ML19341A254

From kanterella
Jump to navigation Jump to search
LER 80-043/03L-0:on 801220,reactor Core Isolation Cooling Valve 15 Had Seat Leakage of 1.531 Lbm/Hr,Exceeding Tech Specs.No Cause Noted.Valve Seating Surfaces Lapped & Valve Retested
ML19341A254
Person / Time
Site: Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date: 01/16/1981
From: Murphy W
VERMONT YANKEE NUCLEAR POWER CORP.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19341A253 List:
References
LER-80-043-03L, LER-80-43-3L, NUDOCS 8101220462
Download: ML19341A254 (1)


Text

o  !

.U

.NRC FORM 364 . U.S. NUCLEAR REGULATO2Y COMMISSION ]

T7 771 LICENSEE EVENT REPORT LER 80-43/3L CONTROL BLOCK: l I

l l l l 1 l@

6 (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATIONI lo Iilsl sv ! TIucaNsEs Vl vcoog I Sl 11@l 0l 01 -l Oiucasss is is 0l 0lNuustR 0101- l 010 l@l 25 4

2e l 1uceNss l 1 I Tvee il 11@l 40 l l si car sa @

CON'T 10l'I 7 8 so RcE I60 L hl Of Sl 0l 61 0l Ol 217 l1 l@l112 OOcKET NUMSER 68 69 l 210 l 810 l@l 0lREPORT tvENT oATg 74 75 1l IloATE 6l 8l1]@ do EVENT DESCRIPTION ANO PROBABLE CONSEQUENCES h l o 12 l l While performing the Type C Leak Rate Testing, RCIC -15 was found to have seat i 1 o 131 11eakane of 1.531 lbm/hr which is in excess of Tech. Spec. Sec. 4.7. A.4. Since a i lotalIsecond valve in the line provided containment isolation, there were no adverse l l o t s i i consequences to the health and safety of the public. There has been no similar l lo l6 l loccurence reported to the Commission on this valve. I lol71l J 10141 1 7 se b SoEs" ##is' co stsci$E coupessNT ccos suscIoe sU$s 10191 l C l E l @ l E l@ (_b_j @ l V l A l L l V l E l Xl@ l E l@ l Dl @

7 8 9 iQ tt 12 13 is 19 20

_ SEQUENTIAL OCCURRENCE REPORT Revision (ta no EVENT YEAR REPORT No. CoOE TvPE No.

  • E O'7 yy,1,a7 l Bl 0l l-l l0l4l3l l/l 10l3l lL l l-l l Of 21 22 23 24 26 27 28 29 30 31 32 TKN AC ON P NT ME HOURS s8 i POR 8. SUPPL E MANUFAC RER l33B l@l34 Zl@ lasZ l@ lM Z l@ l010l0l0l 37 4g

[N,1,,,j @

41 lYl@ l Al@ lWl0l3l0l@

gg 43 g gy CAuSE DESCRIPTION ANO CORRECTIVE ACTIONS @ ~

li1011 The valve seating surfaces were lanned and the valve was satisfactorily retested I t i li j l prior to plant startup per Tech. Spec. Sec. 3.7.A.4. The valve failure will I iii2i I also be reported in accordhnee with Apoendix J, 10 CFR 50, V.B.3. I Ii13l l l liIAI l l 7 s e so

's'T'02 sPowtR oriseRsTATus h 5'sEoSSOv' oiscoveRv cescRiptioN O IiisllHl@ l0l0l0l@l" NA l lB l@l Surveillance Tests _

l Ac'TiviTv co'0 TENT a LeAsso or a LEASE LeCAT CNOFRELEAsE6 l

l1 l 6 l [,2,] @ [f,,l@l AMOUNT NA OF" ActviTVl

@ l NA

  • l esRsoNNeL exposuAss Nuva:R Tves osscRietioN @

l5 l 7 l l 01 01 Ol@l ' '

Z lhl" NA l esRsoNNe'LINJURIEs  !

NuvseR orscRinnoN@

NA .

l i l a$l 9l 0 l 0 l 0 l@l12 11 l

P SO l Loss of OR oAMAGE To FAcluTv g

, Tv'5 C E sCRIPTION NA lt 13 sl 3l Z l@lto 7

l 53

  • ca Lici NRC USE CNLV p

l2lSi I 6 3 h@l to n I 68 67 i 8 IIIIIIIf It lI 33 5 NAME OF PAEP ARER Warren P. Murphy AwCNE:

(802) 257-7711 g 810122OyfQ