to 75% or 45% neutron power respectively.

If the ICS cannot respond quickly enough to avoid exceeding the RPS setpoints, a Reactor and Turbine trip will result.

2.1.2 Loss of two (2) RC Pumps in one loop or loss of more than two (2) pumps will result in a Reactor and Turbine trip initiated by the RPS.

2.1.3 Lift pumps and back-stop pumps Auto-start en loss of RC pump.

2.1.4 Emergency Feedwater Pumps Auto-Start and EFW flow occurs upon loss of four (4) RC Pumps.

Steam Generator leve! will increase to 50". on operating range.

2.1.5 If the Reactor does not trip and both feedwater Control Stations are in Auto and not on low level limits, the feed flow will be raticed according to' the number of pumps still operating.

2.2 Manual Action.

2.2.1 Verify that the unit has runback to the Power Level allowable for the RC Pump Combination.

NOTE.

If any ICS station in Hand, run station back in manual.

2.2.2 If a condition arises which necessitates manual tripping of a pump, reduce to appropriate power levels if possible prior to tripping pump, start the oil pumps and trip R.C. pump.

2.2.3 Verify Feedwater flows are rationed approximately 2.41 to I for loss of one RC pump.

195 080 3.0

25.

2202-1.4 Revision 8 gf-02/08/79 2.2.4 Verify Lift Pumps and Back-Stop Pumps have Auto-Started, A 2 0 upp if ncc, start the oil pumps.

2.2.5 If any of the following ICS stations are in Hand (Steam Generator /

Reactor Demand, either Feedwater Demand, Main or Startup Feedwater Valve Demand, Feedpump Speed, Reactor Master, and/or Diamond) runback the appropriate ICS stations corresponding to plant conditions.

3.0 FOLLOW-UP ACTION 3.1 Af ter pump reaches zero speed, shut?cwn lift pumps and Back-Stop pumps.

NOTE:

Coastdown may take as long as 30 minutes on last pump shutdown. Time is shorter as number of pumps still in operation increases.

3.2 If all for (4) RC Pumps are tripped, proceed as outlined in 2202-2.1 "Bl ackou t. "

3.3 Adjust the nuclear overpower trip setpoint for the allowable pump ccmbination per 2311-6.

e 4.0

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