ML20024B593
| ML20024B593 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 10/25/1978 |
| From: | GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| References | |
| TASK-02, TASK-2, TASK-GB 2202-1.1-01, 2202-1.1-1, B&W-0746, B&W-746, NUDOCS 8307090368 | |
| Download: ML20024B593 (4) | |
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THREE MILE ISLAND NUCLEAR STATION b
UNIT #2 EMERGENCY PROCEDURE 2202-1.1 REACTOR TRIP t
Table of Effective Pages M
Date Revision _
- Pact, Date_
Revision Pac Date Revi:fon 26.0 51 D/
1.0 10/06/78 5
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28.0 53.0 3.0 10/25/78 6
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l-Unit 1 Staff Recommends Approval Unit 2 Staff Re:ommends Approwl
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TEREE MILE ISLAND NUCLEAR STATION UNIT #2 EMERGENCY PROCEDURE 2202-1.1 REACTOR TRIP.
r 1.0 SYMPTOMS Reactor trip may be due to any of the following:
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1.1 Nuclear power > 105.5% of rated power.
a.
Nuclear power > 1.05 times reactor coolant flow (%) $1nus i
i b.
power imbalance reduction.
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Nuclear Power > 50.9% of rated pawer during operation with c.
one R.C. Pump operating per loop.
Loss of two Reactor Coolant Pumps in one reactor coolant d.
I loop.
l Reactor coolant pressure > 2355 psig.
e.
Reactor coolant pressure < 1900 psig.
f.
Reactor coolant pressure < (13.00 Tout-5887) g.
0 Reactor coolant outlet temperature > 619 F.
h.
Reactor building pressure > 4 psig.
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Manual reactor trip actuation.
Individual and group "In Limit" lights actuate.
1.2 Rapid decrease in neutron level as indicated by the Nuclear 1.3 Instrumentation.
Main turbine master trip alarm energized.
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1.4 1.5 Rapid decrease in Unit Load.
4 IMMEDIATE ACTION 2.0 __
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a.
All rods insert (except Group 8) b.
Turbine trip, stop valves close i
c.
Generator breakers open i
d.
Turbine by-pass valves open j
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e.
Source range nuclear instrumentation high voltage energizps at 5 X 10-10 amps on N1-3 or N1-4.
l 2.2 Manual Action
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i a.
Manually TRIP _ the reactor b.
Verify all "in-limit" lights are actuated (except group 8) j c.
Verify that turbitte has tripped and generator breakers i
are open - if turbine has NOT tripped - manually TRIP the turbine, start lift pumps & turning gear oil pump.
d.
CLOSE letdown iso'.ation valve MU-V376.
e.
START second make up pump.
Open MU-V-163 as necessary to maintain 100" n PZR.
f.
Verify turbine bypass control valves are maintaining header pressure st 1010 psig.
g.
If any feedwater stations are in hand, run stations back 3
u to maintain OTSG at 30".
h.
Verify PZR Htrs are off 0 80" in PZR.
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If PZR level gets to 20" open DH-V5B and start 3rd make-uo 9
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pump and open MU-V16C/D to increase PZR level.
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If any of the following ICS stations are in Hand (Steam a-Generator / Reactor Demand, either Feedwater Demand, Main or Startup Feedwater Valve Demand, Feedpump Speed, Reacter 3
I Master, and/or Diamond) runback the appropriate ICS stations.
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3.0 FOLLOW-UP ACTION i
3.1 Announce-on page system - Reactor Trip
! J 3.2 Initiate emergency boration per 2203-1.1 (Loss of Boron)
I, if reactor power is not below--lay _ in 1 minute.
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3.3 Monitor make-up tank level and maintain level reater than 55" by using Waste Transfer Pumps (WDL-P5A/B) and. feeding [ ro t
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RCBT with boron concentration greater or eg'ual to RCS.'concen tration.
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3.4 Verify that the pressurizer heaters and spray have returned
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RCS pressure to normal. operating pressure of 2155 psig.
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3.5 Reducepressurizerlevelsetpointto100"(25%).
l 3.6 Verify normal electric ~al lineup, i.e., no substation or in-(
plant distribution breakers are open (except generator brea 3.7 Check that all RMS channels are normal and that no unplanned or uncontrojled radioactive release is in progress.
3.8 Compute shutdown margin calculations per2103-1.9 (Reactivity Balance Calculations).
If shutdown margin is less than 1%,
boron should be added to the RCS.
3.9 If reactor start-up is not intended within four hours raise OTSG 1evel to 97-99'; on the operating range using the feedwate valve bypass and tube sheet drains for level control.
3.10 Fill out a Reactor Trip report.
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3.11 Notify H.P./ Chemistry to sample R.C. Letdovm for Dose Equ Iodine between 2 and 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after power change of greater than 15% within one hour period per Surveillance Procedure #2304-3 2
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