ML19259B429

LER 79-002/03L-0 on 790107:reactor Bldg Vent Monitor Was Removed from Svc to Investigate Low Flow Condition.For About 2-h Personnel Cleaned & Readjusted Dirty Controller.Alarm Sys Is Adequate to Detect Problems of This Nature

ML19259B429
Person / Time
Site:	Pilgrim
Issue date:	02/06/1979
From:	Mathis C BOSTON EDISON CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19259B427	List: ML19259B426 ML19259B429
References
LER-79-002-03L, LER-79-2-3L, NUDOCS 7902090315
Download: ML19259B429 (1)

Text

LICENSEE EVENT REPORT

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6 (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)

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NUMBLR I .B 0') EVENT DATE 14 15 REPORT DAT E EVENT DESCRIPTION AND PROBARLE CONSEQUENCES h o 7 l On January 7, 1979 the Reactor Building Vent Monitor (RBV) was removed from l g  ; ; service to investigate a low flow condition. The monitor was out of service l

o , l for approximately two hours while I&C personnel cleaned and djt$.,Ced the con j j o ; ,, ; ; troller. A controlled shutdown was initiated as required after the monitor was l

0 e ! INOP for one hour and terminated when the monitor was returned to service. Public l O 7 l Health and safety were not affected by this event. l 0 a l 7 8 9 80 C DE CODE SUBC E COP /PONENT CODE S t, B C D'E Si DE 7

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_ SEQUE NTI AL OCCURRENCE REFORT 60 VISION LER RO EVENT YEAR Re. 07T NO. CODE TYPE No.

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CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h i

o [ This event was caused by a dirty controller which was cleaned and re-adjusted.  ;

ggj The existing alarm syste , is adequate to detect problems of this nature, i gg therefore, no future action is contemplated, g I ' l:1, l li l41 l l 7 8 9 80 STA S  % POWER OTHEP STATUS DISCO RY DISCOVERY DESCRIPTION 1 5 l E l@ l1 l0l0l@l N.A. l lAl@l Operational Event l ACTIVITY CO TENT RELE ASED OF RELE ASE AMOUNT OF ACTIVITY LOCATION OF AELEASE 1 c W @ lZ l@l N.A. l l N.A. l 7 8 9 to 11 44 45 80 PERSONNEL EXPOSURES NUYRE R TYPE CESCRIPTION i 7 l0l0l0l@lZ @l' N.A. l PE R SON N d'IN;u'n',E S 8 NU MH DESCniPTION li In l l U I N.A.

7 8 9 I U @l 11 12 80 LOSS OF OH DAMAGE TO FACilliY TYFE OL SCHIPT ION

[TTil8 I9 Z l@l N.A. l 7 10 80 issu ETCHIPTION

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NAME OF PREPARER Chnw J . N th I 9 PHONE:

INTERIM REPORT Accession No.1 Contract Program or Projer

Title:

Water Reactor Safety Research Subject of this Document:

Papers presented at 6th WRSR Information Meeting, Nov. 6-9, 1978.

Meeting agenda attached.

Type of Document:

Papers presented at 6th Water Reactor Safety Research Information Meeting, November 6-9, 1978 at the National Bureau of Standards Author (s):

See agenda i .'.e of De ume.st:

November 6-9, 1978 Responsible NRC Individual and NRC Office or Division:

Stanley A. Szawlewicz, Division of Reactor Safety Research

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This document was prepared primarily for prelimin:ry or internal use. lt has not received full review and approval. Since there may be substantive changes, this document should not be considered final.

s Prepared for U.S. Nuclear Regulatory Commission Washington, D.C. 20555 INTERIM REPORT 8