ML18283B339

Licensee Event Report Concerning Excessive Drywell Floor Drain Leak Rate Observed During Normal Operation

ML18283B339
Person / Time
Site:	Browns Ferry
Issue date:	07/25/1978
From:	Fox H Tennessee Valley Authority
To:	O'Reilly J NRC/IE
References
Download: ML18283B339 (6)

Text

REGULATORY INFORMATION DISTRIBUTION SYSTEM (AIDS)

DISTRIBUTION FOR INCOMING MATERIAL 50-296 REC:

OREILLY J P

NRC ORG:

FOX k< S TN VALLEY AUTH DOCDATE: 07/25/78 DATE RCVD: 07/28. 7G DOCTYPE:

LETTER NOTARIZED:

NO COPIES RECEIVED

SUBJECT:

LTR 1

ENCL 1

FORWARDING LICENSEE EVENT REPT (RO 50-296/78-019)

ON 07/07/78 CONCERNING EXCESSIVE DRYWELL FLOOR DRAIN LEAK RATE OBSERVED'AUSED BY PARTIALLY BROKEN WELD ON 1-INCH SOCKET WELD FITTING ON INSTRUMENT SENSING LINE ON A JET,, PUMP RISER.

PLANT NAME: BROWNS FERRY, UNIT 3 REVIEWER INITIAL:

X JM'ISTRIBUTOR INITIAL:g~

+4++~++4t>+4k++4+++ DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS 1NCIDENT'REPORTS

( DISTRIBUTION CODE A002)

FOR ACTION:

INTERNAL:

EXTERNAL:

BR CH ORBQ3 BC44W/4 LNCL EG Fll E4

/ENCL

/2 ENCL I

8c C SYSTEMS BR4+W/ENCL NOVAK/CHECK~~W/ENCL AD FOR ENG+%W/ENCL HANAUER+4W/ENCL AD FOR SYS 8( PROJ~+W/ENCL ENG1NEERING BR+wW/ENCL KREGERlJ.

COLLINS++W/ENCL K SEYFR IT/IE++W/ENCL LPDR S ATHENS>

AL44W/ENCL TICt LIZ CARTa R++W/ENCL NSIC4 4 W/ENCL ACRS CAT B+>W/ih ENCL NRC PDR4<W/ENCL MIPC++W/3 ENCL EMERGENCY PLAN BR+<W/ENCL EEB~~W/ENCL PLANT SYSTEMS BR+<W/ENCL AD FOR PLANT SYSTEMS+>W/ENCL REACTOR SAFETY BR<<W/ENCL VOLLMER/BUNCH>~W/ENCL POWER SYS BR%4W/ENCL DISTRIBUTION:

LTR 45 ENCL 45 CONTROL NBR:

782140087 SIZE:

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THE END

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July 2y, 1978 0

TENNESSEE VALLEYAUTHORITY CHATTANOOGA. TENNESSEE 37401 Ih. James P. O'Reilly, Director U.S. Euclear Regulatory Cenmission Office of Xnspection and Enforcement Region XX 101 Marietta Street, Suite 3100 Atlanta~ Georgia 30303

Dear Ih'. O'Reilly:

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9MRBSHE VALLEYAUTHORXTY BROWS PERRY MJCLEQt PZAtIT KGS3 lOCKET I<0. 50-296 - PACXLXTY OPlRATXH'6 XXCEHSE DPR-68 <<EPORGKZ OCCURRENT

'EPORT BFR0<<50-29%819 The enclosed report prcnrLdes details concerning an excessive dryvell f3.oor drain leaIt: rate Mich ~ras obscured by the operator during nprdn1 operation.

This report is submitted in accordance srlth Brims Perry unit 3 tcchnical specification 6.7.2.a.(2).

Very truly yours, TZSESSEEl VAXZZYAUTHORXTY ge ST FNC Director of Power Production Enclosure (3) cc (Enclosure):

. Director (3)

Office of Ifanagement Xnformation ancL Pro am Control U.S. Nuclear Regulatory Commission IIashington, D.C.

20m Director (40)

Office of Xnspection and, Enforcement U.S. Kuclear ReyQatory CommiSsion Vashingtona D.C 20m 782gqP()g7 An Equal Opportunity Employer

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U. S. NUCLEAR REGULATORY COMMISSION NRC FORM 366 (7.77)

CONTROL BLOCK:

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8 9

LICENSEE CODE 14 15 CON'T KK soURcE LLJOG 0

5 0

0 0

2 6

O7 0

0 0'072 57809 7

8 60 01 DOCKET NUMBER 68 69 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES 010

~02 Durin normal o rat ion excessive dr ell floor drain eak ra e s

bs LICENSE E EV EN T R EPORT OI

{PLEASE PRINT OR TYPE ALLREQUIRED INFORMATION) 0 0

0 0

0 0

0 Qs t 1

1 1

ps~ps LICENSE NUMBER

~ 25 26 LICENSE TYPE'0 57 CAT 58 EVENT DATE

~o,f 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> T.S. time limit T.S.3.6.C.3 There was no effect on the pub ic he

~o3 operator (T, S ~ 3 ~ 6. C. 1).

The react or was manuall laced in c O1d shutdown within the

~o5

safety,

. Redundant systems were available had. the instrumentat ion become inoperable

~OG The leaka e did not 'affect connected.

instrumentation

~O

~OB 7

8 7,8 9

SYSTEM CAUSE CAUSE COMP.

VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE

[gag'CB Q11 N Q12

~B Q>s P

1 P

B X

X Qis

~A Q>

~Z Qs, 9

10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION LEB/RO EVENT YEAR REPORT NO.

CODE TYPE NO.

Qll ss~os7

[778 J ~

~01 9

~w

~01

~1'

~0 21 22 23 24 26 27 28 29 30 31 ACTION. FUTURE EFFECT SHUTDOWN ATTACHMENT NPRDR PRIME COhIP.

COMPONENT TAKEN ACTION ON PLANT METHOD HOURS 022 SUBhIITTED FORhf SUB.

SUPPLIER MANUFACTURER

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X 33 34

~ 35 36 37 40 41 42, 43 44 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS 27 o

A rtiall broken weld. on a 1-inch s e

we t7 80 p>>

on a et ump riser was the cause of h

steel pi e ressurized to reactor ressure.

The line was rewelded and. the unit re-turned. to service.

Other sensin lines of a similar confi uration ~are inspected to revent recurrence.

Desi n evaluation of the roblem has been re uested 7

8 9

FACILITY STATUS

% POWER OTHER STATUS 1

5 E

28 1

Q Q

29 CO Q ~P ACTIVITY CONTENT RELEASED OF RELEASE AMOUNTOF ACTIVITY Z

Q>>

LZJps<

N A 7

8 9

10 44

'ERSONNEL EXPOSURES NUhlBER TYPE DESCRIPTION 7 ~00 0Jps7 Z

Qss N A 7

8 9

11 12 13 PERSONNEL INJURIES NUMBER DESCBIPTIONO41

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Qe MA I IETHOO OF DISCOVERY DISCOVERY DESCRIPTION

~Apel 0 orator Observation 45 46 LOCATIONOF RELEASE 45 80 80 80 r

80 7

8 9.

11 12 LOSS OF OR DAMAGETO FACILITY 43 TYPE DESCRIPTION L

p4s No dame e - Nemoorar use of unit uas lost.

7 8

o 9

10 P U8 L IC ITY ISSUED DESCRIPTION~

~NO44 N A 8

9 10 NAME OF PREPARER 68 69 PHONE:

NRC USE ONLY 80 g

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