ML18024A628

LER 78-023/03L-0 on 781211:reactor High Pressure Switches Ps-3-204A&B Exceeded Tech Spec Limits When Static-O-Ring 9N-AA45-(x9)-TT Pressure Switch Drifted Out of Tolerance

ML18024A628
Person / Time
Site:	Browns Ferry
Issue date:	01/04/1979
From:	TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML18024A627	List: ML18024A626 ML18024A628
References
LER-78-023-03L, LER-78-23-3L, NUDOCS 7901120141
Download: ML18024A628 (4)

Text

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NRC FORM 36, ('II U. S. NUCLEAR REGULATORY COMMISSION

'r ICENSEE EVENT REPORT

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~ I CONTROL BLOCK I ,Q (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)

~01 7 8 LICENSEE CODE 14 Q2 0 p p p p I.ICENSE NUMBER p p p 25 Q>A 26 2 2 LICENSE TYPE 2 2 JO Q(~Q<

57 CAT 58 CON'T

~01 soURGE LLJQB 0 5 0 0 0 2 6 0 7 1 2 1 1 7 8 74 6

'15 0 1 0 4 Q9 7 8 60 61 DOCKET NUMBER 68 69 EVENT DATE REPORT DATE 80 EVENT DESCRIPTION AND PROBABlE CONSEQUENCES QIO Durin normal o eration while erformin surveillance testin reactor hi h essure

~03 switches PS-3-204A and B exceeded the T. S. limits s ecif ied in table 3. 2. B. Redundant switches were operable and in tolerance. There was no hazard to the ublic health or safety. (See reversed page.)

~06

~OB 7 8 9 80 SYSTEM CAUSE CAUSE COMP. VAI.VE CODE CODE SUBCOOE COMPONENT CODE SUBCODE SUBCODE

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~09 ~XA Q(( x Q(2 ~z Q(3 I N 8 T 8 0 O(4 ~NO(z ~z 0" 7 8 9 10 11 12 13 18 19 20 SEOUENTIAL OCCURRENCE'EPORT REVISION LEAIAO EVENT YEAR REPORT NO. CODE TYPE NO.

Q(( REPOIIT ~78 Q ~02 3 +r ~03 +L Q Qp ACTION FUTURE TAKEN ACTION LJSR(S MS EBS 33 34 21 22 EFFECT ON PLANT 35 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 23

'6 SHUTDOWN METHOD 24 31 26 HOUAS +22 27 40 28 ATTACHMENT "S

SUBMITTED 41 29 NPRDP LJS LJS '

FORM SUB.

42 30 PRIME COMP.

SUPPLIFA 43 31 44 32 COMPONENT

'S MANUFACTURER 47 0 The Static-0-Ring 9N-AA45- (X9)-TT pressure switch drifted out of tolerance. The swi-tch was inspected, recalibrated8 and functionally tested for repeatability. Since thi is the first problem identified with the instrument, no recurrence control action is planned 4

7 8 9 Q

~Os FACILITY METHOD OF STAruS  % POWER OTHER STATUS DISCOVEAY DISCOVERY DESCAIPTION Q32 EK 8 9 E 88 10 0 7 3 12 13 NA 44 45 Q31 Surveillance testing 80 ACTIVITY CONTENT RELEASEO OF RELEASE AMOUNTOF ACTIVITYQ36 LOCATION OF RELEASE Q36

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Q33 10 Z

Q NA 44 45 NA 80 PERSONNEL EXPOSURES NUI.'IBEA TYPE DESCRIPTION Q39 LpppOp '(Qpz

~ROM NA 7 8 9 'I l 12 13 80 PERSONNE'I. INJURIES 1 8 9 11 '12 80 LOSS OF OR "r(t'SOE TO FACILITY ~43 TYPE DESCRIPTION

~ZQ42 i NA 8 9 10 EC

~20 ~Q44 ISSUED pUBLImr =

DESCRIPTION ~ NRC USE ONlY IlllJJJJ (

8 9 10 68 69 0

NAf(4E OF PREPARER PHONE:

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l~ x Form BF-17..4, BF 15.2 6/09/V8 LZR SUPPLZ AL INFORMATIO 7823 BFRO 260 echnical Specification I olved Table 4~ 2~B Reported nder T nical ecification 6-7 2. ~ (~)

Date of ccur ence / ~ ime of Occuy ence l530 Unit Identifi a and Descri tion of 0 urrencK PS-3-20 A and B, reactor high treasure tches, drifted out of the Sec cal speci c'a tion limits.

onditio s Prior to Occurrence:

Unit operating at 73X ppwer.

Action specific in the Technica1 Spe 'cation Surveillan Require ts met due to ino er 1 e ui ment. Descri e.

Repair wit in 24 ho rs or decla the system inope&able.

A ar nt Cause of Occu nce:

Ins rument drift.

nal sis of Occ rrence:

r The trip f tion was operable due t two edundant switches being operable and in tol rance.

rective Action:

The switches were inspected'rec librated, and re rned to service within the specified time limit.

Failure Data:

None Tennessee VaIley Authority - Brovms Ferry Nuclear Plant 0

Form BF-17 ..

BF 15,2 6/09/7S LER SUPPLZMENTAL INFORMATION BFRO 260 / 7823 Technical Specification Involved Table 4~ 2~ B Reported Under Technical Specification 6~ 7 2-b.{~)

Date of Occurrence /11/ 8 Time of Occurrence Unit 2 Identification and Descri tion of Occurrence:

PS-3-204A and B, reactor high ygessure switches, drifted out of the technical specification limits.

0 Conditions Prior to Occurrence:

Unit operating at 73X ppwer.

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

Repair within 24 hours or declare the system inopetable.

A arent Cause of Occurrence:

Instrument drift.

Anal sis of Occurrence:

A The trip function was .operable 'due to two redundant switches being operable and in tolerance.

8 Corrective Action:

The switches were inspected, recalibrated,and returned to service within the specified time limit.

Failure Data:

None Tennessee VaQey Authority - Brown Ferry Nuclear Plant