ML20024C803
| ML20024C803 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 10/25/1978 |
| From: | GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| References | |
| TASK-*, TASK-GB 2202-1.1-02, 2202-1.1-2, GPU-0561, GPU-561, NUDOCS 8307130343 | |
| Download: ML20024C803 (5) | |
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THR'EE MILE ISLAND NUCLEAR STATION hd UNIT #2 e.MERGENCY PROCEDtlRE 2202-1.1 REACTOR TRIP Table of Effective Pages Psca Date Revision Pace Date Revision Paes Date -
Revision 1.0 10/06/78 5
26.0 51.0
' 2.0 06/12/78 4
27.0 52.0 3.0 10/25/78 6
28.0 53.0
. 4.0 29.0 54.0 5.0 30.0 ' ~
55.0 6.0 31.0
~ 56.0 7.0 32.0 8.0 33.0 57.0 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 48.0 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 Recommends Approval Unit 2 Staff Recommends Approval Approval Date Approval
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Date Cognl:snt Dept. Head Cognizant Dept. Head Unit 1 PORC Recommends Approval Unit 2 PORC Recommends Approval Qate S A Iv GMJM-Cate toy >S f
i Cheltman of PORC v' Chairm:n of PORC Unit 1 Superintendant Aporoval Unit 2 Super.intendent Appreval I
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THREE MILE ISLAND NUCLEAR STATION UNIT #2 EMERGENCY PROCEDURE 2202-1.1 REACTOR TRIP i
l 1.0 SYMPTOMS _
1.1 Reactor trip may be due to any of the following:
a.'
Nuclear power > 105.5% of rated power.
b.
Nuclear power > 1.05 times reactor coolant flow (%).minus power imbalance reduction.
Nuclear Power > 50.9% of rated pcwer during operation with l
c.
one R.C. Pump operating per loop.
d.
Loss of two Reactor Coolant Pumps in one reactor coolant loop.
Reactor coolant pressure > 2355 psig.
e.
f.
Reactor coolant pressure < 1900 psig.
-5887)
Reactor coolant pressure < (13.00 Tout g.
h.
Reactor coolant outlet temperature > 619"F.
i.
Reactor building pressure > 4 psig.
i j.
Manual reactor trip actuation.
1.2 Individual and group "In Limit" lights actuate.
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l 1.3 Rapid decrease in neutron level as indicated by the Nuclear Instrumentation.
j i
1.4 Main turbine master trip atann energized.
1.5 Rapid decrease in Unit Lead. -
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i 2.0' IMMEDIATE ACTION i
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06/12/78
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i, 2.1 Automatic Action a.
All rods insert (except Group 8)
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b.
Turbine trip, stop valves close c.
Generator breakers open t
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i d.
Turbine by-pass valves open 1
e.
Source range nuclear instrumentation high voltage energizes at 5 X.10 10 amps on N1-3 or N1-4.
2.2 Manual Action l
a.
Manually TRIP the reactor b.
Verify all "in-limit" lights are actuated (except group 8)
Verif[y that turbine has tripped and generator breakers c.
are open - if turbine has NOT tripped - manually TRIP the turbine, start lift pu=ps & turning gear oil pump.
d.
CLOSE letdown isolation valve MU-V376.
e.
START second make-up pump.
Open MU-V-163 as necessary to maintain 100" in PZR.
4 Verify turbine bypa's control valves are maintaining f.
s header pressure at 1010 psig.
g.
If any feedwater stations are in hand, run stations back to maintain OTSG at 30".
h.
Verify PZR Htrs are off @ 80" in PZR.
i.
If PIR level gets to 20" open CH-V5B and start 3rd make-up pump and open MU-V16C/D to increase PZR level.
j.
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.
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3.0 FOLLOV-UP ACTION 10/25, 3
3.1 Announce-on page system - Reactor Trip 3.2 Initiate emergency boration per 2203-1 1 (Loss of Beron) if reactor power is not below 10% in 1 minute
- 3. 3 Monitor make-up tank level and maintain level by using Waste Transfer Pumps (WOL-PSA/B) an greater than 55" 2
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eeding from an RCBT with boron concentration greater or equal t o RCS concen '
tration.
3.4 Verify that the pressurizei heaters and spray h g
RCS pressure to normal operating pressure of 2155 ave returned 3.5 psig.
Reduce pressuHzer level setpoint to 100" (25%)
3.6 Verify normal electrical lineup, i.e., no subst ti a on or in-plant distribution breakers are open (except ge 3.7 Check that all RMS channels are normal a a
no unplanned or uncontrolled radioactive release is in progress 3.8 Compute shutdown margin calculations per 2103 1 9 (Reactivity Balance Calculations).
boren should be added to the RCS.If shutdow 3.9 If reactor start-up is not intended within four h OT5G 1evel to 97-99% on the operating range usi ours raise i
ng the feedwater valve bypass and tube sheet drains for level control 3.10 Fill out a Reactor Trip report.
3.11 Notify H.P./ Chemistry. to sample R C
.. Letdown for Dose Equivalent 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 greatar th6n 15% within one hour period per Surveillance Proc d e ure !2304-302.
3.0
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