ML19224B122
| ML19224B122 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 10/25/1978 |
| From: | Metropolitan Edison Co |
| To: | Mullinix W NRC/IE |
| References | |
| 2203-1.8, TM-0040, TM-40, NUDOCS 7906140071 | |
| Download: ML19224B122 (7) | |
Text
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TMI DOCUMENTS
~ hh DOCUMENT NO:
COPY MADE ON 3
0F DOCUMENT PROVIDED BY I
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METROPOLITAN EDISON COMPANY.
Wilda R. Mullinix, NRC f
7906140071 188 122 6
2203-1.8 A ^ ~./'
P A N. j r m 1 ~ 7.RU';It Revision 2 -.
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UUI 10/25/78 in c CEr,1 n t :F.nt Ii f' pa 2 mg 1
f THREE MILE ISLAND NUCLEAR STATION UNIT #2 ABMORMAL FROCEDURE 2203-1.8 VIBRATION AND LOOSE PARTS MONITORIt:G SYSTEM Table of Effective Pages Pace Date Revision Pace Date Revision Pace Date Revision 51.0 1.0 05/03/77 0
26.0 52.0 10/25/78 2
27.0 53.0 2.0 3.0 10/25/78 2
28.0 54.0 4.0 10/25/78 2
29.0 55.0 5.0 10/25/78 2
30.0 56.0 6.0 10/25/78 2
31.0 57.0 32.0 58.0 7.0 33.0 50.0 8.0 34.0 60.0 9.0 35.0 61.0 10.0 36.0 62.0 11.0 37.0 63.0 12.0 38.0 64.0 13.0 39.0 65.0 14.0 40.0 66.0 15.0 41.0 67.0 16.0 42.0 68.0 17.0 43.0 69.0 18.0 44.0 70.0 19.0 45.0 71.0 20.0 46.0 72.0 21.0 47.0 73.0 22.0 48.0 74.0 23.0 49.0 24.0 75.0 50.0 25.0 Unit 2 Staff Recommends Approval Unit 1 Staff Recommends Approval
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8 Date Approva!
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_ Date Cogniz:nt Dcpt. Head Approval Ccgnizant Ocpt. Head Unit 2 PORC Rc:ommer.ds Approval Unit 1 PORC Recommends Approval 0?b L ' '"
Date 'O' 5' I
Date V'- Ch:irraan of F0RC Chairnur.of F0RC 5
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2203-1.8
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Revision 0
,y 05/03/77
.,2 3 iM-THREE MILE ISLAND NUCLEAR STATION
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UNIT #2 - ABNORMAL PROCEDURE 2203-1.8 Vibration and Loose Parts Monitor System 8
1.0 SYMPTONtS a)
Alam lights in monitor cabinet on 305' elev. of Control Bldg.
(Cable Room) Vibration or loose Parts Indicator energized for one or more channels.
(Channels 1 thru 12)
Nuclear Noise Indicator energized for one or both channels.
(Channels 13 thru 14) b)
Abnormal noises heard over local (in cabinet) or remote (Panel 8, Control Room) speakers.
c)
Sudden increase in amplitude (a change which exceeds two times the background trace) noted on the chart recorders for one or more channels.
(Channels 1 thru 12)
Determine increase in amplitude in accordance with Appendix I of 2105-1.13.
2.0 IMMEDIATE ACTION A.
Automatic Action - None B.
Manual Action i)
Report alarm and affected channels to Shift Foreman /
Supervisor.
2)
Attempt to reset the alarm lights by pressing the reset pusiibutton at the loose parts monitor panel.
g
-f 3.0 FOLLOW UP ACTION 1
j 188 124 1.0 4
e
2203-1.8 3'
4 Revision 2 l'
10/25/78 APR 2 3 spg 2105-1.13.
Record the alarming channel or channels in accordance with 1.
Determine type and degree of noise.
2.
If the noise is loud on more than one channel (ie heard receatedly a.
1.
TRIP THE REACTOR Using the cassette recorder obtain one minute of data for 2.
each sample using the order below:
Recorder Channel Selection 1
2 3
4 Samole 1
3 5
9 1
2 4
6 10 2
7 11 8
12 3
13 14 5
6 4
Record tape footage from recorder meter for each NOTE:
sample, date and time.
If noise continues selectively TRIP Reactor Coolant Pumps 3.
(ie. RCP until noise stops and record Unit status.
Trip combination running and/cr other abnormal conditions).
remaining Pumps.
Ccolant Pumos were selectively NOTE:
If Reactor tripped immediately notify the Unit Superintendent.
Limit time of reduced pump operation in accordance with B & W recommendations.
"?-1.1 and 2102-3.3.
4.
Cooldown per If the noi.se is intermittent or periodic on more than one 5
b.
channel Determine location based on loudest channel.
1.
188 125 l
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2.0
b 2203-1.8 i
Revision 2h 10/25/78 APR 2 3 1979 2.
Using the cassette recorder obtain one minute of data for each sample using the order below:
Recorder Channel Selection Samole 1
2 3
4 1
1 3
5 9
2 2
4 6
10 3
7 11 8
12 4
13 14 5
6 NOTE:
Record tape footage from recorder meter for each sample, date and time.
3.
Check the follcwing Unit parameters for abnormalities:
1.
R. C. Fl ow 2.
R.C. Pressure 3.
R.C. Pump Seal Flow 4.
R. C. Pump Vibration 5.
R. C. Pump and Motor Bearing Temperatures 6.
Power Range Power level 7.
CRDM Drive Temperatures 8.
MU-R-720 Readings 9.
Letdown Filter iP 10.
Letdown Sample (Upstream of Filter) 11.
Secondary Sample 12.
Feedwater Control Valves dP's 13.
VA-R-748 Readings j
NOTE:
Some power levels have much more background noise
-f than others.
(There is considerably more background noise at 15% power. )
188 126 3.0
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APR 2 3 873 3-1.8 Revision 2 10/25/78 If significant abnormalities exist in condition 3.1.-3.13 record condition and TRIP the Reactor.
If the noise appears to be in one of the Steam Generators 4.
reduce Reactor Power and selectively TRIP on appropriate Reactor Coolant Pump. (ie. If noise is loudest or A(B) Steam Generator start by tripping RC-9-1A(RC-P-1B).
If Reactor Coolant Pumas were selectively NOTE:
tripped immediately notify the Unit Limit time of reduced Superintendent.
pump operation in accordance with B & W 1
recommendations.
If noise persists reduce Reactor Pcwer and trip a Reactor 5.
Coolant Pump in the other icop (if two operating).
If noise continous TRIP the REACTOR and remaining Reactor 6.
Coolant Pumps until noise stops.
2202-1.1 and 2102-3.3.
7.
Cooldown per If noise is either a soft thumping, grinding or pocoing c.
on more than one channel, or a loud noise on only one l
channel.
Determine location based on noise observed.
I 1.
Using the cassette recorder obtain one minute of data 2.
for each sample using the order below:
Recorder Channel Selection 1
2-3 a
f Samole 1
3 5
9 1
2 4
6 10 2
i 7
11 8
12 3
13 14 5
6 4
188 127 4.0
Y APR 2 s 9g79 2203-1.8 Revision 2 10/25/78 NOTE:
Record tape footage from recorder meter for each sample, date and time.
Check the following Unit parameters for abnormalities:
3.
1.
R.C. Flow 2.
R.C. Pressure 3.
R.C. Pump Seal Flow 4.
R.C. Pumo Vibration 5.
P.C. Pump and Meter Reading Temoeratures 6.
Power Range Power Level 7.
CRDM Drive Temperature 8.
MU-R-720 Readings 9.
Letdown Filter dP 10.
Letdown Sample (upstream of fil+.er) 11.
Secondary Sample 12.
Feedwater Control Valves dP's 13.
VA-R-748 Reading NOTE:
Some power levels have much more be.ckground noise than others.
(There is considerably more background noise at 15% power.)
Additional checks to be made, if deemed necessary by the Shift Foreman / Shift Supervisor.
1.
3D Core Power Maps 2.
Primary and Secondary Samples Entry into the Reactor Building to confirm abnormal 4
3.
sounds by local observation.
-j If abnormalities exist record condition and Shif t Supervisor /
4.
foreman will evaluate whethe-to continue aceration or TRIP 188 128 5.0
1
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{}1:' (li 2 3 2203-1.8
. Revision 2 10/25/78 Reactor.
If all conditions are normal the Supervisor of Operations, Unit Superintendent-Technical Support and Unit / Station Supertendent will evaluate continued operation.
3.
Strip Charts (LPV Monitor) should be checked for time of occurrence, so that alarm may be correlated with a possible large electrical impulse or maintenance personnel action which may oroduce scurious alarm.
4.
Should all observations and plant parameters indicate normal oceration, but LPV monitor system still inoicates abnormal conditions, the system will be thoroughly checked for equipment failure.
If the LPV Monitor System is found to be operating properly, further action will be I
based on Shift Supervisor, Supervisor of Ocerations, Station / Unit Superintendent and Technical Service Personnel decisions.
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188 129
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