ML18024A903

LER 79-017/03L-0 on 790615:during Normal Operation,Setpoint on Pressure Switch PS-3-22D Exceeded Specified Limit.Caused by Drift in Model B2T-A12SS Switch.Switch Recalibr & Satisfactorily Tested

ML18024A903
Person / Time
Site:	Browns Ferry
Issue date:	07/12/1979
From:	TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML18024A902	List: ML18024A901 ML18024A903
References
LER-79-017-03L, LER-79-17-3L, NUDOCS 7907180536
Download: ML18024A903 (4)

Text

J-, .,'NRC'FORM 366, U CLEAR REGULATORY COMMISSION TTi777)

LiCENSEE EVENT REPORT CONTROL BLOCK: QI (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)

I 6

~01 7 8 9 A 1 B UCENSEE CODE R 9 2 14 Q80 15 0 - 0 0 0 0 LICENSE NUMBER 0 0 0 25 Q84 26 1 1 1 LICENSE TYPE 1

30 04~0557 CAT 58 CON'T

~O ~LQB 0 5 0 0 0 2 6 0 7 0 6 1 5 7 9 6 0 7 1, 2 7 9 Qg 7 8 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES 010 Durin normal o eration while erformin S7 4.1.A-5 ressure switch PS-3-22D, Reactor High Pressure, setpoint exceeded the setpoint specified in Table 3.1.A of the T. S..

4 Redundant switch PS-3-22B was operable and in tolerance. There was no hazard to the public health or safety. Previous occurrences: 50-259/7816, 50-260/7916, 50-296/797,

~o 6 and 50-259/798.

~OB 7 8 9 80 SYSTEM CAUSE CAUSE COMP. VALVE

~OB 7 . 8 9

~IA CODE 10 0>>

CODE 11 E 0>>

SUBCODE

~E 0>>

12 SEOUENTIAL 13 COMPONENT CODE 18 OCCURRENCE Q14

~ ~

SUBCODE 19 REPORT Q16 SUBCODE 20 Q16 REVISION QTT LF RIRO RRPORT,~79 ACTION FUTURE EVENT YEAR 21 22 EFFECT

~

23 SHUTDO1VN

~0 24 REPORT No.

26 U~ UM CODE ATTACHMENT NPRDA TYPE Lul PRIME COMP.

Ll NO.

LJ COMPONENT TAKEN ACTION ON PLANT METHOD HOURS Q22 SUBMITTED FORM SUB. SUPPLIER MANUFACTURER 33 Q16 ~QIB 34

~Q20 35

~Q21 36 37 0 0 0 0 40

~Y 41 Q23 ~Q24 42

~Q26 43 44 47 Q

CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 o The model B2T-A12SS switch had drifted. The switch was recalibrated and functionall tested satisfactoril . The cause of the instrument drift is still under inves"i a 3

4 7 8 9 FACILITY STATUS 'lI POWER OTHER STATUS Q METHOD OF DISCOVERY DISCOVERY DESCRIPTION Q32

~45 ~E Q28 ~07 7 Q28 NA ~B Q31 Surveillance testing 7 8 9 ~ 10 12 13 44 45 46 80 ACTIVITY CONTENT RELEASEO OF RELEASE AMOUNT OF ACTIVITY Q LOCATION OF RELEASE Q 7 8

~Z 9

Q ~ZQ34 10 11 NA 44 45 NA 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q3g

~00 0 QRT ~ZQRR NA 7 8 9 11 12 13 80 PERSONNEL INJURIES NUMBER DESCRIPTIONQ41

[ii~J ~00 0 048 NA 7 8 9 11 12 80 LOSS OF OR DAMAGE To FACILITY TYPE DESCRIPTION Q43 9 Z Q42 NA 7 8 9 10 80 PU 8 L I C I T Y

~2O ISSUED L~JQ44 DESCRIPTION NA Q NRC USE ONLY 45 4

8 9 10 68 69 80 45 0

NAME OF PREPARER PHONE: L 0

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Tennessee Valley Authority Form BF-1V Browns Ferry Nuclear Plant BF 15.2 1/10/V9

'ER SUPPLEMENTAL INFORMATION BFRO 260 / 7917 Technical Specification Involved Table 3;1.A Reported Under Technical Specification 6.7.2.b.2 Date of Occurrence 6/15/79 Time of Occurrence 0850 Unit 2 Identification and Descri tion of Occurrence:

Reactor high pressure switch PS-3-22D exceeded'etpoint durmng. performance of SI 4.1.A-5.

Conditions Prior to Occurrence:

Steady state oper'ation at approximately 77X power.

Action specified in the Technical Specification Surveillance Requirements met due to ino erable e ui ment. Describe.

NA A arent Cause of Occurrence:

Instrument setpoint drift.

Anal sis of Occurrence:

NA Corrective Action:

Switch was inspected, recalibrated, and functionally tested for repeatability.

Failure Data:

50-259/'7816, 50-260/7916, and 50 259/798.

• Retention: eriod - Lifetime; Responsibility - Administrative Supervisor

• Revision:

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