05000280/LER-2077-005, Failure of Reactor Coolant Flow Comparator to Trip

From kanterella
Jump to navigation Jump to search
Failure of Reactor Coolant Flow Comparator to Trip
ML19105A121
Person / Time
Site: Surry  Dominion icon.png
Issue date: 08/11/1977
From: Stallings C
Virginia Electric & Power Co (VEPCO)
To: O'Reilly J
NRC/IE, Office of Nuclear Reactor Regulation
References
LER 1977-005-00
Download: ML19105A121 (4)


LER-2077-005, Failure of Reactor Coolant Flow Comparator to Trip
Event date:
Report date:
2802077005R00 - NRC Website

text

/.;:*-*_i __ -_-.*-~_'._'.:._r:_*::_.'.:_-_:_:_.t_,_-_-._:_.:._*.,_:_;_:_:,._._.:1_:_*_1:_:_r;_*_* ___

  • _:_:_._I_:,*_._._'._._.:;_,_'._*_:_:_*:,-*:******_***.:_-,

__._~---:*:*.~--.-,_-_--_-,:.?*;."'.;,,/

  • ,, * ;/.

"i'\\ff:f?':)/~:.. _'.*,,:::,:.::,.

' -" ' -*t. -*'

    • .. -*~** _.~ ;

,.:. *.:.RIOHMOND, Vre.oxN:rA',2a2*51

  • *;:cc: '(J * -'*.,1,;:*'
  • * -*{\\ *-~--

2.* * *:.. *... :

.I

  • ,:::-:l**.'...::}'.J:'.:r~:\\'..
  • -:*';Mr..-*.:J~~-:.:_P~;_,~' R~;~l'll'.~:-'.Dir.e~tor,,,:_.c'/*.,.-,:.:::;,_: *--;://f\\\\}i~ Serial **No.* -338*, *

'J,

't -\\,* C

,:,_*/ *.*/,.f

.-.~

C

  • . '"'=t*.'

. \\:i.

'. '.:::~-/~.::*=.:')}t'.}/~ ~;-.

. \\\\.-, '

--. ~; l.':~.\\::, :. -. /*,\\ */;,-. >* \\

  • ,'. i.

-.:_,,*_._:.J_:_._._:_:*_~. ~::_:*.,_* -~ *.*... _:_. _

..... :.. ::_,.:_**,._.: : __ * :-,_*........ *_,.~*.*_.', '

'1

"_-r_\\ };~,;:,:,:,~ :j)>;*~*--*~J~' *:,;f {**,c::,1,._":, ~ J*<r:

~.'_

  • r

.*-.::.,.. _i:Pu~&u~nt, to-Surry,,~o~er *Stat~Oif:~~~hrii¢.al*.. Speci£ica~i?n, _6;6~2(:_the,* :, *

  • *' *:* _:.Virg:i.iµa)Uectrict; ~rid..:'* P(?W8J: _:-coinp!int '*h¢f~by~ ~ullinit's', a;,; C~PY.:.:.<>~,*,R,epo£t~b!t<l; :. * **,

'*.*: Occurrenc*e* No. ;RO-S2-77~05~- *.. '> "< -:*..... :**:~* *

        • ..
  • i-.:,:;;-'*t/,,, /-/':-:.. '. :'°"*** *: *.

. *>.;/':*,/~h~*:'.**;ub~ ~~~~::*:~~-;-~:~~J;~¥i~~1::::;~~!i~le1{'i~~l~4:,:_b/::~~e, ::*;t~::to:,:.-~ti~i-~r-::;i*._:*..,

. *. Safet;y_:and**,0perat.ing'Committee* and**wiil;J:,~ plS:c~d ~n: :the*ag~d~ :for*:the...

<._*.::. '. next' _meeti~g_..-of -~~e' Sy~~em* ___ ~t,t.c_:i;~--*iSaf~~y*::a~~\\operatilig: eommit~ee~ *;: *'.\\. ' '

  • ' *, *\\> *.

.. * /*;,iiJ?:~:,.!i:;t~r:~~/f f ~?ruff \\'.Y f m;lf "._{ * *

.,;: ':-<*_:_?:_:_if':_.. -.:.~_:_:_ *. :.,.** *_:,, :.,t '.' \\'.i*.~:_*/t11 i-*->Jf[i~(&ift'i :*. j,:._.::/.?.:* ','

    • . qi:'!';t:i}:)rf ;!_jf iiij~~~l!=J::}((Il*

' ;.--.~,

' J.' -~* _;'.I.

,,,-1 :*. *'. :~-~: *

. *.,*1

e LICENSEE EVENT REPOR'~

CONTP.OL BLOCK: L._j 1

I J.. J I J (IYJW!.lrle ~BF.'JT f.\\U. !l§@IJ!!<lfiO l!'Ji'lDO'.lC:1:~'!i'~rG_;

LICENSEE NAME

@Ifl L vi A Is I PI s I 21 7

8 9 14 6

LICENSE NUMBER Io Io I~ I o Io Io Io l o I-lo Io I 15 25 LICENSE TYPE 14!1!1!1!0!

26 30 EVENT TYPE lo \\ 3 I 31 32 CATEGORY REPORT SOURCE OOCKl;T NUMBER EVENT DATE REPORT OATE

@ill CON'T ~.

llJ I o I s I o I~ 10 j 2 1 s 11 I

  • I o I 7 j l Is 17 L7 I 1.Q_ls!o!3!7!7J 1

a 57 sa 60 61 68 69 74 75 ea EVEi\\!T DESCRIPTION

@llij lAt Cold Shutdown, in the course of routine testing, Reactor Coolant Flow Comparator J 7 es 80

@liJ LQ:£-2-414) failed to trip.

7 6 9 The two redundant systems were operational for the J

80

@Ei] l!,7quired two out of three low flow trip.

Previous test was satisfactory.

The I

7 8 9

~

~:rective action implemented was to replace the comparator

, a a 80 with an operat~~j

~

l,~yare.

This conditio~ ~s reportable 80 per Technical Specification 6.6.2b(2).

_I 1 es SYSTOA CODE

@0 LLUI 7

B 9 10

CAUSE

CODE w 11 CAUSE DESCRl?TION.

COMPONENT COOE l I I NI s I T! R I UJ 12 17 COMPONENT MANUF~

IH I O 1 2 I O I 44 47 (RO-S2-77-.5

)

80 VIOlATXJN

~

48

@:rill l.AJtestingl;_ousE:._Hagan Single Sig~al Comparator Model 4111082-001 failed to trip due toJ 7.B 9 80

@NJ L_c.apacitor leakage.

Since these capacitors. have an expected life of 10 to 20 yea:.s, J

7 88

~

IT@ ~~

this fai~apacitor has been in use for, approximately nine years, the (Co?t'd) j 7

89 00 FACILITY METHOD OF STATUS

'16 POWER OTHER STATUS DISCOVERY lgJ Lg I o! o J._l -..:N/._A ___

......iJ W 8

10 12 13 44 45 Lill]

7 6

FORM OF

~.CTWl1'Y CONTENT j PT-2. 2 -

46 DISCOVERY OESCRIPTION Reactor Coolant Flow.

80 E]I

, a Rl:I.EASEO OF P.ELEASE AMOUNT OF ACTMTY LLl LLl I.__N~/ A _____

9 10 11 44 I

N/ A LOCATION OF RELEASE

~-----------~1 45 BO PERSONNa EXPOSURES NUMBER TYPE OESCJ:llPTION [el b.J.o_W lLJ

-'='--N..... / A-----------~-------------1 7

S S 11

- 12 13 60 PERS.ONNEL INJURIES NUMBER OESCF'JPTIQN EE~

N/A 7 B 9

11 1*"!2-----------------------------~---~----8...,iO OFFSITE CONSEG!UENCES B]j NA

_J 7

8 S 80

°Loss OR DAMAGE ro FACILITY TYPE

DESCRIPTION

filfil WI=-_N

__ {_A _________________________ J 7

a 0 10 so PUBLICITY (ill]

N/A 1

7 8 9 80 ADDITIONAL FACTORS GEJ L The ~1ealth and safety of the public were not affected because the two operational _J 7

6 9

- 80

~ ~unclant: comp1:rators would have initiated the required low flow trip, in that 7

8 9 (Cont'f-:

80 NAl\\.1E:--.,""4~~"=

  • --- PHONE: t!3CJ <./-JS"?- 9:1~
  • G 07

L

. e 1

CAUSE DESCRIPTION (CONTINUED) probable cause was aging.

As per a Westinghouse Technical Bulletin (NSD-TB-75-14) dated October 21, 1975, these capacitors have no specific problem qf *a generic nature.

However, Westinghouse does recommend that these leaking capacitors be replaced with a premium grade or Tantalum capacitor, presently available, on an as-failed basis, instead of a general capacitor replacement program.

This cri-teria is presently observed-at Surry.

The present rate of capacitor failure is very low and any increase in this rate will require a re-evaluation of our capa-

_citor change-out policy.

ADDITIONAL FACTORS (CONTINUED) particular loop.

I

RECEIVED DOCUMENT PF:OCESS!t!G UfJ!T

  • 1911 AUG 15 AM 9 I 7