ML19224A267
| ML19224A267 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 11/15/1978 |
| From: | Lengel R Metropolitan Edison Co |
| To: | NRC Office of Inspection & Enforcement (IE Region I) |
| Shared Package | |
| ML19224A266 | List: |
| References | |
| NUDOCS 7811210384 | |
| Download: ML19224A267 (5) | |
Text
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A'<'.AF1? " A "'.v. f.*.. *. "..a._,m
',7_'.
Oceket No.
- C 12?
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n u..
._ e Date l'-15 7Q Cc=pleted By P.
A.
re-n1
- *EhCU'
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- 0 D'
- 10 C C'"^- * ~~l
.t%.,,,,tr 3/Y A7EFAGE DAILY PC'JER E!IL DAY AVE? AGE DAILY PC'4ER Cr:.*
{M'Je-Net )
(M'Je-N et )
2co c9,,
.4 2
299
,a hc-7
- v-h96 k
301 20 LS9
_ 'i_ _ ' -
21 292 l
5 6
-10 22 615 7
23 676
-8 8
-10 2h 67S 5
698
-lk o
-30 26 665 10
-15 2~.
7C6'
-33
-a
- c-
-o
,e e.
- 2 29
-36 13 ik 30
-38 h2 72h
-o 15 31
-;v 2, k 4
ev vs112103 74 S
3-vas
'Se negative turbers indicate that =capcVer was sed by
'-a produced ':7 it.
he se nu=bers are inc1;ded f:r 7-"
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k
CPERA*'I'IG DATA RI?CET Occhet No.00-320 707*20*#
2' E3 Date Cc= leted 37
?.
A.
_enral c e. r_.a. m...,v-e. m~. a
... c ~..,.. o,c_ce_c_
_c.n.,_
a...
1.
Unit Na=e:
~hree Mile !aland, '? nit 2 2.
Repcrting Peried:
Cc:c'cer 3
Licensed ~her=al Pcver (.T4t):
AI"5 70-k.
Nameplate Rating (Gress Mie):
5.
Design Ilectrical Rating (Net Tie):
9c6 6.
Max Cependable Capacity (Grcss M'4e): 930 7.
Max. Dependable Capacit/ (Net Kie):
0 22 3.
If Changes Cecur in Capaci*y Ratings (Items No. 3 thrcugh Since 'ast Repert, Give Reasces:
9
?cver Level to which Restricted. If Any (Net M'Je):
10.
Reascus for Restrictices, If Any:
Sis Month Yr.-to-Date Ct=ulative I". -
--n5
.,,0
?
?'"
0'4 11.
Ecurs in Reporting Period
,,s.
"*e**
12.
No. of Ecurs Reacter vas Critical SC8.1 1C86.8 13 Reacter Reserve Shutdevn Ecurs 23e.o c3ve.y
,e,ca.4 lk.
Ecurs Generater Cn-Line hhS.5 679.6 679.6 0"
15 Unit Reserve Shutdevn Ecurs
^n n
16.
Gross "'her=al Energy Generated Ogg) 665280 363356 365856 17.
Grcss Ileet. Energ.t Generated (M'4H) 21co.0
.- c, 5 2c2014 a
13.
Net Electrical Energy Generated (T4E) c o ~-h
,cac-n 156570 19 Unit Service Facter NA NA NA J^
NA NA 20.
Unit Availability Facter 21.
Unit Capacity Facter (Using !CC Net)
'7A
'7A "A
22.
Unit Capacity Fanter (Using DER Net)
NA NA NA
- IA NA 23 Uni Fcreed Cutage F. ate jtA 2h.
Shutdcuns Scheduled Over Next 6 Menths (?ype, Cate, and Ouratien of Zach):
25 If Shut Oest at End of Repcrt Pericd, Isti=ated Cate of Startup:
- 26. Units In Test Status (Prior to Cc==ercial Cperatien):
FCRICAST ACHIIVD III-'IAL CRIT!CALI~Y 3-9-73 3-23-73
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, _e -a 2-.,_
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CCMME?C'_AL CPIRA* ION M. d< r p' o
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Docket No.
IINIT SillffDOWNS AND POWEll ItEDUCTIOt's Unit Name Tf1I-2 HEPORT MONTil SElW24HElf Date 11 -1 '> '(8 Completed !!y it. A. I,en gel W) 601 Ext..
13 8 4
Telephone P
o l 07 f
li System Cornponen t Cause and Correctlve No.
Date Type cu Code 5 Action to Code li
}k y
$ igg g
e Prevent llecurrence 33 sg g o g
g S N 'al U 'ai f r a s.
un-1 9-1-78 P
l 21.'l II 3
78-33/1P Repair aal Testing of Mains *. ream Safety i
Valves 2
9-20-78 V
9.2 A
3 Ix2us of "A" Main Feedpump 3
9-21-78 P
8 A
3 Control Problema With INPTA h
9-22-78
- )
92 Il 1
Testing of Main Stetur. Sa rety Valves N
NO
([I i
I F; Fo rc ed 2fteason:
3 Methodi j
S: Scheduled A-Equipment Failure (Explain) f r Preparation of Data 1-Munu al it-Maintenance or Test En W 2eets M I.kensee p_gyng,g ge p,,,
I C-Herueling 3-Automatic Scram.
~
D-Itegulatcry llestriction 1 -Other (Explain) 4 E-Operator Training & I.icensee Examination F-Administrative G-Operational Error (Explain)
Exhibi t.1 - Same Source Il-Other (Explain) t 4
i h
I r
Docket No.
50_ 0 0 llHIT Sillf1'DOWHS AND POWElt HEDtlCT10fi:1 Unit, Name TMf-2 HEP 0HT MLiTil sylerFulwn Date 11-15 '(6 Compl e t.ed by H.A. Iengel Telephone 215-929-3601 Ext. lle8 No.
Date Type NC System Component Cause and Correct.ive l
cu I
Code 5 fction to I!$
N
'otan O'
Code 6
as as E) m on as m Prevent Hecurrence ym gp3 g
g e
.r U
CUM NUj
- li d J!
3 di m S
10-5-78 3
198 B
2 The outage was ext. ended due to conax connector problems on t.he stemn generator 6
10-13-71' F
114.S A
N/A The turbine generator was taken off line to reiwtir a hydraulic leak on GVF2 1
- (
1 0-.1 s-71!
F 12.li A
3 The t.urbine t.rlpped due to a reedwater pump problem. The react.or then t.ri p;md on low prea-aure due to manually overcompenuating for t.he turbine trip.
4 N
8 10-l'( '(8 S
1.1 11 N/A hin generator dirrerent lal relay problema g
D l.1 A
N/A 9
10-20 '(h F
i i
10 10-21-'lh F
2.5 A
N/A I1 10-211 '(8 F
90.1 A
1 Breakdown of inaulat, ion on t.he #9 exciter bearing 1s
~
IF. Fo rc ed 2Heuuon; 3
~ "
Me t. hod a S: tie bedu l ed A-E<1uipment 1stlure (Explain) 1-Manu al Il-Maintenance or Tes t.
2-Manual Scruto.
C-He ruel in Event Hep rt, (1.EH) 111e 3-Automatic r iua.
Nt!RKG'0l 61 )
D-Itegulatory llestriction l W her (t qi.'ain)
E-Operator Training & I.icensee h amination F-Adini nis trat.i ve G-Operat.ional Error (Explain)
Fxhibit, 1 - Same Source Il-Other (Explain) i
~
Major Operating Experience The unit entered the month at 4C% power continuing with the 400 power level test plateau. On Oct. 5 tne unit was manually tripped from 40%
p,acr in accordance with the test procecure. The unit was subsequently cooled down for condenser maintenance. Unit heatup began en Oct. 10, but a leak developed at a canax connection on the special instrumentation installed in "B" 0TSG and the unit was cooled down to initiate repairs.
The unit returned to service at 20% power on Oct.13. Socn after the generator breakers were closed, RC-V-1, the pressurizer spray valve, failed to function, reducedto10jheturbinewasremovedfromserviceandreactorpowerwas amps to allow repairs to RC-V-1.
The unit returned to service at 255 power on Oct.14 The reactor tripped from 25% power at 0728 on Oct. 14 due to a loss of main feed pump 1A.
The unit returned to service at 1940 on Oct.14 and power escalation to 40%
commenced.
The 40t power level was achieved on Oct. 15 and main steam safety valve testing commenced.
~
On Oct.17, reactor coolant pump 1A was manually tripped per the test procedure.
Reactor power was reduced to 275 and the coolant pump restarted. Reactor power was then increased to 30% and the turbine manually tripped in accordance idth the test procedure. The turbine was returned to service and reactor power was increased to 40%. Power escalation to 75% reactor power at a rate of 5% per shif t co=cenced.
The unit achieved 75" power on Oct. 20. At 1821 on this date the main turbine tripped due to a generator transmission line phase differential fault. The reactor plant ranback to 15" power. The turbine was returned to service and powm escalation to 750 commenced again.
At 1909 on Oct. 21 the turbine again tripped on a generator transmission line differential fron 625 power. The reactor plant successfully ranback to 155 power. The turbine was returned to service and power ascalation to 75; commenced.
The unit achieved 755 power at 1105 on Oct 22 and the 75" power level testing co= enced. On Oct. 27 power escilatica to 1000 commenced. The unit acnieved 90" power at 01i3 on Oct. 28. At 0453 on the 2Sth i9 bearing on tne main turbine indicated a high vibration. Power reduction commenced and at 0531 the turbine was m.anually tripped and reactor power was reduced to S3, On te:Ober 29.verk begs.: to inspect #9 ber.uing. Se reae:Or was aise shutder. ::
investig=.te prehlens with Et-7-1.
On Oct. 30 Ec.J vas re n. nei t: se: rice der '
switch repai s were
- =plet ed.
At this v-iting verk is :::ti:ning :: i. tea-ing := the c'- :n :ine.
Ea'e-/ Ee'ated.Vaintenance Rese: -'*
s es: relie' n ves at -: p ver.
o qM f. gV I