05000296/LER-1978-031-01, /01T-0 on 781128:during CRD Scram Timing & Associated LPRM Connect on Verification Noted That All LPRMs Had Been Connected in Reverse Order.Caused by Lack of Explanation in Documents Describing Connection Procedure

/01T-0 on 781128:during CRD Scram Timing & Associated LPRM Connect on Verification Noted That All LPRMs Had Been Connected in Reverse Order.Caused by Lack of Explanation in Documents Describing Connection Procedure

ML18024A588
Person / Time
Site:	Browns Ferry
Issue date:	12/11/1978
From:	TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML18024A586	List: 05000296/LER-1978-031, Forwards LER 78-031/01T-0 05000296/LER-1978-031-01, /01T-0 on 781128:during CRD Scram Timing & Associated LPRM Connect on Verification Noted That All LPRMs Had Been Connected in Reverse Order.Caused by Lack of Explanation in Documents Describing Connection Procedure
References
LER-78-031-01T, LER-78-31-1T, NUDOCS 7812190111
Download: ML18024A588 (3)

LER-1978-031, /01T-0 on 781128:during CRD Scram Timing & Associated LPRM Connect on Verification Noted That All LPRMs Had Been Connected in Reverse Order.Caused by Lack of Explanation in Documents Describing Connection Procedure

Event date:
Report date:
2961978031R01 - NRC Website

text

NRC FORM 366 (7 7X)

U. S. NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT CONTROL BLOCK:

I

,Q (PLEASE PRINT OR TYPE ALLREQUIRED INFORMATION)

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A L

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1 8

9 LICENSEE CODE I.015 0

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1 Q" ~Qs 25 26 LICENSE TYPE JO 57 CAT 58 0

LICENSE NUMBER CON'T

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8 REPORT ~LQB 0

60 61 EVENT DESCRIPTION AND Durin CRD scram 5

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0 2

9 6

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1 2 l l DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 PROBABLE CONSEQUENCES QIO timin and associated P

o eratin at 36 percent power, it was discovered that all the LPRM' had been connected in reverse

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order.

No significant occurrence took place as a result of this event.

No other reac-tors were affected, nor have there been any previous event reports of a similar nature at Browns Ferry.

The consequence of the event was a unit outa e.

There were no ef-fects on public health or safety.

No redundant systems exist.

~DB 7

8 9

80 SYSTEM

CAUSE

CAUSE COMP.

VALVE CODE CODE SUBCODE COMPONENT CODE SVBCODE SUBCODE

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N S

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10 11 12 13 18 19 20 SEOVENTIAL OCCURRENCE REPORT REVISION LERIRO EVENT YEAR REPORT NO.

CODE TYPE NO, Qii esse ii'r ~78

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QO 21 22 23 24 26 27 28 29 30 31 32 ACTION FUTURE EFFECT SHVTOOYIN ATTACHMENT NPROX PRIME COMP.

COL'IPONENT TAKEN ACTION ON PLANT METHOD HOURS +22 SUBMITTED FORM SUB.

SUPPI.IER MANVFACTUREfs

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o QB 33 34 35 36 31 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 The problem was caused by a lack of explanation of ro er LPRM connection rocedures in the document governing the work.

The corrective action was to shut down the uni and properly reconnect the LPRM's.

To prevent recurrence, the ap ro riate rocedures will be clarified and QA hold points will be added.

4 7

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FACILITY STATUS

% POWER OTHER STATUS Q

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Qss DXele Stattas 7

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10 12 I'I 44 ACTIVITY CONTENT RELEASED OF RELEASE AMOUNTOF ACTIVITYQ 6

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10 II 44 PERSONNEL EXPOSURES NUMBER TYPE.

DESCRIPTIONA L0000 JQ33 Z

Q33 NA 7

8 9

11 12

'13 PERSONNEL INJURIES 7

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I I 12 LOSS OF OR DAMAGETo FACILITYQ43 TYPE

DESCRIPTION

Z Q42 NA 7

8 9

10 PUBLICITY 7

8 9

10 NAME OF PREPARER V8121901~l METHOD OF DISCOVERY

~CQ3I 45 46 45 80 80 80 80 80 PHONE'8 69 80 NRC USE ONLY ss 3

80 6 0

DISCOVERY DESCRIPTION Q32 Startup Testing LOCATION OF RELEASE Q

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cform ar-ii BF 15.2 6/09/V8 LER SUPPLEPIENTAL INFORMATION BFRO 296 /

7831 Technical Specification Involved Reported Under Technical Specification 6-7.2.A.6 Date of Occurrence 11/28/78 Time of Occurrence

6. 7. 2.A. 6 Unit 3

Identification and Description of Occurrence:

All LPRM connections were incorrect.

Conditions Prior'o Occurrence:

Stable power operation at 36 percent.

Action specified in the Technical Specification Surveillance Requirements met due to ino erable eauioment.

Describe.

'/A A

arent Cause of Occurrence:

Incorrect hook up of LPRM connectors during refueling outage.

Anal sis of Occurrence:

Occu'rrence was caused by procedural deficiency but problem was detected by test designed to discover such mistakes.

There were no effects on public health or'safety.

'Corrective Action:

Short term:

Shutdown unit and correct'connection.

Long t'erm:

Clarify procedure and add QA hold points.

Failure Data:

None Tennessee Valley Authority - Browne Ferry Nuclear Plant