ML19209B658: Difference between revisions
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Date VI2Y?9 Date | Date VI2Y?9 Date VChairman of PORC Chairrnin of PORC A | ||
VChairman of PORC Chairrnin of PORC A | |||
Unit 1 Superjtntende Ap;< oval Unit 2 Superintendent A pr val | Unit 1 Superjtntende Ap;< oval Unit 2 Superintendent A pr val | ||
'b | 'b | ||
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Tut SS.A Row 8/77 7 910100 hh j j 3," '?Q P | Tut SS.A Row 8/77 7 910100 hh j j 3," '?Q P | ||
1202-4 Pevision 11 06/26/79 THREE i; ISLAND NUCLEAR STATION UNIT #1 EMERGENCY PROCEDURE #1202-4 Reactor Trip 4.1 Symotoms - | 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), | : 1. Reactor trip alarm due to any of the following: (Actual trip set points are in parentheses), | ||
Line 50: | Line 47: | ||
: 3. Rapid decrease in Neutron Level indicated by Nuclear Instrumentation. | : 3. Rapid decrease in Neutron Level indicated by Nuclear Instrumentation. | ||
1.0 7? TO J4 / | 1.0 7? TO J4 / | ||
* ' 1202-4 Revision 11 06/26/79 | * ' 1202-4 Revision 11 06/26/79 | ||
Line 69: | Line 65: | ||
: e. If pressurizer level drops below 80", verify pressurizer heaters are off. If not off, place heater control switches to 0FF on console CT:. | : e. If pressurizer level drops below 80", verify pressurizer heaters are off. If not off, place heater control switches to 0FF on console CT:. | ||
2.0 1134 'O | 2.0 1134 'O | ||
, 1202-4 Revision 12 09/24/79 | , 1202-4 Revision 12 09/24/79 | ||
Line 91: | Line 82: | ||
e i | e i | ||
3.0 i | 3.0 i | ||
$bN 'kl | $bN 'kl m | ||
m | |||
1202-4 Revision 12 09/24/79 | 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. | : 5. Verify that the pressurizer heaters and spray have returned RCS pressure to normal operating pressure of 2155 PSIG. | ||
Line 105: | Line 93: | ||
: 10. . Notify Shift Foreman / Shift Supervisor to fill out and submit & | : 10. . Notify Shift Foreman / Shift Supervisor to fill out and submit & | ||
reactor trip report. | reactor trip report. | ||
s 4.0 | |||
s | |||
4.0 | |||
Figure ! ' | Figure ! ' | ||
Revision 12 | Revision 12 | ||
, 09/24/70. | , 09/24/70. | ||
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Latest revision as of 06:26, 2 February 2020
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
.
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 ,
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 s 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 Staff Recom pproval Unit 2 Staff Recorame pproval Approval Date Approval / Date -
Cognizant Dept. Head Cognizant D6pt. Head Unit 1 PORC Recommends Approval Unit 2 PORC R mmend pproval -
!A k
^
Date VI2Y?9 Date VChairman of PORC Chairrnin of PORC A
Unit 1 Superjtntende Ap;< oval Unit 2 Superintendent A pr val
'b
. Date ,# Date V l */ b Manager Generation Quality Assurance Approval bh Date "
Tut SS.A Row 8/77 7 910100 hh j j 3," '?Q P
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.
1.0 7? TO J4 /
- ' 1202-4 Revision 11 06/26/79
- 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:.
2.0 1134 'O
, 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.
CAUTION: Low main steam pressure may indicate the secondary safety valves have not closed.
- 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". ;
e i
3.0 i
$bN 'kl m
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.
s 4.0
Figure ! '
Revision 12
, 09/24/70.
TRESSURE /Th~M PER frTUR.C
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