05000280/LER-1981-022-03, /03L-0:on 810514,amp Reading for Heat Tracing Panel 9,circuit 20C,found Below Acceptance Criteria.Caused by Excessive Heat.Tracing Replaced & Tested.Design Change Initiated: Difference between revisions

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{{Adams
#REDIRECT [[05000280/LER-1981-022-03, /03L-0:on 810703,low Flow Alarm Observed for Process Vent Sys.Caused by Process Blower Motors Out of Svc Due to Valve 1-CM-21 Leaking Through to Vent Piping During Attempt to Drain Mixed Bed Demineralizer 1A for Resin Fill]]
| number = ML18139B388
| issue date = 06/05/1981
| title = /03L-0:on 810514,amp Reading for Heat Tracing Panel 9,circuit 20C,found Below Acceptance Criteria.Caused by Excessive Heat.Tracing Replaced & Tested.Design Change Initiated
| author name = Wilson J
| author affiliation = VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
| addressee name =
| addressee affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
| docket = 05000280, 05000281
| license number =
| contact person =
| document report number = LER-81-022-03L-01, LER-81-22-3L-1, NUDOCS 8106090559
| package number = ML18139B384
| document type = LICENSEE EVENT REPORT (SEE ALSO AO RO), TEXT-SAFETY REPORT
| page count = 3
}}
{{LER
| Title = /03L-0:on 810514,amp Reading for Heat Tracing Panel 9,circuit 20C,found Below Acceptance Criteria.Caused by Excessive Heat.Tracing Replaced & Tested.Design Change Initiated
| Plant =
| Reporting criterion =
| Power level =
| Mode =
| Docket = 05000280
| LER year = 1981
| LER number = 22
| LER revision = 3
| Event date =
| Report date =
| ENS =
| abstract =
}}
 
=text=
{{#Wiki_filter:*
NRC FORM 366
.LICENSEE EVENT REPORT U.S. NUCLEAR REGULA. TORY COMMISSION li-7')
CONTROL BLOCK: '
I',\\
(PLEASE P~INT OR TYPE ALL REOUIREC INFORMATION) l--..... _
............... _..._ __ ---,!6 \\.!.I
~
! V ! A I S I P I SI 2 IQ)l O I OJ S
9 L.ICSNSEE COOE 14 7S
:- I o I 01 01 01 01 -I 01 o 1014 11 J 1 1111101 l I© LICENSE NUMBER 2S.
25 L.ICENSE TYPE JO S7 CAT SS CON"7
~-
7 6
~;~~~~ LI© I o I s l o l o I o I 21 s 1 1 101. o I s 1 1 I 4 I s I 1 l© I o I 6 I o I s Ls I 1 10 60 61 DOCKET NUMBER 6S 69 EVENT DATE 74 7S REPORT OA, =
BO EVENT DESCRIPTION AND PR06ASLE CONSEQUENCES@
I With Unit No. 2 at 100% power, PT-27C revealed* that amn readino for heat tracing
.III!]. J Panel 9, circuit 20C, was below the acceptance criteria stipulated in the PT.
This
([II] I event is contrary to T.S. 3.2.B.5 and is reportable per T.s: 6.6.2.b(2).. ~he [TI)) _I redundant. heat tracing circuit was operable, therefore, the health* and safety of the J..
[£I[] I public were not affected, IITil L.....------------------------------------___..
wIJ 7
B 9
.. rrm 8
SYSTSM CODE
!S IHI@
9 10 C\\ LER/RO LVENT YEAR
\\!..:.J REPORT I 8 I 1 !
NUMBEFI 21 22
 
==CAUSE==
CAUSE CODE SUBCOOE COMPONENT CODE
, El@ liJ@, H, E, A, T, E, R,e 11 12 13 18 SEQUENTIAL OCCURRENCE REPORT NO, cooe I o I 21 21
*I,I Io I 3 I 24 26 27 28 29 COMP.
SUBCOOE W
19 REPORT TYPE lliJ 30 VALVE SUBCOOE w@
20 1:=l 31 BO REVISION NO. w 32 COMPONENT ACTION l'UTURE EF;:ECT
*SHUTOOWN
~ ATTACHMENT NPRc-4 PRIMECOMP.
TAKEN ACTION ON PLANT METHOD HOURS ~ SUBMITTED FORMliUB.
SUPPI.IER MANUl'ACTURER
*-l*T *l l'*Ws.j s !@.
44 47
_*_ LSJfis\\L!.J@)
~'20' W I* o l o I o I o I* t!J@* L!U@). W-33 S!V 34 3S
~ JS 37 40 41 42 43 CAUSE DESCRIPTION ANO CORRECTIVE ACTIONS @
D:I]J j The loss of heat tracing was aue to excessive heat. The defective heat trac;n2 was o:::IIJ replaced and tested.
A design change has been initiated tq change tbe manner by
!III!
which these borated lines are heat traced.
I 1-., _____________ __:._~;:.;;..;;~-------------------
o:TIJ l..l -------------------------------------.-J t!El 8
9 FACILITY
'3Q1 STATUS
% POWER OTHER STATUS \\:::::)
1ITI1 -~@.1 1 I O I O '"""'' __
N.;.../ A ___
8 9
10 1:Z 13
'4 ACTIVITY CONTENT IC\\
RELEASED OF RELEASE AMOUNT OF ACTIVITY ~
[2EI Ll.l@ W@I
, N/A a
9 10 11 7
METHOOOF
. A DISCOVERY OISCO~ERY DESCRIPTION -~
W@I Routine Test.
45 46 N/A
,LOCATIO~ OF RELEASE 80 PERSONNEL EXPOSURES Q
NUMBER t:::;\\ TYPE~ DESCRIPTION ~
!'' EITI J, 0 I O I O lLl.J~I..----* _..;,;N~/A~--------------------"'
a 9 12 1:
so PERSONNEi. INJURIES
~
I\\IUMBER' CESCRll'TION6
. ETIJ _.I O IO IO !@1.-.. _____...;;~.;,:..~/A~-----------------,-~
a s 11 12 110
*,..*...,, *",,.*,.,, '*l:.OSS"OF OR DAMAGE TO FAC:11..ITY t:::'13
.TYPE
 
==DESCRIPTION==
~
: 13}3* L~J@1--. __
r....;.~/_A ____________________
~
*,..
* a s*
10 so PUBLICITY C\\
NRC USE ONLY
.* ISSUEOQ DESCRIPTION~
Im] LEJ~----------~N_/A=--------------
I l I l *l I l I l l I I I !
7 S
9 10.
68 6S 80 ;
~AME OF P=e? ARER _..;:J'=..*;....:L:.:.* _W=i=l-=s=o=n:..... ________ _
(804) 357~3184
~
 
ATTACHMENT 1 SURRY POWER STATION, UNIT No. 2 DOCKET NO:
50-281 REPORT NO:
81-022/03L-0 EVENT DATE:
05-14-81 TITLE OF EVENT:
HEAT TRACING FAILURE
~
: 1.
 
==DESCRIPTION OF EVENT==
With Unit No. 2 at 100% power, PT-27C revealed that the amp reading for heat tracing Panel 9, circuit 20C (".C" BAST recirc. line), was below the acceptance criteria stipulated in the PT.
This event is contrary to Technical Specification 3.2.B.5, and is reportable per Technical Specification 6.6.2.b(2).
: 2.
PROBABLE CONSEQUENCES and STATUS of REDUNDANT EQUIPMENT:
The heat tracing circuits are intended to maintain a fluid temperature above that needed for flow.
The redundant heat tracing.circuit was operable, therefore, the health and safety of the public were not affected.
: 3.
 
==CAUSE==
The loss o:1; heat tracing was due to excessive heat.
: 4.
U1MEDIATK CORRECTIVE ACTION:
The irrnnediate corrective action was to verify that the redundant circuit was operable.
: 5.
SUBSEQUENT CORRECTIVE ACTION:
The defective heat tracing tape-was** replaced and tested within the time span specified by Technical Specifications.
: 6.
ACTION TAKEN TO PREVENT RECURRENCE:
No additional actions were deemed necessary.
: 7.
GENERIC IMPLICATIONS:
A task force has reviewed the total spectrum of the Heat Tracing system and a Design Change is being prepared as a result of the Task Force's study.
Long lead items are being procured.
*.:..:~~.:;._.::._..... --
-:- -~- ---,,...
-- ____ j
::11~ *.:.:-System *:e.ode -~\\\\*- ~;:iP-. ~
s~~ - -... ;-; '.:.:-~,,;,:<',4*;;',.:;;<*:'.",:,,
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*.:..12.
l4.. Componen_t 0.code l5.
Component -sti.bcoae
.l6. Valve -subcode.. -*-:c:..;;.
: 18.
Action taken c..
: 19.
Future action I-
: 20.
Effect on plant ~
i*
: 21.
Shutdown method c:::-
: 22.
Hours 0
: 23.
Attachments
: 24.
*.25.,
.. - -::-,-*.: ~*' -
, -r.....:?.
--*_;,-.:.. ;--.:-- ~..
--*.~~-..:..-.--.~~~_......=___. -.-:*..:*.'.:..~(::'.(:'=\\.--::.. : *-*
NPRD Form
;ir,~-h:l:v~.
I
~ '{I Prime component supplier -;G, ~-
: 26.
Component manufacturers -'--tR(2. v'LM ~
: 28.
: 31.
s k,; ~. ~----
 
==Method of discovery==
Q 0 _ v, 1..... E l ~
I.
Facility status
: 33. Activity -:released
:- 34.
Contents of.release
: 35.
Amount of activity
* 38.
Personnel exposure type
: 42.
Type damage/loss L
}}
 
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Latest revision as of 13:01, 26 May 2025