ML19261F290

From kanterella
Jump to navigation Jump to search
Abnormal Occurrence 50-289/74-15:on 740911,during Quarterly Surveillance of Reactor Bldg Cooling & Isolation Sys Logic, Spray Valve BS-V1B Failed to Open.Caused by Improperly Installed Wire.Wire Removed & Blown Fuse Replaced
ML19261F290
Person / Time
Site: Crane Constellation icon.png
Issue date: 09/20/1974
From: Arnold R
METROPOLITAN EDISON CO.
To:
References
GQL-0344, GQL-344, NUDOCS 7910250741
Download: ML19261F290 (4)


Text

,. _ q.

.....,......, -.- - < 3..,..--.

u.

-., 1,

q

(... :..,. -. r..,.,s

.._m e e. -. e.

v,.,... _9847 _

TII.E :

v. p. e s...

pA., o.r cCw"

'u -- - erc.-

A

.t....

-x ta Metrop*.litad Edison Co

,.,..=;...

Reading, Pa 19603 R C Arnold 9-20-74 9-24-74 XX TO:

e ORIG CC CTi-2R SE:iT AEC ?:R yy Sg'.-, ce ~.,

~.

DL 1 signed

~ YY CIASS.,

L7;CL.uS

?RCP INFO INFUT 2;0 CYS ?20'D DCCF2T :;0:

AAAAAAAA 1

0-289 DESCRIPTION:

E';CLCSU?lS :

Ltr re Abnormal' Occurrence #74-15 on 9-11-74 concerning the inability of the Reactor Building Spray Valve BS-VlB to open during testing.....

co

,r n

J.bp,p, !MNgb i ;nM-D D

i

=

_.o a l'IJ2iT NE3

  • THREE MILE ISLAND #1
, 3 n-.....-.-.,....,...

9-24-74 ent o,... L..,. (. )

s u.... :.. - - - ( u, )

zI.....,. ( u. )

u.G,,,,. ( c. )

.t m

v

.s....

t;/ CYS W/ CYS U/ CYS

'/ CYS CLARK (L) sTOL2 (L)

OICKER (E)

EAR U/ CYS v/ CYS w/ CYS v/gCYS

...,..i.,,,

t/ CYS w/ CYS u/ CYS W/ CYS IOil'L (L)

PURPLE (L)

YOUNG 3LCCD (E)

V/ CYS W/ 'CYS U/ CYS W/ CYS

(

1..7. ;. g.

..7.........

,a3

-.t q..:.g. _ ;.

...i

{:.p

.a o

.s j :

1.. q ac a J,'.7.C F P.

.GRI:'.ES DIC35 (L)

ERA 1IY 4.

/,CCC

/cCHRCIDER GASO!ILL GEARI:* (L)

SALTZ 5'A';

  • VUNTEIC /STA? ?

lACCARY KASTNER GOULECU?';E (L)

3. iCET s.
  • / CASE

' NIGHT 3ALLARD KREUTZER (E)

G.92:3US50 A'n'LICKI SP.'J;0 LER LEE (L)

PU2;S 1GYO pHA0 MAIG?l? (L)

P.CDC:.ALD M' CRE (L)(L:.2-2) v5TELLO ENVIRO REED (E)

CEAPMA'.

DEYO':50 (L,' ( L'.2-1)

ACUSTCN MULLER SERVICE (L)

DUEE w/irpu:

SKOVHCLT (L)

M;CVAR DIC72R SHEPFARD (L)

E. COUPE GOLLER (L) 5./?.05S IC;IG HTC'.

SIATER (E)

P. COLLINS

/TPPCLITO YOUNOILCCD j:IITH (L)

/D.THOMI^:: (2)

DE'?!SE dEDESCO REG.221 W EETS (L)

/KLECKE?

f'. REG CFR

/ 0'.;.G PROJECT MCR L'ILLIT:S (E)

/IISE:;.ET t

t. 7..,

(., )

.2 j.u.u....c...:.s...

(= 2...,.

..I.,.S u,.... ( )

a

-....-.m...

.t:..,.=..=.

....s

./

n.. %r....z

\\ h

.x

  • e,.=..=..-

\\

\\

.e....,. -,

_a..

'.C C.i '. 2 2. Harr is bur g, Pa

.g-si. ss......

r.--

L.%

-t.' L.

.n (As\\-}\\ 41

..s.-

..^.r 9~pr-:.-

..J h 1

s. q ' p

(:,'...

.........)

.C.

  • r., - (' J.,'..

'.1 s 4' '1'\\

. ~.

L e-L".'6.........

. a' *

^-

.2r

..O.e 3 1 e.,, c.:.,..r..--,'.....

.+

as.

y

.m..

e-

, e r

t.

u.

v.....

. 3'J N.1 P.C c '." 3 0 3 1

.p e..

3..., - -

,..........s

.we....... -..

c.;.. ; a./

v&

w.r..L.,

s. a.c.

CL SE:.. IQ m:0 ' SS'?

TEETS 1-CC; '-. '. ' '.;

E:: 2 *..' ~ C M

1 910'86Q W }

}

W A P-t.%- n i 2

7,Q. ",.,,

x-,n METROPOLITAN EDISON COMPANY DOC

  • cFFICE BOX 542 RE AclNG, PENNSYLVANI A 19603 TELEPwCNE 215 - 329 : Col SEP 2 01974 Regulatory Decket File os Osuu Director Directorate of Licensing U. S. Atc=ic Energy Co==ission Washingten, D. C.

20545 tear Sir:

Operating License DPR-50 Decket No. 50-289 In accordance with the Technical Specifications fcr Three Mile Island Nuclear Station, Unit 1, we are reporting the folleving abnormal occur-rence:

k

/'

(1)

Report Nu=ber: A0 50-289/7h-15 hkU TAk (2c) Report Date: Cepte=ber 20, 1974 3

r 14 SEP N 7979 @\\

(2b) Occurrence Date: Septe=ber 11, 197h G

r; m (3)

Facility: Three Mile Island Nuclear Statien, Unit 1 C.)

c fQ' '--;.i O[ V':p (k)

Identification cf Occurrence:

c t

'y /

Title:

Inability of the Reactor Building Spray Valve BS-V13 to Open During Test Type:

An abncr=al occurrence as defined by the Technical Specifi-cations, paragraph 1.8d, in that che inability of the Reactor Building Spray Valve BS-VlB t) cpen thrcatened to cause an Engineered Safeguard feature er system to be incapable of performing its intended i'uncticn.

(5)

Ccnditiens Prior to Occurrence: The reactor was at steady state power with =ajor plant parameters as follows :

e.

} kh

-Q' k' Power:

Core: 75%

Elec: 655 W (Gross)

RC Flev:

Ikh x 10 lbs/hr b d'$f

Directerate of Licensing SEP 2 01974 RC Pressure: 2155 psig RC Te=p.:

579 F FR2R Level:

260 in.

PRZR Temp.:

650 F (6)

Description of Occurrence: At 1500 hcurs en Septe=ter 11, 197h, while the quarterly surveillance of the Reacter Building Cooling and Isolation System logic was being perfor=ed, Reactor Building Spray Valve BS-V13 did not respend to an open signal because of a blevn centrol fuse. The valve did open when two other autc=atic 1cgic channels and the manual actuatien were tested.

(7)

Designation of Apparent Cause of Occurrence: It has been dete:::ined that the cause of the occurrence was an improperly installed wire in an Engineered Safeguards Actuatien System Lcgic Panel in cen-junction with a spurious ground on the 1A statien battery. The existence of these cenditicus plus an Engineered Safeguards actuatica signal permitted a never-before-encountered current path to ground. The current flov which resulted vas, in turn, sufficient to cause the centrol fuse to blev. It is believed that the i= prop-erly installed wire was the result of a manufacturing error.

(8) halysis of Occurrence: It is believed that the failure of Reactor Building Spray Velve BS-VlB to open did not represent a threat to either the health or safety of the public in that Spray Valve BS-VlA and the redundant spray pu=p system associated with it were still available in the event an accident had cecurred.

(9)

Corrective Acticn:

The folleving shcrt-ter= corrective acticas were taken in the crder given:

a.

The imprcperly installed vire was re=oved, thus correcting the faulty viring conditiens; and the ground identified and ccrrected.

b.

The blown fuse was replaced.

c.

The affected spray valve was tested and was fcund to perfer=

satis factorily.

At a meeting b-1d in=ediately after the incident was reported, the Plant Operaticns Revf v Cec =ittee (FORC) reviewed aid approved the above corrective actions and reccc= ended to the Staticn Superintendent that in addition a detailed visual inspacticn cf tne viring in all of the Engineered Safeguards Actuation Syste= Legie Cacinets be perfor ed to deter =ine the existence of any =anufacturer errors.

\\

\\

Directc. ate of Licensing SEP 2 0 $74 The Statien Superintendent cencurred with FCEC's recc==endaticn and has directed the recc== ended corrective action to be taken.

(10) Failure Data:

a.

Previous Failures: Nene.

b.

Equipment Identificaticn:

Engineered Safeguards Actuatica Syste= Lcgic Cc net SA A. O. Smith Ccrporatien Clark Centrol Division.

Sincerely,

(

.<.'irnold Vice President ECA:JFV:sh File 7 7 3 5 1 20.1.1 cc:

Mr. J. P. O'Reilly Directorate of Regulatory Operations, Region 1 U. S. Atc=ic Energy Cc==ission 631 Park Avenue King of Prussia, Pennsylvania ISkO6

.