ML18283B027

LER 1976-015-00 for Browns Ferry Unit 2, Offgas post-treatment monitor(2-RM-90-265) Suction & Discharge Sample Lines Were Found to Be Reverse During Startup Testing

ML18283B027
Person / Time
Site:	Browns Ferry
Issue date:	11/11/1976
From:	Fox H Tennessee Valley Authority
To:	Moseley N NRC/RGN-II
References
LER 1976-015-00
Download: ML18283B027 (10)

Text

~ '

~ ~~

~ ~ I ~

~ ~ ~

~ ~

0 ~ ~

~ ~ P

~ ~ ~~

~ ~ ~

~ ~  ! ~ ~ II ~ ~~

~ ~ ~

gl ) ) ~ ~

II ~ ~

~

~

I I

~ x ate ~ ~ I

~

~

~ ~ 8 ~

I' ra et i ~

g gF ~t

+I%i j i

@4

~oiVTlOy

~

TENN SEE VALL'EY AUTHORITY 0

0 rTl CHATlANOOGA. TENNE55EE 3740l 8

~

1))6-1916

't November ll, f9'l6 @iyiataly Docket 88 eP Hr. Norman C. ?Ioseley, Director ef.KIfI;II U.S. Nuclear Regulatory Commission Office of Inspection and Enforcement JOAN $ 8)ggII l Region, IX n 230 Peachtree Street, NI7., 8th Floor Atlanta, Georgia 30303

Dear'Ir,

. Noseley!

TENNESSEE VALLEY AUTHORITY - BROWS PERRY NUCLEAR PLANT UNIT 2 DOCKET NO, 50-?60 - FACILITY OPERATINC LICENSE DPR<<52 ~ REPORTABLE OCCURRENCE REPORT BFRO-50-260/7615 The enclosed report is to provide details concerning the unit 2 ggQ~as post-treatment. monitor,(2-HH-90-265) suctio d dischar e sam le t St ound to e reverse ur ng startup testing. This report is su m accor ance w ical Specifications Section 6< This event occurred on Brogans Perry Nuclear Plant unit 2.

Uery truly yours, TENNESSEE UALLEY AUTHORITY

~rg

$ 7/

H. S. Pox Director of Power Production Enclosure (3) or CC (Enclosure):

Director (3)

Office of lfanagem nt Information and Program Control U,S. 'Nuclear Regu story Commission Washington, D.C. 20555 Dire Office of Inspection and Enforcement

• Q.Si Nuclear Regulatory Commission Washington, D,C. 20555 I ~,'$ rl'P qg p n Fquat Opportunity ErnpioYar

t 4 IRI)

'>7 C I

I I) sh3 f@x0 gofshgg III*R-,~ .. ( J It 'I

%If

~NSSX YON I pn~~

'E. 80~ I IJ I

RI I I tl

<<',5 I lt I' 'P t I lt I,

1 I I ' 'Y

<<RR -Itt It rg R

' lt I~

It I I I 'J, I'7 Rt Rt 7. I RIR J I I

'I I R I.

7 CI R 7 '

J 7

It lt 8 [f0 7

'7 7

I 't 1 tt1 f 7 ~

~

IR I, I 1

1 I

tt J f' . R l P I

LICENSEE EVENT REPORT sa~~W'ONTROL BLOCK (PLEASE ~sNT ALL REQUIRED INFORMATION)

LCENSEE LCENSE EVENT NAhlE LCENSE NUMBER TYPE TYPE

~1 A L B R P 2 0 0 0 0 0 0 0 0 0 1 1 1 1 LOU~33 89

~01 tQTTT 7 8 CATEGORY

~l 57 58 REPORT TYPE L

59 14

~L 60 15 REPORT SOURCE 61 o 5 OOCKET -'NUMBER o o 2

'iLa~ILZLZM 68 25 69 26

'VENT OATS 74 30 75 31 32 REPORT DATE I

80 I

EVENT DESCRIPTION

~0 2 Durin startu testing the unit 2 off as ost-treatment monitor 2-RH- 0-26 7 8 9 80 and discharge sample lines were found to be reversed'. Since startup 'the monitor has I

7 89 60

~os been indicating the activity upstream of the charcoal beds rather than downstream~

7 8 9 BFRO-50-260/7615 7 8 9 60 I00BI I 7 89 PRME SYSTEM CAUSE COMPONENT COMPONENT COOE COOE COMPONENT COOE SUPPUER MANUFACTURER

[007I ~B3 A I N 3 T R U z 9 9 l9 7 8 9,.10 11 12 17 44 47 CAUSE DESCRIPTION roOI 1nstallation error..

7 8 9 60

'[oasj I 7 89

~10, f 89 METHOO OF FACIUTY STATUS POWER OTHER QTATUS OISCOVERY DISCOVERY OFSCRIPTION

[ii)] .

~a ~() 3 P NA 0 Lonusual ldonftor 'Res onse Noted 7 8 9 10 12 13 44 45 46 60 FORM OF 1 ACTIVITY CONTENT REI.EASEO OF RELEASE AMOUAIT OF ACTIVITY LOCATION OF REI.EASE

~z z NA Q>g 7 8 9 10 11 44 '5 NA,

~ PERSONNEL EKPOSURES NUMBER TYPE OESCRIPTION

~3 ~Oa 0 7. NA 7 89 11 12 13 60 PERSONNEL INJURIES NUMBER OESCRIPTION

[ig ~oo 0 NA 7 89 11 12 60 ~

OFFSITE CONSEQUENCES NA 7 8 9 LOSS OR DAMAGE TO FACILITY TYFE OESCRIPTION

[ice] z NA 7 89 10 PUBI.ICITY NA 7 89 ADDITIONAL FAC;QRS QB Znstallation of similar lines on units 1 and 3 has been verified correct.

/ 89 Bb 7 89 NAME:

d 7 v PHONE'o IIPO 68 I ~ 667

II

>J

~p1 UTlOy 6~

Z 0

TENNESSEE VALLEY AUTHORITY O m CHATTANOOGA. TENNESSEE 37401 b

'~)S 19'~

November ll, 1976 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 2 >>

DOCKET NO. 50-260 . FACILITY OPERATING LICENSE DPR-'52 REPORTABLE OCCURRENCE REPORT BFRO-50-260/7615 The enclosed report is to provide details concerning the unit 2 offgas post-treatment monitor (2-RM-90-265) suction and discharge sample lines that were found< to be reversed during startup testing. This report is submitted in accordance with Browns Ferry Technical Specifications Section 6. This event occurred on Browns Ferry Nuclear Plant unit 2.

Very truly yours, TENNESSEE VALLEY AUTHORITY 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 Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, D.C. 20555 go -ZS 0 Art Equal Opportunity Empioyer

4 rt N

4" '4 IJ t

4 4

)i{

4 fj

'tl()(

I p(jjt

• . (

-4 I ( JIJ(44 J4

-Ir

~

'tI," I 4

) )

4 gr f'

r ttjr,t),

II 4 (Jlpr ~4

'4

~

'lj 'J)

JJJ4 (

Ct Ijtttr(

tlj'. ( '

~,'jl0'":9 ()( I'4 "1'i), ()( Xf)lt) f>'r') jh'))(' ',J j t>5 4( ')

g g,

'l 0'4$ t)(

(()( ig4

rjf't tj

'J 4

r,(JI QI

')'z'(

I a=re*'()('

r))gtl'4))44)gt J f r)['I, r- -(4 R',, rt -

()Q i jf(gg 4I ~ 4 Jt( ~ yr)r ~ ~

Vr))tp r" 4 IJ' J i "'J'gt [Itt),4+'ttj.)rt(JI Q(tl " p (.jJ I I I

~ I ,J) I y f p)1.

~ r ~

(

,, fl ~ J r'

44 ~

I

>>',') (4> (Ij,,)fj(rl ( rs <<',) <<,':, I Jt rl"l)(r r 4 I, J) J tj 44 Jfj P(( ~

(4 tr(P 4) ~ )

~ II. ~

~,

LlCENSEE EVENT REPORT CONTROL BLOCK: fPLEASE NT ALL REQUIRED INFOAIVIATION)

L!CENSEE LICENSE EVENT NAME LCENSE NUMBER TYPE TYPE T~] A L B R F 2 0 0 0 0 0 0 0 0 0 4 1 1 1 1 ~o 89 14 15 25 26 30 31 32 REPORT REPORT CATEGORY DOCKET 'NUMBER EVENT DATE REPORT DATE

~03 OON'T 7 8

~l 57 58 TYPE L

59 SOURCE

~L 60 61 0 5 0 0 2 68 LiLa.~l 69 74 75 EVENT OESCRIPTION 7

Qo I 8 9 Durin startu testin the unit 2 off as ost-treatment monitor 2-RN-9 -26 80

[QQ3) and discharge sample lines were found to be reversed". Since startup the monitor has I

7 89 80

~os been indicating the activity upstream of the charcoal beds rather than downstream~

8 9 BO BFRO-50-260i'7615 7 8 9 7 8 9 PRME SYSTEM CAUSE COMPONENT COMPONENT CODE CODE COMPONENT CODE SLUcPUER MANUFACTURER

[007j ~B3 A 2 N 5 T R U

'3 Z 9 9 9 N 7 8 9 10 'l1 12 17 44 47 48 CAUSE OESCRIPTION toas] Installation error.

7 8 9

'~os 7 8 9 80 89 FACIUTY METHOD OF STATUS '6 POWER OTHER STATUS DISCOVERY DISCOVERY DESCRIPTION Jig 9 B ~05 P NA 0 Lonusual Monitor Res ense No ed 7 8 10 12 13 44 45 46 s 80 FORM OF I ACTIVITY CONTENT RELEASEO OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE Z Z NA NA 7 8 9 10 11 44 45 60

~ PERSONNEL E:<POSURES NUMBER TYPE DESCRIPTION

~OO O ~2 NA 7 8 9 12 13 80 PERSONNEL INJURIES NUMBER DESCRIPTION

~0' 0 NA I

7 8 9 11 12 , 80 OFFSITE CONSEQUENCES NA Jig 7 89 80 LOSS OR OAMAGE TO FACILITY TYPE OESCR!PTION

~16 Z 7 89 10 80 PUBLICITY 7 89 80 ADDITIONAL FACTORS QB Installation of similar lines on units 1 and 3 has been verified correct.

/ 89 7 89 NAME'

/ 1 PHOI'IE'PO 8!I I ~ 6 67

(g

.r j