05000325/LER-1981-053, Updated LER 81-053/03L-1:on 810922,during Reactor Startup, Reactor Recirculation Pump 1B Tripped.Caused by Spurious Trip Signal from ATWS Low Water Level Instrument B21-LTM- NO24B-2.Instrument replaced.W/840329 Ltr

Updated LER 81-053/03L-1:on 810922,during Reactor Startup, Reactor Recirculation Pump 1B Tripped.Caused by Spurious Trip Signal from ATWS Low Water Level Instrument B21-LTM- NO24B-2.Instrument replaced.W/840329 Ltr

ML20087N817
Person / Time
Site:	Brunswick
Issue date:	03/29/1984
From:	Dietz C, Pastva M CAROLINA POWER & LIGHT CO.
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
BSEP-84-0869, BSEP-84-869, LER-81-053-03L, LER-81-53-3L, NUDOCS 8404050031
Download: ML20087N817 (2)

LER-2081-053, Updated LER 81-053/03L-1:on 810922,during Reactor Startup, Reactor Recirculation Pump 1B Tripped.Caused by Spurious Trip Signal from ATWS Low Water Level Instrument B21-LTM- NO24B-2.Instrument replaced.W/840329 Ltr

Event date:
Report date:
3252081053R00 - NRC Website

text

U. T T!UCLE AR HLUVEATURTL 88AC F0" W UPDATE REPORT:

% t-LICENSEE EVENT REPORT PREVIOUS REPORT DATE: 10-20-81 (PLEASE PR!iJT OR TYPE ALL REQUIRED INFORMATIONI CONTROL BLOCK: l i

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74 75 REPORT DATE 60 EVENT DESCRIISTION AND PROBABLE CONSEQUENCES h l

2 lDtiring ia reactor s'tartup, IB-reactor recirculation pump tripped concurrent with the o 3 'greceipt of the pump ATWS high. reactor pressure / low level trip annunciator. At the time l p;T 1 P =f th'e event reactor level was. normal and pressure was at 0 psig. Immediately after j gag 3; lthe pump. trip all control rod withdrawal was stopped. This event did. net affect the j

-6 'l health and safety of the public. l l

LR.L7_] I" g o [a l I. Technical Specifications 3.4.1.1, 6.9.1.9b j COYP.

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SYSTEM . CAUSE CALSE VALVE COCE CODE 'SUSCODE COMPONENT COCE $UBCODE SUSCODE TOTil 7 8 I Cl B10 [@. 11lx l@- l Zl@ l 1l NI S I T l R l u l@ lY l@ l20Zl @

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.-lijo(lThe event'is attributed to a spurious trip signal from ATWS low water level instrument ]

[i l 3 l l B21-LTM-N024B-2; however, an evaluation of the subject instrument hv the manu facturer I i 2 1failed to revealany problems. N0243-2, Model No. 510DU216026A010, was replaced and I-s.

gilii ] returned to service. No further action is planned regarding this event. l l

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Brunswick Steam Electric Plant-P..O. Box 10429 Southport, NC 28461-0429 March 29, 1984 FILE: B09-13510C

. SERIAL: -BSEP/84-0869 Mr.. James P. 0'Reilly, Director

U. S.-Nuclear Regulatory Commission Region II, Suite 3100'

'101 Marietta Street N.W.

' Atlanta, GA 30303 BRUNSWICK STEAM ELECTRIC PIANT, UNIT 1 DOCKET NO. 50-325 LICENSE NO. DPR-71 SUPPLEMENT T0' LICENSEE EVENT REPORT 1-81 -

Dear Mr. O'Reilly:

-In accordance with Section 6.9.1.9b of the Technical Specifications for

_ Brunswick Steam Electric--Plant,. Unit 1, the enclosed supplemental Licensee-Event Report._is submitted. The original report fulfilled the requirement for

a. written report within thirty (30) days of a reportable occurrence and both are.in accordance with the format set forth in NUREG-0161, July 1977.

Very truly yours, t

C. R. Dietz, General Manager Brunswick Steam Electric Plant RMP/jih/LETJH1 Enclosure cc: Mr. . R. C; 11eYoung NRC. Document Control Desk k

. OFFICIAL COPY SE21 I t.

. .. - . - _ . .-