ML19209B658

Emergency Procedure 1202-4,Revision 12, Reactor Trip.

ML19209B658
Person / Time
Site:	Three Mile Island
Issue date:	09/24/1979
From:	METROPOLITAN EDISON CO.
To:
References
1202-4, NUDOCS 7910100282
Download: ML19209B658 (6)

Text

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1202-4

- - Revision 12 09/24/79 THREE MILE ISLAND NUCLEAR STATION CONT UNIT #1 EMERGENCY PROCEDURE #1202-4 REACTOR TRIP PolC C AlRV A\

Table of Effective Pages UN T 1 Paoe Date Revision Pace Date Revision Pace Date Revision 1.0 06/26/79 11 26.0 51.0 2.0 06/26/79 11 27.0 52.0 3.0 09/24/79 12 28.0 53.0 4.0 09/24/79 12 29.0 54.0 5.0 09/24/79 -12 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 ,

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Cognizant Dept. Head Cognizant D6pt. Head Unit 1 PORC Recommends Approval Unit 2 PORC R mmend pproval -

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1202-4 Pevision 11 06/26/79 THREE i; ISLAND NUCLEAR STATION UNIT #1 EMERGENCY PROCEDURE #1202-4 Reactor Trip 4.1 Symotoms -

1. Reactor trip alarm due to any of the following: (Actual trip set points are in parentheses),

a. Nuclear Power 1 105.5% of rated power (104.75%).

b. Nuclear Power 1 1 08 times flow (%) minus imbalance reduction 1.0725.

c. Nuclear Power 1 91% of rated power during operation with one pump operating per loop. (89.5%)

d. Loss of two reactor coolant pumps in one reactor coolant loop,

e. Loss of one or two reactor coolant pumps during two-pump operation.

f. Reactor coolant pressure 1 390 2 PSIG. (2384 PSIG)

g. Reactor coolant pressure 1 1800 PSIG. (1806 PSIG)

h. Reactor coolant pressure 1 (11.75 T out -5 W ) (11.75 T - 5097) out i.

Reactor coolant outlet temperature 1 6190F. 0 (618 F) j.

Reactor building pressure 1 4 PSIG. (3.15 PSIG)

k. Manual reactor trip actuation.

2. Individual and group "In Limit" lights actuate.

3. Rapid decrease in Neutron Level indicated by Nuclear Instrumentation.

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4. Main turbine master trip energized alarm.

5. Rapid decrease in Unit Load.

4.2 Immediate Action

1. Automatic Action

a. All rods insert (Except Group 8). '

b. Turbine trip, stop valves close, generator breakers open.

c. Source range high voltage energizes 0 5 X 10-10 amp on NI-3 or 4.

d. Turbine by-pass valves open.

NOTE: The Atmospheric Relief Valves will open if steam generator pressure reaches 1027 PSI.

2. Manual Action

a. Manually trip the reactor and verify that all rods are inserted except Group 8.

b. Trip the turbine, verify that the generator breakers are open and start lift pumps and turning gear oil pump.

c. Close the letdown isolation valve tiU-V3.

d. Monitor pressurizer level and maintain level greater than or equal to 100". Start second make-up pump (MU-PlA or IB) and open MU-V16B. Shift pump suction to the BWST.

e. If pressurizer level drops below 80", verify pressurizer heaters are off. If not off, place heater control switches to 0FF on console CT:.

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, 1202-4 Revision 12 09/24/79

f. If pressurizer level drops below 20", open MU-V14B, start MU-Plc and open either MU-V16C or 160.

g. Verify that turbine bypass control valves are maintaining header pressure at 1010 PSIG.

CAUTION: Low main steam pressure may indicate the secondary safety valves have not closed.

h. If any feedwater station (s) are in hand, run station (s) back to maintain OTSG level at 30".

1. If high pressure injection has initiated due to low reactor coolant system pressure, an immediate trip of all reactor coolant pumps is required. Refer to EP 1202-6,

" Loss of Reactor Coolant / Reactor Coolant Pressure."

4.3 Follow-Vo Action The objective of this procedure is to conserve RCS inventory to offset shrink, ensure the core is 1% shutdown, remove decay heat thru the steam generators and arrive at a stable hot shutdown condition.

1. Announce on page sy' stem reactor trip.

2. If reactor power was not below 10% after 1 minute ensure emergency boration from BWST is in progress.

3. Verify that the initial pressure decrease is stopped and '

pressure begins an increasing trend. Using the console indicator, verify that the RCS is within the limits of Figure

1. Obtain at least a 50 0F margin from saturation.

4. Energize pressurizer heaters when two out of three pressurizer level instruments as read on RC-1-LR indicate pressurizer level greater than 80".  ;

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1202-4 Revision 12 09/24/79

5. Verify that the pressurizer heaters and spray have returned RCS pressure to normal operating pressure of 2155 PSIG.

6. Reduce pressurizer level setpoint to 100" (25%).

7. Verify no substation breakers open, except cenerator breakers.

8. Verify no unplanned or uncontrolled radioactive release in progress.

Check that all RMS channels are normal.

9. Run reactivity balance to determine shutdown margin using OP 1103-15 Reactivity Balance Calculation. If SDM is less than 1% boron should be added to RCS.

10. . Notify Shift Foreman / Shift Supervisor to fill out and submit &

reactor trip report.

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