ML18024A789

LER 79-004/03L-0 on 790414:reactor Bldg,Turbine Bldg & Refueling Zone Vent Exhaust Monitor RM-90-250 Failed Surveillance Test SI 4.8.B-4.3,Section 4e.Caused by Failure of Input Card for Radiation Monitor

ML18024A789
Person / Time
Site:	Browns Ferry
Issue date:	05/07/1979
From:	TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
LER-79-004-03L-02, LER-79-4-3L-2, NUDOCS 7905110318
Download: ML18024A789 (2)

Text

'NRC IA)RM 366 UCLEAR REGULATORY COMMISSION (7477 >

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CONTROL BLOCK: Qi {PLEASE PRINT OR TYPE ALL REQUIRED INFORMATIONI

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~01 7 8 9 A L B LICENSEE CODE R F 2Q, 14 15 p p p LICENSE NUMBER 0 0 0 0 25 Q3 26 4 1 LICENSE TYPE 1 1 30 Q4~ 57 CAT 58 QS CON'T

~01 ~LQB 0 5 p p p 2 6 0 7 0 4 1 4 7 9 8 0 5. 0 7 7 9JQ9 7 8 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION ANO'PROBABLE CONSEQUENCES QIO

~oz Durin normal operation, Reactor Building, Turbine Building and Refueling zone vent exhaus t monitor RM-90-250 failed surveil lance test SI 4. 8. B-4. 3, section 4p. There is no redundant system. Samples were taken and analyzed until monitor was returned to l service. There was no hazard.to the public health or safety. No previous occurrence

~06

~07

~08 80 SYSTEM CODE CAUSE 'AUSE SUBCODE COMPONENTCODE COMP. VAI.VE CODE SUBCODE SUBCODE

~09 ~SC Q>> E Q77 ~PQ77 1 N 0 T R 0 Q74 ~EQ74 ~E Q74 7 8 9 10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION Q>>

LERIRO 77>>>>

ACTION FUTURE EVENT YEAR L779J 21 22 EFFECT

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23 SHUTDOWN

~00 24 REPORT NO.

4 26

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27

~03 28 ATTACHMENT CODE 29 NPRD 4 TYPE

~L 30 PRIME COMP.

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31

'~0 NO.

COMPONENT TAKEN ACTION ON PLANT METHOD HOURS O22 SUBMITTED FORM SUB. SUPPLIER MANUFACTURER

~AQIB 33

~ZG9 34

~ZQ20 35

~ZQ21 36 37 0 0 0 0 40 PJ 41 Q23 ~Q24 42 PJ 43 Q25 44 47 Q28 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 o In ut card for the Nuclear Measurement Cor oration Model 1C-13G radiation monitor failed. A re lacement in ut card was installed, calibrated, functionall teste and returned to service. This is not a generic failure and no further action is indicated 7 8 9 80 FACILITY METHOD OF I 5 STATUS EQ 28 ACTIVITY CONTENT LiiJQ% POWER 0 0 29 OTHER STATUS Q30 NA D IS COY ER Y

~B 45 Q31 46 Surveillance Testing DISCOVERY DESCRIPTION Q32 80 RELEASED OF REI.EASE Z

AMOUNT OF ACTIVITY Q LOCATION OF RELEASE Q Q33 ~ZQ34 7 8 9 10 11 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION Q39 7 ~00 0 Q77 ~ZQ74 NA

~Q 7 8 9 11 12 13 PERSONNEL INJURIES NUMBER DESCRIPTION 4i EKI 7 8 9 11 12 80 LOSS OF OR DAMAGE To FACILITY TYPE DESCRIPTION Q43

~19 ~ZQ42 NA 7 8 9 10 80 P V8 L I C ITY

~20 ISSUED

~NQ44 DESCRIPTION Q NA

~9o5l~ 03/ d NRC USE ONLY 74 a

7 8 9 10 68 69 80 g 0

NAME OF PREPARER PHONE: a 0

Form BF-1V BF 15,2 6/09/78 LER SUPPLEMENTAL INFORMATION BFRO 260 / 794 Technical Specification Involved Reported Under Technical Specification 6.7.2.b a 5.6.

Date of Occurrence 4-l4-79 Time of Occurrence 2l00 Unit Identification and Descri tion of Occurrence:

CAN 2-RM-90-250 failed S'L 4.8.B.4-3 section 4.e.

Conditions Prior to Occurrence:

Unit operating normally at 1090 NW, CAM functioning normally.

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

Chem Lab notified to begin sampling by alternate means.

A arent Cause of Occurrence:

Component failure.

Anal sis of Occurrence:

None.

Corrective Action:

Replaced input card, performed calibration and FT on 2-RM-90-250.

Failure Data:

None Tennessee Valley Authority - Browns Ferry Nuclear Plant