ML20003A394

From kanterella
Jump to navigation Jump to search
LER 80-033/03L-0:on 801227,one of Four Loops Indicating Pressurizer Pressure & Feeding Thermal Margin/Low Pressure Calculator of Reactor Protection Sys Channel & Safety Injection Actuation Channel,Failed Low.Caused by Blown Fuse
ML20003A394
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 12/29/1980
From: Core M
OMAHA PUBLIC POWER DISTRICT
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML20003A395 List:
References
LER-80-033-03L, LER-80-33-3L, NUDOCS 8102030608
Download: ML20003A394 (4)


Text

- - - . _ _ _ _ - . - _ _ . - - . __ _ - . . _ . - . . ._. . _- -. -_

Pun . . . . . - . . . . . . , . . . . . . . . . .

17-77) j

  • LICENSEE EVENT REPORT i

CONTRolBLOCs0l l l l l l lh (PLE ASE PRIP* r1R TYPE ALL REQUIRED INFORMATION) 7 8 9 l NI E l F l C l Sl ll@l 0101010101010101010101@l4lilllllll@l LICENSEE CO~)E 14 15 LtCf.N5E NVVSEH 25 26 LICENSE TYPE JO I

b 7 LA T 58 l@

) con'T l i

l 10111 7 8

%R$lLl@l01510101012181Sl@l112121718101@l11212191810l@

60 61 DOCAET NUVSER 68 63 EV ENT DATE 74 76 REPOH T OATE 84 EVENT DEiCRIPTioN AND PROB ABLE CONSEQUENCES h tol2ll Durink power operation, one of four current loops indicating pressurizer pressure andl

) io i3i I feeding the thermal margin / low pressure calculator of one Reactor Protective System I o 4 l channel and one Safety Injection Actuation channel failed low, placing the SIAS in 1 I F5Ts1 l half trip and tripping one Ti1/LP channel of the RPS. The RPS "B" channel wculd not l i,

iO is i ! have tripped on high pressurizer pressure. The RPS was placed in two-out-of,-three l j l O 171 [ logic by bypassing the "B" channel TM/LP bistable. Technical Specification 2.15 l 1Otai I applies. I 80 y g 9 C DE CODE S SC E COMPONENT CODE SUB DE SU DE l0l9l l Il Al(U) [Ej@ W@ ll IN lS lT lR lu l@ LPl@ 18 19 _

Lzj @

10 7 8 9 10 11 12 13 SEQUENTIAL OCCURAENCE REPORT REWSION LEp no EVENTYEAR REPORT NO, COCE TYPE NO.

@ 4'g,a; 18 10 I l-l Io13I3I Lo lo 13 i LL_j [-j [0]

, _ 21 JJ 23 24 .'G 27 25 29 30 31 32 I

KEN AC ON ON PL A* T MET D HOURS S B IT FORi B. SUPPol MAN FACTURER IAl@lZl@

JJ J4 LZj@

35

[._Zj@

J6 l0101010I 3J 40 L_J@

41 In 42 l@ l43Al@ lG 44 l0181047l@  !

CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h j [1Lo ] l After investination. it was discovered that the current 1000 fuse in the CE/MAC lilil l Type 570 power supply for the B/ PIA-102Y loop had blown. The fuse was roolaced and I i,i,ii the loop returned to normal after comparing the loop current with the other three I gl loop currents measuring the same process.  !

i < l

, I 80 l 7 8 9

[ STA S  % POWE R OTHER STATUS 015 O RV DISCOVERY DESCRIPTION

! m LE_j@ l 0 l 7 I 5 l@l NA I l A l@L operator observation I

' " ** ** '" 8 l

' JTivit y CO4 TENT RETE AsEO OF RELE ASE AMOUNT OF *CTIVITY LOCATION OF RELEASE NA l 7

i c 8 9 W @ W@l 10 il NA 44 l l 45 80

, PERSO%E L EXPOSURES t '

NuvafR TYPE DESCRI8TI l

[TIB 1010101@l '

zl@l" NA i PERsOwf t'iNau'R'iES

! NuveE n otSCn,PnON@

NA l 7

i a 8 9 1010101@l12 11 80

, LO'S OF OR D AV AGE TO F ACILtTV j TYPE D ESCRIP flON t 9 l NA l-

' 80 7 8 9 to l Pustictiv ,Q NRC USE ONLY ,

l Ob0h .a .a. - . . - . - . - . -- .- . . -

4

. i a-

LER 80-033 i Omaha Public Power District Fort Calhoun Station Unit No. 1 -

Docket No. 05000285 ATTACHMENT N0. 1 Safety Analysis The Reactor Protective System is designed in such a manner that no-t single failure will prevent it from performing its design function. The failure of the B/P-102Y loop placcd the "B" channel-Thermal Margin / Low i Pressure trip bistable in the trip condition and was immediately by- t passed, placing the RPS in two-out-of-three logic. Further, the failure 4 of the loop rendered the "B" channel High Pressurizer Pressure trip bistable inoperative. However, during the time the "B" loop was in-operable, the other three channels-of the RPS were operable and wo.'d have performed the design function of the RPS; that is, trip the re-4 actor. Further, the Safety Injection Actuation Signal logic was in half 3- trip, as it should have been with the failure of the instrument loop, j and was, therefore, conservative.

At all times, the minimum degree of redundancy conditions were met.

i

}

l 6

i

?

i  !

i J

f 4

e f

e - -1 -

n -e-, , - , , ,w-w..--,ew v.-+-. --m%+ -w-,r, y-s v-' ,w=w ;3 r-mn, v -rv = a- g e- we -y- y-- 've- e,w-p vv. y , v- w, ,, ----,.e.- , , w e-

4

. 1 i

LER 80-033 1

Omaha Public Power District i Fort Calhoun Station Unit No.1 7

Docket No. 05000285 ATTACHMENT NO. 2 f

Corrective Action 4

After troubleshooting the loop for malfunction, it was discovered l that the loop current fuse in the power supply, a GE/MAC Type 570, had

. blown, thus opening the current loop. The loop fuse was replaced and the loop returned to service. The RPS & SIAS circuitry was verified to be reset and the bypass keys removed, placing the RPS into its normal two-out-of-four logic. No further corrective action is anticipated.

e i

I 4

w f

1 i

2

, s 4- 2.,.~ . , , , , , , . . . . . . . - 4 .4- , , + - -, , , -s , - , , . . -,..-r ;J -, r,., ,, ,4 - -,--

. w LER No.80-033 Omaha Public Power District Fort Calhoun Station Unit No.1 Docket No. 05000285 ATTACHMENT NO. 3 Failure Data This is the first reportable occurrence of this type in loop 102Y at the Fort Calhoun Station. Other fuses in GE/MAC Type 570 power supplies have failed; however, these failures have always been in the conservative direction (failed safe) or involved non-safety related equipment.