ML19224B287
| ML19224B287 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 10/13/1978 |
| From: | Metropolitan Edison Co |
| To: | Mullinix W NRC/IE |
| References | |
| 2202-2.2, TM-0409, TM-409, NUDOCS 7906140390 | |
| Download: ML19224B287 (5) | |
Text
w TMI DOCUMENTS DOCUMENT NO:
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COPY MADE ON OF DOCUMENT PROVII3 BY METROPOLITAN EDISON COMPANY.
Wilda R. Mullinix, NRC 7 9 0 614 0 39c i
197 042
CONIMUtLt.U LUn 2202-2.2 CEDA_
n _E B;ung 3 l
THREE MILE ISLAND NUCLEAR STATION UNIT #2 EMERGEllCY PROCEDURE 2202-2.2 LOSS OF STEAM GEt1ERATOR FEED Table of Effective Pages Page Date Revision Pace Date Revisio n _
Pace Date R evision 1.0 10/13/78 3
26.0 51.0 2.0 10/13/78 3
27.0 52.0 3.0 10/13/78 3
28.0 53.0 4.0 10/13/78 3
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 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
.34 18.0 43.0 68.0
'1 19.0 44.0 69.0 20.0 45.0 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 Recommends Approval Unit 2 Staff Recommends Approval Date Approval Date Approval
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Cognizaat Dept. Head Cognizant Dept. Head Unit 1 PORC Recommends Approval Unit 2 PORC Reco mends Approval I
Date
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d'k Date /b /T
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Chairman of PORC Chairrnan of PORC b.
Unit 1 Superintendent Approval Unit 2 Superintendent pproval Date
.6&N Date /d V
n
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Manager Generat on Quality Assurance Approval
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Date i
19 7 0 43"-^ "-"'"
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2202-2.2 Revision 3 10/13/78 THREE MILE ISLAND NUCLEAR STATION UNIT #2 EMERGENCY PROCEDURE 2202-2.2A TOSS OF MAIN FEEDWATER FLOW TO BOTH OTSG'S 1.0 SYMPTOMS 1.
Both OTSG levels decreasing.
2.
Feedwater flow to both OTSGs decreasing.
3.
Feed pump turbine speed decreasing or both main feed valves closing.
4.
Both feed pump turbine trip alarms.
5.
Increasing rea.ctor coolant pressure and temperature.
6.
Reactor - turbine runback 7.
Turbine trip if both feed pumps trip.
2.0 IMMEDIATE ACTION
~"
A.
AUTOMATIC ACTIONS' 1.
If loss of FW is due to loss of both feed pumps:
a.
Reactor / Turbine trip due to high RC pressure.
b.
Emergency feed pumps EF-P-1, EF-P-2A, and EF-P-2B start and maintain OTSG level at 30" (S/U range indi cation).
2.
If loss of FW is due to valves closing, ICS trips to track due to FW X-Limits.
B.
MANUAL ACTIONS 1.
If loss of FW is due to loss of both feed pumps:
a.
Trip the Reactor 4
b.
Verify Turbine trip and stop valves closed.
5 c.
Verify EF-P-1, EF-P-2A, and EF-P-28 start as evidenced by pump discharge pressures.
}a ur, 1.0
44U4-4.4 Revision 3 10/13/78 d.
Verify emergency feed water valves (EF-il A (B)) are in automatic and controlling OTSG level at 30 inches (S/U range indication).
2.
Loss of feed water due to valves closing:
a.
Verify or open main and startup feedwater block valves (FW-V-17A (B) FW-V-14A (B), FW-V-19A (B), FN-V-26A (B)).
b.
Verify the MWe and reactor power are decreasing.
c.
Attempt to open main feed reg. valves.
d.
If reactor coolant temperature and pressure cannot be maintained, or if feedwater flow cannot be restored, or if the reactor trips, start the emergency feed pumps and maintain 30 inches in the steam generators
- 31
~ (S/U range indication).
3.0 Follow-Up Action 1.
Repair system as required and restore normal feed to OTSG.
2.
If plant cooldown is required on loss of both main feedwater pumps, conduct cooldown using emergency feed system.
Refer to 2102-3.3, Decay Heat Removal Via STSG.
3.
With flow through the emergency feedwater nozzles, there is a possibility of water accumulation in the OTSG steam annulus space, and the steam lines.
Insure these areas are drained prior to startup.
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i 197 045 2.0
2202-2.2 2
ib71f/fif i
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3 THREE MILE ISLAND NUCLEAR STATION UNIT #2 EMERGENCY PROT.EDURE 2202-2.2B LOSS OF MAIN FEEDWATER FLOW TO ONE OTSG 1.0 SYMPTOMS 1.
Steam generator level decreasing on one OTSG.
2.
Feedwater flow to ona OTSG decreasing.
3.
One main feedwater valve closing.
4.
Increasing reactor coolant pressure and temperature.
5.
Increasing temperature differential across reactor coolant cold legs.
6.
Reactor - turbine runback.
2.0 IMMEDIATE ACTION A.
Automatic Action 1.
ICS-goes into track due to feedwater cross limits (FW
'1 error > + 5%).
2.
ICS in tracking mode reduces generated ff.le and reactor power to match available feedwater flow.
B.
Manual Action 1.
Vecify that the ICS is in the tracking mode as indicated by both hand and auto lights lit on the unit load demand H/A station.
2.
Verify the MWe and reactor power are decreasing.
3.
If OTSG level on the affected 0TSG is greater than 30 inches, go to manual on H/A station and increase the demand
- to the associated main and startup R4 regulating 5
valve and attempt to regain feedwater flow.
197 046 3.0
m 2202-2.2 C
Revision 3 10/13/78 1
4.
Verify that the associated feedwater block valves are open, (FW-V-14A(B), FW-V-17A(B), FW-V-19A(B) and Ri-V-26A(B).
5.
If any ICS stations are in hand, runback the appropriate ICS stations.
3.0 FOLLOW-UP ACTION 1.
If able to restore FW flow prior to Reaching OTSG leveT of 15 inches, continue normal operation.
2.
If unable to restore normal FW flow prior to reaching 015G level of 15 inches, concurrently raduce reactor power to Tess than 8". full power and restore feedwater flow to the affected 0TSG using emergency feedwater pump and EF-VilA(B).
NOTE:
In the event that an OTSG boils dry, establish feed
' flow using emergency feedwater pump through the emergency feed valves EF-V-11 A(B) very slcwly (2 inches per minute).
3.
Raise the OTSG level to 25 inches using the emergency feedwater pump and EF-V-llA(B).
Restore normal feedwater flow through FW-V-30A(B) amd/or FW-V-25A(B) and shutdown the emergency feedwater system.
(stop emergency feedwater pump and close EF-V-llA(B)).
4.
With flow through the emergency feedwater nozzles, there is a possibility of water accumulation in the OTSG steam annulus space, and the steam lines.
Insure these areas are blown down i
before continued operation.
J 197 047 4.0 i