ML18024A638

LER 78-034/03L-0 on 781216:during Normal Operation,The Relief Valve on Discharge of Standby Liquid Control Pump 3A PCV-63-512 Was Observed to Open at Wrong Set Pressure. Caused by Maladjustment of Crosby 1X2 Style Jm Wk Valve

ML18024A638
Person / Time
Site:	Browns Ferry
Issue date:	01/12/1979
From:	Krause L TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML18024A637	List: ML18024A635 ML18024A638
References
LER-78-034-03L, LER-78-34-3L, NUDOCS 7901170223
Download: ML18024A638 (4)

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~,366 U. S. NUCLEAR REGULATORY COMMISSION LICENSEE EVE NT REPORT

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,Q {PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)

[oO~J AJ L 0 R F 3 Q2 0 0 - 0 0 0 0 - 0 0 Qsd I I I I Q4~ps LICENSEE CODE 14 15 LICENSE NUMBER 26 LICENSE TYPE 30 57 CAT CON'T KEI 7 8 soURcE MQ60-GO GI 5 0 0 0 DOCKET NUMBER 2 9 6 68 Q71 69 2 1 EVENT DATE 6 8 74 Qs 0

/5 1 1 2 7 9 Qs REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES QIO During normal power operation, while erformin SI 4.4.Ael the relief valve on the discharge of standby liquid control pump 3A, PCV-63-512, was observed to open at ocz

~os 3.4.5A. I. The redundant component, SIC pump 3E was dem'one traced to be operable

~ps immedi ately. There was no hazard to the public heal th or safety. Previous occurrences: 296/7701, 296/7708, 296/7713 ~

~os 7 8 9 80 SYSTEM CAUSE CAUSE COVIP CODE CODE SUBCODE VALVE COMPONENT CODE SUBCOOE " SUBCODE

[os) 7 8

~SH 9 10 Q11 'E pie LBJ Qio V A L V E X O4 ~X Q15 ~B Qis 11 12 13 18 ~

19 20 SEQUENTIAL OCCURRFNCE

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REPORT REVISION LERIBO EVENT YEAR REPORT NO.

Q17 iisiosT ~78 21 22 23

~03 24 A

26

~m 27

~03 28 CODE 29 TYPE

~L 30 NO.

~0 31 32 ACTION FUTURE EFFECT SHUTDOIVN ATTACHEIENT NPRD.4 PRIME COEIP, TAKEN ACTION ON PLANT hIETHOD COIUIPONENT HOURS Q22 SUBhIITTED FOBh1 SUB. SUPPLIFR hIANUFACTUBER

~Zpis LZJQ>> ~ZQo ~Zpsi 0 0 0 0 Y Q>> ~NQ54 MNQ>> 0 7 1 0 Q>>

33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS 27 p The relief valve, a Crosby Valve and Gage Co. 1 Z 2 st le JH LK valve was ad 'usted 1:o the proper set pressure. It was retested and met surveillance testin re uire~

ments. Relief valve setting changes during normal operation without mechanical 3 fai lure have been random and in freque'nt ~ No recurrence control action is appropriate.

4 7

80 ILIETHOD OF

'4 PO'IVER OTHER STATUS DISCOVERY DISCOVERY DESCRIPTION

~15 E P>> ~O~ O P>> NA ~apsi Surveillance Testin

~

8 9 10 12 13 44 45 4G ACTIVITY CONTENT 80 RELEASEO OF REI.EASE AMOUNT OF ACTIVITY LOCATION OF RELEASE 5 ~Z Qso ~ZQ54 NA NA 7 6 9 10 11 44 45 PERSONNEL EXPOSURES 80 NUMBER TYPE DESCRIPTION

~OO OJpop ~iQss NA 7 8 9 11 12 13 PERSONNEL INJURIES 80 NUMBER DESCRIPTION 41 5 ~OO 0 Qso 7 8 9 11 12 LOSS OF OR OAhIAOE TO FACILITY 80 TYPE DESCRIPTION z Q47 NA 7 8 9 10 PUB L I CITY 80 ISSUEI) DESCRIPTION NRC USE ONLY o ~wpi NA I

GiB 69 80 g

'9o>>image>,. L. L. Krause PHOI'IE 100/106 0 L

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Form BF-17 v

BF 15.2 6/09/V8 C+

LER SUPPLEMENTAL INFORfIIATION BFRO 296 / 7834 'echnical Specification Involved 3.4.A. 1 Reported Under Technical Specification 6.7.2.6.2 Date of Occurrence 12/16/78 Time of Occurrence 1100 Unit Identification and Descri tion of Occurrence:

During normal power operation, while performing surveillance test 4.4.A.1 the relief valve on the discharge of standby liquid control pump 3A, 7CV-63-512, was observed to open at 1,150 psig vice the design setting of 1,425 + 75 psig required by T.S. 3.4.A.l.

Conditions Prior to Occurrence:

Unit operating at 70~ercent power; Action specified in the Technical Specification Surveillance Requirements met due to ino erable e ui ment. Describe.

Redundant components were demonstrated operable immediately in accordance with T.S. 4.4.B.l.

A arent Cause of Occurrence:

Xnservice drift of relief valve setting.

8 I

Anal sis of Occurrence:

Operation of the relief valve, a Crosby Valve and 'Cage Co. 1 X 2 style JM KC valve, was satisfactory subsequent to adjustment with no evidence of mechanical fai.lure.

Corrective Action:

The set point aG relief valve PCV-63-512 was adjusteg and S.I. 4.4.A.1 was satisfactorily performed.

Failure Data: BFRO-50-296/7701 BFRO-50-296/7708 BFRO-50-296/7713 Tennessee Valley Authority - Browns Ferry Nuclear Plant

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