05000293/LER-1979-002-03, /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

/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: 05000293/LER-1979-002, Forwards LER 79-002/03L-0 05000293/LER-1979-002-03, /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
References
LER-79-002-03L, LER-79-2-3L, NUDOCS 7902090315
Download: ML19259B429 (1)

LER-1979-002, /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

Event date:
Report date:
2931979002R03 - NRC Website

text

LICENSEE EVENT REPORT

- COrnnol BLOCK-l l

l l

l l

l@

(PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 1 6

%p lMlAlPlPlSl1 0 l0 l0 0 l0 [0 l0 l0 0 l 0 l 0 lgj f ljl1l1ltlgl l

[Q 7

8 9 LICLNSE E CODE 14 15 LICENSL NUMutH 26 26 LICLNSE TYPE JO S1 CAT 58 CON'T

$"C[

Ll@l0 5 l0 l-l0 l 2 9 l 3 l@l 0 1 l o l 7 l 7 l 9 l@ 0 l 2 l 0 l 6 l 7 l 9 @

0 1

7 8

60 61 DOCKET NUMBLR I.B 0')

EVENT DATE 14 15 REPORT DAT E 80 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 troller. A controlled shutdown was initiated as required after the monitor was l

j o ;,, ; ;

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

'lMjC @ y@

E l@ l I Nl Sl Tl Rl Ul@ l Cl@ l Zl@

o 9 7

8 9

10 11 12 13 18 19 20 SEQUE NTI AL OCCURRENCE REFORT 60 VISION LER RO EVENT YEAR Re. 07T NO.

CODE TYPE No.

@ REP l7 l 9l l_

l0 l0 l2 l l/

l 0l 3l lLl l_l g

_ 26 22 23 04 26 27 28 29 30 31 J2 KEN ACT ON O PLA T Ti HOURS S R I D

FOR UB.

S PLIE MAN T RER l

l@l l@

l Z l@

lE l@

l0 l0 l 0l 0l lN lg lN lg lN [g jB l4 l4 l5 lg 33 34 35 36 3/

40 41 42 43 44 47 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 l E l@ l1 l0l0l@l N.A.

l lAl@l Operational Event l

1 5

ACTIVITY CO TENT RELE ASED OF RELE ASE AMOUNT OF ACTIVITY LOCATION OF AELEASE W @ lZ l@l N.A.

l l

N.A.

l 1 c 7

8 9 to 11 44 45 80 PERSONNEL EXPOSURES NUYRE R TYPE CESCRIPTION l0l0l0l@lZ @l N.A.

l i 7 PE R SON N d'IN;u'n',E S 8

NU MH DESCniPTION li In l l U I I U @l N.A.

7 8 9 11 12 80 LOSS OF OH DAMAGE TO FACilliY TYFE OL SCHIPT ION [TTil I Z l@l N.A.

l 7

8 9 10 80 issu ETCHIPTION lllll lll 2 O 4

7 8 9 to bu 69 80 &

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

- s

~

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