ML18283B441

From kanterella
Jump to navigation Jump to search
LER 1977-003-00 for Browns Ferry, Unit 3, Reactor Low Water Level Scram Switch LIS-3-203D Failed to Operate During Routine Surveillance Testing
ML18283B441
Person / Time
Site: Browns Ferry  Tennessee Valley Authority icon.png
Issue date: 03/07/1977
From: Fox H
Tennessee Valley Authority
To: Moseley N
NRC/RGN-II
References
LER-1977-003-00
Download: ML18283B441 (8)


Text

195 U.S. NUCLEAR REGULATORV COI ISSION DOCKET NUMBER FilRI F OR M I2.7BI 50-296 FILE NUMBER NRC DISTRIBUTION FoR PART 50 DOCKET MATERIAL INCIDENT REPORT FROM: DATE OF DOCUMENT Tennessee Valley Authority 3/7/77 Chattanooga, Tennessee DATE RECEIVED Mr. Norman C. Moseley H. Fox ST 3/10/77 X(LETTER 0 NOTO 8 IZE 0 PROP INPUT FORM NUMBER OF COPIES RECEIVED OORIGINAL jZUNC LASS I FIED IN'cop v None signed DESCRIPTION ENCLOSURE Ltr. trans the following: Licensee Event Report (RO 50-296/773) on 2/8/77 concerning the reactor low water level scram switch LIS-3-203D failing to oper'at)....

I

,i I 'e PLANT NAME: (1-P) (1-P)

Browns Ferry Unit No. 3 NOTE: IF PERSONNEL EXPOSURE IS INVOLVED SEND DIRECTLY TO KREGER/J, COLLINS FOR ACTION/INFORMATION 3 11 7=7' : "'JL

=BRANCH CHIEF: Schwencer W 3 CYS FOR ACTION LICo ASSTo: She ard W CYS

@CR$ XS 88h&XN6 S INTERNAL D IST RI BUTION

~G'ILE MIPC SCHROEDER/IPPOLITO

-HOUSTON NOVAK/CHECK GRIMES CASE BUTLER HANAUER TEDESCO/MACCARY EISENHUT BAER SHAO VOLLMER/BUNCH KREGER/J COLLINS EXTERNAL DISTRIBUTION CONTROL NUMBE R LPDR TIC:

N

J

\ \

'L c<,J .'

II f )

1 I

~()g)TIO(t e

. ~

TENNESSEE YALLEY AUTHOR[TY O m CHATTANOOGA, TENNESSEE 37401 C

M4

'~re-19<~

ij~>~&a<ALQ~4 g M44III;44 March 7, 1977 gfgilS

> +'~

ge Mr. Norman C. Moseley, Director IIA~OC4I U.S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region XI ~ 4' 230 Peachtree Street, NQ., Suite 1217 Atlanta, Georgia 30303

Dear Mr. Moseley:

TENNESSEE VALLEY AUTHORITY

- BROOMS PERRY NUCLEAR PLANT UNIT 3-DOCKET NO+ 50-296 FACILITY OPERATING LICENSE DPR&8 REPORTABLE OCCURRENCE REPORT BFRO-50-'296/773 The enclosed report is to provide details concerning the reactor

-low water level scram switch LIS-3-203D that failed to operate during routine surveillance testing. This report is submitted in accqgdance with Browns Ferry Technical Specifications Section 6.

This event occurred on Browns Perry unit 3.

Very truly yours, TENNESSEE VALLEY AUTHORITY .. oocrofa

~/(eh~

Hi Si Pox Qg u.4'4. NUCHAR eoMMI R

0

~<o 5 Director of Power Production JAo I g) t Enclosure (3)

CC (Enclosure):

Director (3) r Office of Management Information and Program Control U.S. Nuclear Regu atory Commission Washington, D.C. 20555 Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Vashington, D.CD 20555 An Equal Opportunity Employer

~ ~

41 1

89'0 LiCENSEE EVBN1 Hhl UHi e

CONTROL BLOCK:~ SE PRINT ALL REQUIRFD INFCRti.ATIQY) 1 LICENSEE LICEtJSE EVENT lI ll LID tJAVIE LICENSE NUMBER TYPF TYPE A "L Bl R F 3 0 0 I IOI OI 0 0 OI 0 0 I 4 ~013'9 32

~

14 15 25 26 30 31 REPORT PEPQAT AEPCRT CAEE CATEGORY TYPE SOURCE DOCKET NUtISER EVENT DATE

, [DD~JCONT L L 0' 0 0 2 9 6 Ot2 0 8 7 7 8 57 58 59 60 61 68 69 74 75 50 EVENT OESCRIPTION .

During routine surveillance testing, the reactor low water level scram switch 89 80 LZS-3-203D failed to operate. Redundant. switches were available and. operable.'his }

"7 is not a repetitive occurrence. The faulty micro switch was replaced, tested, and BO 7 8 9 I~15 returned to service.(BFR0-50-296/773) 7 8 9 BO' Qi3 5 8 9 PRiiIE SYSiEM CAUSE CQMPQIJEtJT CO!APQNENT CODE CODE COMPONENT CODE SUPPUEA MAtJUFACI UPDi VIQULTCN I~7 ~LA ~E 2 N S T R U 17

~N 43 B 0 810 47 L~J 7 8 9 10 1i1 12 CAUSE OESCRIPTION An erratic micro switch was'he cause. Barton Model 288 PdTS. The, switch was 7 8 9 i~IS re laced.

8 9 BO i+0 l,,

8 9 FACILITY METHOD OF STATUS  %, POVVER OTHER STATUS OISCOVEAY DISCOVEAY 0-SCRiPTtci J E ~Oe N/A B Durin surveillance testin 7 8 9 10 '-12'. 13 44 45 . 46 60 FORM OF ACTIVITY CONTENT-RELEASEQ OF RELEASE AMOUNT OF ACTIVITY LOCATION OF REI.EASE ii 2 Z Z N/A 7 8 9 10 11 44 45 80

. PERSONNEL EXPOSURES NUMSER,TYPE OESCRtPTION =

}~!a ~OO 0 ~Z N/A 8 9' 11 '12 -13 80 PERSONNEL INJURIES NUMBER OESCAIPTION

~oo o N/A BO 8 9 11 12 OFFSITE CONSEQUENCES I Ig 7 8 9 N/A eo LOSS OR OAliilAGE TO FACILITY TYPE DESCRIPTION Z N A 8 9 10 PUBLICITY N/A

'OOI i ION ' FACTORS iBI N/A

<<9g TENNESSEE VALLEY AUTHORITY O

CKATTANOOGA, TENNESSEE 37401

~p)6.1916 March 7, 1977 Mr. Norman C. Moseley, Director U.S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region II 230 Peachtree Street, NW., Suite 1217 Atlanta, Georgia 30303

Dear Mr. Moseley:

TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT UNIT 3 DOCKET NO. 50-296 FACILITY OPERATING LICENSE DPR-68 REPORTABLE OCCURRENCE REPORT BFRO-50-296/773 The enclosed report is to provide details concerning the reactor low water level scram switch LXS-3-203D that failed to operate during routine surveillance testing. This report is submitted in accordance with Browns Ferry Technical Specifications Section 6.

This event occurred on Browns Ferry unit 3.

Very truly yours, TENNESSEE VALLEY UTHORITY S. Fox Director of Power Production Enclosure (3)

CC (Enclosure):

Director (3)

Office of Management Information and Program Control U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Director (40)

Office of Xnspection and Enforcement U.S. Nuclear Regulatory Commission Washington, D.C. 20555 An Equal Opportunity Employer

h

~ ~

'a k l ~

f I II II J

I'

)i I

II l I'.

'4 C', )I 'p t[

A

~ ~

)'

d ~ ~

~ ~

CONTROL BLOCK; (P 6 PRINT A' R -QUIRc,o INFORVATQN) 1 t.CEttSE F VENT

'ii- zl LICENSEE NAVE LFCEttSE NUMBER TYPE TYPE L B R F 3 0 o o ol ol o ol ol o zl! Izl+x 32 7 89 14 15 25 26 30 31 REPORT REPORT C-tE CATEGORY OOCKET NUMBER EVENT OATE REPORT TYPE SOURCE

~oIz'VENT

~

~21 CON'T z z, 0 5 0 2 9 6 0 t 2 0 8 7 7 8 57 58 59 60 61 68 69 74 75 OESCRIPTION During routine surveillance testing, the reactor low water level scram switch

-89 60 LIS-3-203D failed to operate. Redundant switches were available and. operable. This 8 9's not a repetitive occurrence. The faulty micro switch was replaced, tested, and GQ 8 9 GO 7

i~~5 returned to service. (BFRO-50-296/773) 8 9 DQ'/DS CQ 7 8 9 ~.I = CO!8?D.'eE!IT SYSTEI.I CAUSE CO!A?DNENT CODE CODE COMPONENT CODE SU?PUER MAttUF'CTUPSR

~zz 8 9 10 E

11 12 z N S T R U 17

~N

.43 B OI 8I 0 47 N

48 CAUSF OESCRIPTION An erratic micro switch was'he cause. Barton Model 288 PdIS. The. switch was 7 8 9

~)9 replaced.

GO

'~i0 I 'I,.

FACILITY STATUS POWER OTHER STATUS METHOD OF DISCOVERY OISCOVERY DESCRIPTION r

. J'i lgal . ~E ~oo N/A Durin surveillance testing 8 9 10 12 13 44 45 46 GQ FORM OF AMOUNT OF ACTIVITY LOCATION OF RELEAS~

N/A N/A 7 8 9 10 11 44 45

. PERSONNEL EXPOSURES NUMBER ~ TYPE OESCR!PTION

!~! ~oo '

o z

'l3 N/A 80 7 8 9 11 12 PERSONNEI INJURIES NUtABER OESCR!PTION FH ~oo o ego 7 8 9 11 12 OFFSITE CONSEQUENCES t 1~5 N/A 7 8 9 LOSS OR OAtv'AGE TO FACILITY TYPE OESCR:PTION z N A 7 8 9 10 PUBLICITY N/A

'OOITION'L FACTORS c

I N/A 8 9

/~