ML19308C918

TMI-1 Operating Status,Plant Shutdown, June-Nov 1974

ML19308C918
Person / Time
Site:	Crane
Issue date:	11/30/1974
From:	Lawyeer L METROPOLITAN EDISON CO.
To:
References
TASK-TF, TASK-TMR NUDOCS 8002110653
Download: ML19308C918 (42)

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4. M 7,739

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o. sine e fe.ity re-trei red dri.

4 a L b 4 A 41 J u 4 9./ nearter A edeenshew Fergs, e een.e neerger.e.sesses a 100 (a) tue pmspe ree et s

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Unet Capacity Facter Y

a

&Ussne DER het Meel

"~""*'" " * ' ' ' ' * * ' ' ' ~ ' ' " ' ' ' ' "

AVERAGE DAILY POWER LEVEL (MWe)

OPERATING STATUS I

1 Do*M Nwae'er stem 21 concueeted by useg 2 ut.hty Data Prepared By D G M.tcheM151929 3691_

e wefited eveeege 3 L. censed insemei Power ' Wats

_M TMtEE n!LE Isuw01 968 a 0 9 a 871 4 Namepiste Hanne IGree. Moses hune 8

5 De ea E tectrics Nhas 'N M***

1500 840 e w

.moa ospenneo capac.ev #G DESIO*1 ELEC. RATING a 819 ftAX. DEPEND. CAP.

778 (1002)

'"**"""*D*""*'"*C"*'"

8 II Changen Ot.cus e Cmeest, Rotwigs usoms %wmewe 3 Theo sch 7> 5.nre Less Meoort G e beun-9 Power Levee To ten ces RestreseJ if Aa, sNee M..e _ hone 10 heae wes For Nesarscs.<ms if Aav E

1000

~

mE Th.s Moath

• e so Date Cwemuu=.

lW Call 81 EXCEEMS Mt OPTIIWIL C818DITIsm3 1} Mours in heponemg eermai

~~

-8 a.

7 m g-1 = e. (,

• J,s.7.e as Y"-

IM g 12 humoer Of Maurs Reartor was Crit.ca

" ~ ~ - - " -

R is meerio, no e wido.a ours

• L 0

--- M2i A

e.

14 Moves Generator On tone

.-- 11245. ~ 2'*

J J4 hd

. en e-E.a ti unst Rewrwe Shwedowei Mouri

-2.

0 21.-

s e 500 5

16 Gnom Thermes E nergy Genereien ewnMi 141.2 E42.* }.

1412a4h12. 114111sAI.l g

6

< 80 17 Gross Eisc== E aerov G*aeree 'wwM.

_.14 :. 7. l_

1 d4L aialmE

~..

u er g

er c a m -r ~

10 het Eiectrw.m taere, Generseed (f *w Mi

);,,e b J 25 ah 4 44 Ni '

e ' 'ei C en 7

v :en. e da 19 Un e ber==e F ortee

_ J gn g,,_ g g_

7,.t 20 Un t Avedatwe're 8 ocent

.-..t sai.

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I*

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10 15 to 26 30 3*'usoas t 'etieus v17 1979 + ' ' ' * * * -

F ' * * = "

A E'au'o'.'

DAr$

$ Scheoveed 8 Me.eie n ';- :

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or.

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e Lmes Cassaty f ecte

=

tus.re, saDC het Mweet ur t c e.tv.-

(unsag DER 8 met MWel

' ~ ~ " ' " " ~ " ' " ~ ' ' ' '

AVERAGE DAILY POWER LEVEL (MWe)

OPERATING STATUS l

I i

2 289 1 Doemet %mber.

item 21 meted n, usias 2 util.t, Dete Preewmi sy. O c M.te*e's t2111NDH1

• • '**'*d*****

TsimEE st!LE ISLAND 1 2 Lisea.se inw=e e, iunti A

oss e 0 9 = s71 1600

. same en. Rooa,icro wwet Ol' CESIGN ELEC. RATIN3 z 819 6 Demen Emco.es Reting.het Meet

_ PRX.

DEFEND.

CRP. z 776 1100%)

6 Moe,mvv= Dependmue Capacivv iGrou M*er 776

,.e. _ c

.v..

..e :

$ If Cheagn Ocew en Casw.ty Rosenga litem.%enbe. 3 Tweevgh 7: 5. ace L w Neowe G e heems a t

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0

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24 Sm.eno.as Seaso.saed Ove, best 6 Months (Tvee Lee and Dureteoa of techi 1

I 7 ype E

FEBRUARY 1979 g,,,,,.,,,,,,,,,7,,79

,a.sen.P F Fo

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2b H Saut Do.a At Ead Of Aaport Pered. Estemend Dee of startwo A8' 3 7'

'I tih hi. MtLL LSLanu i I.

Summary Description Performance Outages Location: Goldsboro, Pennsylvania Net electrical energy Total No.

2 Docket No: 50-289 generated (MW11):

1,977,812 Forced 1

Reactor Type: Pressurized Water Unit availability Scheduled 1 Capacity (MWe-Net):

792 factor (%):

88.1 Total 346 Itours, 11.9%*

Commercial Operation: 9/2/74 tin i t capacity factor (%):

86.0 Forced 97 Ilours,

3. 3%

• Plant Age: 0 5 Years (Using Design MWe)

Scheduled 249 Ilou rs,

8.6%*

Cause: Equipment Failure 1 Maintenance / Test 1

Method of Shutdown:

J Manual 2 h3 h

i

~ gh l inh t s~

Data is based on date of first com-N II.

lii ti mercial operation - September 2.

I A.

Gene ral_:

1 Initial Electrical Power generat ion occurred on June 9 and commercial operat ion was declared September 2.

Operations were uninterrupted in September and December, and at essenttally full power in December.

d B.

Outages:

~

1.

Forced: There was one forced outage last ing 9 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> to replace a faulty control rod drive motor stator winding.

2.

Scheduled: There was one scheduled outage for 249 hours0.00288 days <br />0.0692 hours <br />4.117063e-4 weeks <br />9.47445e-5 months <br /> to repair leaking rellef valves on the pressurizer.

(

ke

1;h m

t I p '.

- n!E M Bi3 Ed % %y p@ od 4 Gl %q @ nME.a.

y; dn*

w ME

" C.," 5itM *'# * '2 L. 3 $'M i$& g s0ita2 @i% '"'

~

~

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.c-+~-

-~

r._

- -. 3 w.-u en===m.-r.n=-

TifREE MILE ISLAND 1 DETAILS OF PLANT OUTAGES

• Date Duration N*

Shutdown System Component (1974)

(llrs)

Type Description Cause Method Involved Involved 1) 10/20 249 S

Repaired leaking relief B

1 Reactor Valves

-t

^

valves on the pressuri-Coolant zer.

(Cit) 2)

11/17 97 F

Replaced a faulty con-A 1

Reactor Control trol rod drive motor (R3)

Rod stator winding which Drives had caused a dropped rod condition.

f 4

Data for this table covers the peric.; f rom the dat e of commercial operat ion, Sept. 2, through December J

31, 1974.

3 t

M

.o L,J CO g4 I

A

.h A,

t

.f4 J

?

Na JA e

ti

n

6

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e,

<3 Cx,2 a

r I,

iT -

A 'pf 467 -~C*SM -* Jaf.**i N4-hahMMM,$hQgg -}p.;-.s4 M.?@4rM4.f4 g g g g gg g g

.j

.g ffld r

o

/97 rr THREE MILE ISLAND 1 I.

Su=marr Descriotion Performance Outares Locati on :

Middletown, PA Net Electrical Energy Total No.

4 Docket No:

50-289 Generated (!Ta"d):

5,673,616 Forced 2

Reactor Type: PWR Unit Availability Scheduled 2 Capacity (Irde-Net): 776 Factor (%):

85.1 Total:

1306 Ecurs, 14.9%

Ccc:mercial Operation: 9/2/74 Unit Capacity Factor (%)

Forced 218 Hcu s, 2.5%

Plant Age: 4.5 Years (Using MDC):

82.1 Scheduled 1088 Hou s,12.4; Unit Capacity Factor (%)

(Using Design Ir4E):

79.1 II.

Highlights There were six months during the year in which operations were uninterrupted.

Between March 18 and May 12 refueling was accomplished. Operations during the remainder of the year were routine.

1 l

J

'TilREE MILE ISLAND 1 DETAILS OF PLANT OUTAGES Shutdown System

. Component _.

No.

Type Description

'Cause i.

(1978)

(llrs)

Method Involved Involved d

la) 3/18 1086 S

Refueling.

C 1

Reactor Fuel (RC)

Elements-lb) 5/2 2

S Turbine testing.

B 4

Steam &

Turbines Power I

(HA) i 2) 6/22 214 F

Seal failure on RCP.

A 1

Reactor Pumps Coolant (CB) 3)

11/15 4

F Lost DC power to EHC con-A 4

Electric Electrical trol system.

Power Conductors (EC) 1 i

1 i

i l

l i

s

-w

l' I

N C.

JL

-t J

O 1

1 O

N R

L I

Y VS I

R O

F E

M NL I

M e

~

E E

R HT R

1

)

P C0 G

(0 1

i 1

F 8

7 m_

7

=

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PC R

n E.

M SN D

E P

E E

D a

m X

~

A M

B G

E E

J 9 L

1

=

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I y

=

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2 I

T

~

A R

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LC

~

E

[

S J

T LL E

J_

N G

I S

E

)

D 0 0 0 0 0 0 0 0 0 0 0 O 0 0 0 0 0 0 0 0 0 0 0 0 e1 0 9 8 7 6 5 4 3 2 1

1 0 9 8 7 6 5f4 3 2 1

1 1

1 1

UG= a" 5go5to r

• y$

g

/

Surnarj Outages Performance _

Descriotion Total No.

4 Location:

Dauphin, Pennsylvania Net Electrical Energy Forced 3

Generated (MWH): 5,463,439 Scheduled 1 Docket No:

50-289 l

Unit Availability Reactor Type:

PWR Total:

1670 Hours, 19,1%

Capacity (:Ge-::et): 819 Factor (*.) : 80.9 Forced 276 Hours, 3,2%

Commercia' C;aration: 9/2/74 Unit Capacity Factor (%)

Scheduled 1394 Hours, 15,9%

(Using MDC): 78.7 l

Plant Age:

3.5 Years Unit Capacity Factor (%)

(Using Design MWE): 76,2

?

l3 to II.

Hiehli2h:s

~

the year, and there were six months in which operation was The unit operated routinely throughout At the end of the year A refueling outage took place between March 18 and May 16 uninterrupted.

the unit was operating at 100% of maximum dependable capacity, j$

Y A

il 1

yl Y 3*"y

?

ll

.,n n am$#

,,bh g

~

P o

. Tl!REE MILE ISLAND 1 DETAILS OF PLANT OUTAGES

"##E' "

Shutdown System Component No.

Type Description Cause (1977)

(llrs)

Method Involved Involved 1

02/05 7

F Malfunction of Turbine Over-A 4

Steam & Power Pipes, fittings speed 011 Trip Test Tubing (llA) 2 03/18 1394 S

Refueling and repairs C

1 Reactor (RC)

Fuel elements l

3a 09/16

^

F lligh conductivity in secondary G

1 Steam & Power Demineralizers 48*

l side of steam generators was (IIG)

I initial reason for outage.

l l

3b 09/16 144*

F Outage extended due to RC pump A

4 Reactor Coolant Motors cont'd motor malfunction.

(CB) 3e 09/16 69*

F Outage further extended due to a A

4 Steam & Power Generators i'

cont'd

,'{}

main turbine trip resulting from (IIA)

E!

generator ground problem.

o 4

11/14 8

F Failure of ICS Module Signal A

3 Instrumentation Instrumentation Converter "L" (ICS 2-2-3,3)' caused

& Controls (IA)

& Controls reactor power to increase above 103% F.P.

Caused a flux / flow im-balance trip.

• Estimated values, g

i

• 5 Y

)

E o.

s

. m.

.s

,-w.,.

.4~_

ifr sie r

'nc n

,;gcp

{Ig

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110 fi 100

"^

~-

-- f-

~-

90 80 70 60

$ 50 e

! 40 39

'i g

g 20 E 10 t

JN FE MM RPR MRY JUN w

g e=

~

~

"C

~100

-a y

• 90 Eg 80

@ 70 60 l

50 l

l I

iJ.

40 1

I w

I 30 I

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r JLJL_

RLJG SEP OCT NOV OEC o

eee,. <<ec..

1,.

.,e mex.

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0

~

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/

o 9

TilREE MILE ISIAND 1 I.

_Su= mary

_Descrintion Per formance Outages

?

Location: Dauphin, Pennsylvania Net Electrical Energy 1

Docket No: 50-289 Generated (bMI):

4,335,625 Forced 2

Total No.

4 Reactor Type: PWR Unit Availability l

Capacity (!Ge-Net): 819 Factor (%):

65.4 Total:

3,036 Ifours,34.6 %

Scheduled 2 Commercial Operation: 9/2/74 Unit Capacity Factor (%)

Plant Age: 2.5 Years (Using MDC):

62.3 Forced 568 Hours, 6.5 %

yN Scheduled 2,468 Hours,28.1 %

~ ^ '

Unit Capacity Factor (%)

(Using Design MWE):

60.3

co II.

Highlights Ib The unit operated at full power for the first In February, an extended outage was required for refueling and maintenance 15 days of the ye was required.

c returned to service, after the refueling outage, on May 27 and operated continuously withoutThe unit was I,

except for power reductions, for the next 5 months.

interruption, repairs and then returned to service on December 4, whereupon the unitOn November 5, the unit was taken off line for 4

power for u.e rest of the year.

remained at essentially 100%

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Sunmarv Description

_ Performance Outaces Location: Dauphin, Pennsylt.tia

' ret tiectrical Energy Total Mo.

16 Docket Ho:

5')-289 Generated (!S.'n):

5,541,52'l Forced 13 Pcactor Type: PI?It Unit Availability Scheduled 3

Capacity (T?c-net): 319 Pactor (Z):

32.2 Total:

1,559 "ours, 17. C

rhic t clal Operation: 9/2/74 Unit Capacity Factor (%)

Forced 022 I!ou rs, 10.5%

Plant Age:

1.5 '! cars (Using "DC):

79.9 Scheduled li37 Hours, 7.3%

Unit Capacity Factor (C)

(!! sing Design !!"F):

77.3 Cause: Equipment Failure 11

'faintenance or 3

Tent *~1 Operational Trror 2

Method of Rhutdoen:

8

?'anual 7

s Automatic Scram 5

~

II.

Highlights i

A.

General:

A total of 16 outages occurred in 1975.

Eleven wqre related to problems with equipment failure, 3 were for maintenance, and 2 were the result of operational error. There were 2 outages associated with each of the following components: electrical conductors, I & C, transformers, pumps, and valves. Three outages involved turbines, and 1 each for relays, control rods, and control rod drives.

B.

. Outages:

1.

Forced: There were 13 forced outages in 1975. Of these, the ones of longest duration were:

(1) 214 hours0.00248 days <br />0.0594 hours <br />3.53836e-4 weeks <br />8.1427e-5 months <br />, for electrical conductors; (2) 144 hours0.00167 days <br />0.04 hours <br />2.380952e-4 weeks <br />5.4792e-5 months <br />, for replacement of a pump motor shaft; (3) 303 hours0.00351 days <br />0.0842 hours <br />5.009921e-4 weeks <br />1.152915e-4 months <br />, for a turbine control valve; and (4) 104 hours0.0012 days <br />0.0289 hours <br />1.719577e-4 weeks <br />3.9572e-5 months <br />, for repair of a make-up valve.

2.

Scheduled: There were 3 scheduled outages during the report period.

}

l on y.e r. t duration were:

Of these, the ones of (1) 266 hours0.00308 days <br />0.0739 hours <br />4.398148e-4 weeks <br />1.01213e-4 months <br />, to correct problems with a reactor coolant pump; p$

(.' ) 277 hours0.00321 days <br />0.0769 hours <br />4.580026e-4 weeks <br />1.053985e-4 months <br />.. f or cont rol rod in t e rchany.c ; and (3) 94 hours0.00109 days <br />0.0261 hours <br />1.554233e-4 weeks <br />3.5767e-5 months <br />, for control rod drive

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,1 m...i 1 1_ t. o m u otow Date Duration Shutdown System Component No.

Type Description Cause (1975)

(firs)

Method Involved Involved s

1) 1/23 40 F

Personnel error led to C

3 Steam &

Turbines turbine trip.

Power (IIA) 2)

3/30 14 F

A faulty relay gave an A

3 Steam &

Relays erroneous signal which Power indicated loss of DC (llA) power to the turbines 27 EIIC system. The sig-nal tripped the turbine.

The reactor tripped from high RC pressure.

S 3) 4/5 214 F

Faulty cable connector on A

1 Reactor Electrical

]

[

reactor vessel head caused 1

(RB)

Conductors control rod to drop into the core and rod withdraw problems.

4) 5/9 9

F Turbine trip due to mechani-A 3

Steam &

Instrumenta-cal failure in moisture Power tion &

separator high level switch.

(!!B)

Controls

,' w 5) 5/22 16 F

Fans and cooling puups on A

NA Electric Transformers l main transformer tripped Power t

y necessitating removing tur-(EB) bine off line.

j 6) 5/25 144 F

Motor shaf t sheared on DR-A 1

Reactor Pumps PIB.

Unit shut down for Coolant repairs and a previously

?.

4 scheduled control rod (CB)

-g interchange.

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TilREE MILE ISLAND 1 DETAILS OF PLANT OUTAGES (continued)

1. 1. EI "

Shutdown System Component No.

Type Description Cause (1975)

(llrs)

Method Involved Involved i k[.. ~ !

l 7) 5/31 277 S

Unit in scheduled control B

1 Reactor Control

[

rod interchange.

(RB)

Rods

/

8) 6/18 20 F

A brush recorder monitoring A

3 Steam &

Instrumenta-the turbine EllC system Power tion &

'l caused erroneous voltage (IIA)

Controls spikes res"Iting in rapid j

i load reduction and reactor trip on high pressure.

'i 9) 6/21 4

F Turbine had to be taken off A

NA Electric Transformers 4

li the line due to main trans.

Power

( ;]

former problems.

(EB) i 10) 6/25 27 I'

Reactor trip due to high posi-A 3

Reactor Electrical j

p

[j tive imbalance created when (RB)

Conductors ij cont ol rod group 7 Phase

1 Bus bar faulted to neutral causing group 7 rods to drop j

into the core.

d

[j

[:j k

11) 6/26 24 F

When attempting t,o put the A

NA Steam &

Turbines turbine on line after the Power H

reactor was returned to ser-(llA)

_13 vice, the turbine tripped due O

{'

to high eccentricity.

h]

l 12) 9/26 266 S

Repair RC-P-1A to reduce B

1 Reactor Pumps 1

a m

I i

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Coolant

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DETAILS OF PLANT OUTAGES (continued)

No.

1. 1. I"

,,p (1975)

(Ifrs)

Type Description Cause Shutdown System Component

• ..: 1 Method Involved Involved

13) 10/16 94 S

Repair CRD stator.

B 1

Reactor Control (RB)

Rod Drives

14) 11/12 303 F

Repair control rod drive A

1 Steam &

Valves Nechanisms stator; duration increased due to repairs to control Power valve of turbine.

(llA)

15) 12/16 104 F

Repair make-up valve.

A 1

Auxiliary Valves

'e Water e

(WC)

16) 12/22 3

F 3

Turbo gen. trip while C

NA Other Turbines testing the deluge i

system.

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