ML19224B299
| ML19224B299 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 10/25/1978 |
| From: | Metropolitan Edison Co |
| To: | Mullinix W NRC/IE |
| References | |
| 2202-1.1-01, 2202-1.1-1, TM-0406, TM-406, NUDOCS 7906140427 | |
| Download: ML19224B299 (4) | |
Text
.
.t JMI DOCUMENTS lil" OYOh DOCtmE:rt NO:
COPY M>.DE ON OF DOCL"ENT PROVIDr:D BY lEIROPOLITAN EDISCN COMIWrl.
glMy/
Wilda R. Mullinix,
?!RC 7906140421 D
i
CONTROLLO ':";d 2202 u Revision 6
((,} }_{ [,t l' t L.C.
10/25/78 g1y THREE MILE ISLAND NUCLEAR STATION UNIT #2 EPIRGENCY PPOCEDURE 2202-1.1 REACTCR TRIP Table of Effective Pages M
Date Revision
,PR D ate _
Rcvicion M
Date R evi:fon 1.0 10/C6/78 5
26.0 5 '.0 2.0 06/12/78 4
27.0 52.0 3.0 10/25/78 6
26.0 53.0 4.0 29.0 54.0 5.0 30.0 55.0 6.0 31.0 56.0 7.0 32.0 57.0 8.0 33.0 58.0 9.0 34.0 59.0 10.0 35.0 60.0 11.0 26.0 61.0 12.0 37.0 62.0 13.0 30.0 63.0 14.0 39.0 G4.0 16.0 40.0 65.0 1 G.0 41.0 66.0 17.0 42.0 67.0 16.0 43.0 68.0 19.0 44.0 60.0 20.0 4 S.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 Staff Recomrcanes Approval Unit 2 Staff Rtcomrnends Approval
/
Q' N
__ D ate Appioval Date,__~
Approval l
Cc;ni::nt Ogt. Hesd Cc;n!:ent Dt Head Unit 1 PORC Rccommcnds Approval Unit 2 PORC Rrsemrnends Approvel N
~
9/ / 7:Wif D r.t c _
M /,
9 D to, Chtirrn.n of FORC t/- Chirmen of FORC
~
U;,it 1 Ceperint;nd:nt Approval Unit 2 Superintend:nt Apprcycl
/
"\\'l
'" /
Dat / '- - -
i
// f Dete
(/
()
/
/
//
m.;er Gcneratien Cur.lity Azurcnc Apprcva' N Y __
~ ~ ~ ~
Dcte n :.: A no n7
2202-1.1 f8/$d)fj5 THREE MILE ISLA!;D i;UCLEAR STATI0t1 Utili 52 E"ERGEtiCY PROCEDURE 2202-1.1 REACTOR TRIP 1.0 SYMPTO.$
1.1 Reactor trip may be due ti any of the folicwing:
t?uclear po.zer > 105.5% of rated power.
a.
I!uclear po ver > 1.05 times reactor cooiant flow () minus b.
power imbalance reduction.
!;uclear Power > 50.9% of rated power during operation with c.
one R.C. Pump operating per icop.
Loss of two Reactor Coolant Purps in one reactor coolant d.
loop.
Reactor coolant pressure > 2355 psig.
e.
l f.
Reactor coolant pressure < 1900 psig.
Reactor coolant pressure < (13.00 Tout' 887) g.
U h.
Reactor coolant outlet temperature > 619 F.
i.
Reactor building pressure > 4 psig.
j.
Panual reactor trip actuation.
1.2 Individual and group "In Limit" lights actuate.
Rapid decrease in neutron level as indicated by the "uclear 1.3 Instrumentation.
1.4 "ain turbine. aster trip alara energized.
1.5 Rapid decrease in Unit Lead.
2.0 IM :EDI ATE ACTIO.'1 1.0 l-E
2202-1.1
'4 Revision 4 1
06/12/78 2.1 Automatic Action a.
All rods insert (except Group 8) b.
Turbine trip, stop valves close
[.
c.
Generator breakers open d.
Turbine by-pass valves open e.
Source range nuclear instrumentation high voltage energizes
~10 at 5 X 10 amps on N1-3 or N1-4.
')'
AN 2.2 Manual Action
<e w
a.
Manually TRIP the reactor elf
'il Ij b.
Verify all "in-limit" lights are actuated (except group ff
.w 8)
'3G Ot c.
Verify that turbine has tripped and generator breakers 9I F.
are open - if turbine has NOT tripped - manually TRIP the
^: _
turbine, start lif t pumps & turning gear oil pump.
Di d.
CLOSE letdown isolation valve MU-V376.
5 e.
START seccnd make up pump.
Open MU-V-163 as necessary to maintain 100" in PZR.
f.
Verify turbir.e bypass control valves are maintaining header pressure at 1010 psig.
_ ~.
g.
If any feedwater stations are in hand, run stations back to maintain OTSG at 30".
hi h.
erify PZR Htrs are off 9 30" in PZR.
f4 i.
If PZR level gets to 20" cpen DH-V5B and start 3rd make-up I
}:
pump and open MU-V16C/D to increase PZR level.
j.
If any of the following ICS stations are in Hand (Steam
,e Generator / Reactor Demand, either Feedwater Demand, Main or Startup Feed'.zater Valve Denand, Feedpump Speed, Peactor Master, and/or Diamond) runback the appropriate ICS stations.
\\6
zzuz-1.1 v
3 Revision 6
~,,
10/25/78 3.0 FOLLCU-UP ACTION 3.1 Announce-on page system - Reactor Trip 3.2 Initiate emergency boration per 2203-1.1 (Loss of Boron) if reactor power is not below 10% in 1 minute.
3.3 Monitor make-up tank icvel and maintain level greater than 55" by using Waste Transfer Pumps (WDL-PSA/B) and feeding from an RCBT with boron conc r.tration greater or equal to RCS concen-t ra ti on.
3.4 Verify that the pressurizer heaters and spray have returned RCS pressure to normal operating pressure of 2155 psig.
3.5 Reduce pressurizer level setpoint to 100" (25%).
3.6 Verify normal electrical lineup, i.e., no substation or in-plant distribution breakers are open
.. cept generator breakers).
3.7 Check that all RMS channels are normal and that no unplanned or uncontrolled radicactive release is in progress.
3.8 Compute shutdown margin calculations per 2103-1.9 (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 level to 97-99% on the operating range using the feedwater valve bypass and tube sheet drains for level control.
3.10 Fill out a Reactor Trip report.
w 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 greater than e
s 15% within one hour period per Surveillance Procedure #2304-302?
fb 3.0 I