05000296/LER-1979-007-03, /03L-0 on 790612:during Performance of Procedure SI 4.1.A-14,turbine First Stage Permissive Pressure Switches PS-1-81A & B & PS-1-91A & B Setpoints Exceeded Tech Specs. Caused by Setpoint Drift.Switches Recalibr

/03L-0 on 790612:during Performance of Procedure SI 4.1.A-14,turbine First Stage Permissive Pressure Switches PS-1-81A & B & PS-1-91A & B Setpoints Exceeded Tech Specs. Caused by Setpoint Drift.Switches Recalibr

ML18024A900
Person / Time
Site:	Browns Ferry
Issue date:	07/11/1979
From:	TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML18024A899	List: 05000296/LER-1979-007, Forwards LER 79-007/03L-0 05000296/LER-1979-007-03, /03L-0 on 790612:during Performance of Procedure SI 4.1.A-14,turbine First Stage Permissive Pressure Switches PS-1-81A & B & PS-1-91A & B Setpoints Exceeded Tech Specs. Caused by Setpoint Drift.Switches Recalibr
References
LER-79-007-03L-02, LER-79-7-3L-2, NUDOCS 7907170205
Download: ML18024A900 (4)

LER-1979-007, /03L-0 on 790612:during Performance of Procedure SI 4.1.A-14,turbine First Stage Permissive Pressure Switches PS-1-81A & B & PS-1-91A & B Setpoints Exceeded Tech Specs. Caused by Setpoint Drift.Switches Recalibr

Event date:
Report date:
2961979007R03 - NRC Website

text

NRC RORM 366 (7.77)

LICENSEE EVENT REPORT UCLEAR REGULATORY COMMISSION

~01 7

8 CON'T

~01 7

8

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LICENSEE CODE 14 15 (PLEASE PRINT OR TYPE ALLREQUIRED INFORMATION)

CONTROL BLOCK 0

0 25 26 LICENSE TYPE 30 57 CAT 58 4 ~QE LICENSE NUMBER REPORT 7

SOURCE 60 61 DOCKET NUMBER 68 EVENT DESCRIPTION AND PROBABI.E CONSEQUENCES 010 Dux'in normal o eration while erformin SI 4.1.A-14 Turbine First Sta e Permissive 0

6 1

2 7

9 B

69 EVENT DATE 74 75 REPORT DATE 80 pressure switches PS-1-.81A

& B and PS-1<<91A

& B set oints exceeded T.

S ~ Table 4

3.1.A limit of 154 sig.

A reactor txi would have occurred from a turbine tri with xeactox power greater than 31,3 pex3cent.

4

Previous occurrences

50-259/7816, 50-260/

6 791$ and 50-259/'798 'here was no hazard to the ublic health or safet There are

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no redundant

channels,

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Tennessee Valley Authority Browns Ferry Nuclear Plant LER SUPPLEMENTAL INFORMATION Form BF-17 BF 15.2 1/10/79 BFRO 296 / 797 Technical Specification Involved Table 3.1.A Reported Under Technical Specification 6.7;2.b.2 Date of Occurrence 6-12-79 Time of Occurrence 0930 Unit

~

3 Identification and Descri tion'of Occurrence:

As found setpoints for PS-1-81A and B, PS-1-91A and B

(RPS Turbine First Stage Pressure Permissiva SI 4.1.A-14) exceeded technical specification limit of 4154 psig by 9.5 to 12 psig.

Conditions Prior to Occurrence:

Unit 8 1070 MWe. Steady state.

Action specified in the Technical Specification Surveillance Requirements.

met due to ino erable e u~iment.

Describe.

Setpoints ad)usted to within technical specification limits.

Each instrument channel was satisfactorily functionally tested.

A arent Cause of Occurrence:

Drift of instrument setpoint.

Anal sis of Occurrence:

Presently reviewing setpoint data for all three units, Investigation of cause of setpoint drift continuing.

Corrective Action

Instrument calibration.

Failure Data:

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

• Retention:

eriod - Lifetime; Responsibility - Administrative Supervisor

• Revision:

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