ML18283B448

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LER 1976-020-00 for Browns Ferry, Unit 3, Drywell Temperature Recorder TR-64-52 Became Erratic During Startup Testing
ML18283B448
Person / Time
Site: Browns Ferry  Tennessee Valley Authority icon.png
Issue date: 01/10/1977
From: Fox H
Tennessee Valley Authority
To: Moseley N
NRC/RGN-II
References
LER 1976-020-00
Download: ML18283B448 (6)


Text

NRC FORM 1/5 U.S. NUCLEAR REGUI ATORY COM ION DOCKET NUMBER (2 76 I 50-296 FILE NUMBER NRC DISTRIBUTION FoR PART 50 DOCKET MATERIAL INCIDENT REPORT ':.

TO: FROM: TVA DATE OF DOCUMENT Norman C. Moseley 1>>10-77 Chattanooga, Tennessee 3740 H. S. Fox DATE RECEIVED l-l -7 I.ET ER QNOTORIZED PROP INPUT FORM NUMBER OF COPIES RECEIVED ORIGINAL PjfVN C LASS I F I E D 1 signed org.

OCOP Y DESCRIPTION ENCLOSURE Ltr. Trans The Following: Licensee Event Report (RO 50 296/

7620) on 12-12-76 concerning that during startup testing drywell temperature recorder

( 1 ~~ ) TR-6II-52 became erratic.

( 1 encl rec'd )

( 1 page.)

=PLANT NAME: BROWNS FERRY UNXT P. 3 ACZNOVn,EDGED NOTE: IP PERSONNEL EXPOSURE IS INVOLVED

.DONOT REMOVE SEND DIRECTLY TO 'KREGER/J; COLLINS FOR ACTION/INFORMATION BRANCH CHIEF:

W 3 CYS FOR ACTIN LIC, ASST': LEE W CYS ACRS CYS %%8%H8 S INTERNAL DISTR I BUTION

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-NRC PDR I&E 2

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TENNESSEE VALLEY AUTHORITY O Pl CHATTANOOGA. TENNESSEE 3740'I b.

'~~a-tete January 10, 1977 Regulatory Docket File Mr. Norman C. Moseley, Director U.S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region II 230 Peachtree Street, NW., 8th Floor 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-50-296/7620 The enclosed report is to provide details concerning the drywell temperature recorder TR-64-52 that became erratic during startup testing. This report is submitted in accordance with Browns Ferry Technical Specifications Section 6. This event occurr on Browns Ferry Nuclear Plant unit 3.

Very truly yours, TENNESSEE VALLEY AUTHORITY OL t-/y>~

".> wa>g ~reut~~

eo~ us IQg H. S. Fox Director of Power Production I

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

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LICENSEE EVENT REPORT ~

<<CONTROL BLOCK: t'PLEASE, T ALQ REQUIRED INFORMATION) .

~e LICENSEE LICENSE EVENT NAME LICENSE NUMBEA TYPE TYPE

+0' L B. R R B 0 0 0 0 0 0 0 0 0 4 1' 1 1

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89 14 15 25 26. 30 31 32 AEPOAT AEPOAT CATEGORY TYPE SOURCE DOCKET NUMBER EVENT DATE AEPOAT DATE 0 5 0 0 2 9 6 1 2 1 2 7 6 le+>come 8 57 58 59 . 60 68 69 74 75 80 EVENT OESCRIPTION During sta'rtup testing 'drywell temperature recorder TR-64-52 became erratic. .A 89 80 redundant indicator, TT.-64-52, was operable. (BFRO-50-296/7620) 8 9 80 i+04 9 80 7 8 9

~as 8 9 80 SYSTENI CAUSE QlPAME I elI e<<e <<Qe epQele~g

'ODE CODE COMPONENT CODE SUPPUQI MANUF ACT UFER

~os ~ID 8 9 10 E N S T R

'7 U N 43 Z 9 9 9 a7 48 7 11 12 CAUSE OESCRIPTION Ioom I The checmcccup'le lead was found broken insid'e the junction box"and was connected.

7 8 9 80 7

Q~ I 8 9 Climatic - 0/600 F cu/con. 'A loose set screw holding terminal block in place may I~I", I -have allowed excessive vibration of thermocou le leads.

7 9 80 FACIUTY METHOD OF STATUS POWER OTHER STATUS DISCOVERY DISCOVERY OESCR>PTION Q~g,. B I ~oe B Routine inspection 7 8 9 10 12 13 44 45 46 80 FOAVI OF I AC.IVITY CONTENT AELEAS O OF RELEASE AMOUNT'OF ACTIVITY LOCATION OF RELEASE

~$ 2 Z Z EA NA 8 9 10 11, 44 as PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION

~QO 0 Z 7 8 9 11 1P 13 80 PERSOI"NEL INJURIES NA I11I LQL~I 7 8 9 '1 12 80 OFFSITE CONSEQUENCES Q~g 7 8 9 80 LOSS OR OAMAGE TO FACILITY TYPE DESCRIPTION EG6 7 8 9 LJ 'Io 80 P.UBLICITY 7 89 80 AOO!TIONAL FACTORS r 89 80

[ll9j 89 80.

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