ML20010C729

From kanterella
Jump to navigation Jump to search
Updated LER 80-041/03X-2:on 801229,routine Surveillance Discovered Water Leaking from 4-inch Reactor Water Cleanup Line Between Regen & Nonregen Heat Exchangers.Caused by Stress Corrosion Cracking.Affected Portion of Pipe Replaced
ML20010C729
Person / Time
Site: Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date: 08/05/1981
From: Murphy W
VERMONT YANKEE NUCLEAR POWER CORP.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20010C726 List:
References
LER-80-041-03X, LER-80-41-3X, NUDOCS 8108200354
Download: ML20010C729 (2)


Text

QFony ass Correction to UPDATE REF9RT - Previous Report 1/28 /810. S. NUCLEAR R EGULATOQY COMMISSION UPDATE REPORT 7/8/81 LICENSEE EVENT REPORT LER 80-41/3X CONTROL BLOCK: l i

l l l l l lh e

(PLEASE PRINT OR TYPE ALL REQUIREG INFORMATION)

R IVd IT J 9 I VLACENSEE l Y lCODE s l 1 l@l 0101 -l 0101 14 15 O i 0l 01 -l 0l 01@l4 LICENSE NUMSER 25 M l1LICENSE l1 l1TYPE l1 JOl@l57 CAT l Sa l@

CON'T lol I i 5 5Ou?$

R 60 l L hl 61 0 l 5 lDOCK 0 lET0NbMBER l 0 l 217 68 l 1 @l 69 1 EVENT l 212 l 9l 8l 0@l75 Ol8'REPORT DATE 14 l0 l DATE 5 l 8 l180l@

EVENT OESCRIPTION AND PROBABLE CONSEQUENCES h 10121 l During startup at 24 percent power, routine operation surveillance d scovered water I lo I31 i leaking f rom the 4 inch. Reactor Water Cleanup Line between the Regen and the Non- J 101411 Regen heat oxchangers. Upon close inspection, two areas of water weepage were l I o I 51 i found. There were no consequences to the public health and safety as a result of I I O 16 I i this event. Similar occurrences were reoorted to the commission as T ER 80-37 and I I o I 7 I I 1 FR 79-01. I I o 181 1 I F 8 9 80 CE CODE Su8CO E COMPONENT CODE

  • SL8CbO'E Su E lol91 l C ] G l@ W@ l D l@ lP l1 l P l E l X l X l@ W@ 20W @

F 8 9 10 11 12 13 18 19

,_ SEQUENTIAL OCCURRENCE REPORT REVISION LER'RO EVENTYEAR REPORT NO. COCE TYPE NO.

O17 ,REQE RT l 8l 0l 22 l-l 23 l0 l4 l1l 24 l/l l0l3l lX l l-l l 2]

21 26 27 28 29 30 31 32 TAK N ACT CN ON PL NT M HQURS S8 i FOR 8. SUP IE MANUFACTURER

[Aj@W@

J3 J4 l 7. l@

S lZ M

l@ l0 l0 i0 l 0 l 37 40 lYl@

41 lYl@ l43 Al@ lU l1 l0 1547l@

42 44 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Lu o I I I I1 lil i SEE ATTACHFD l 11 171 l l f i l 31 l l U_1,i.j l 1 8 9 80 ST S  % POWER OTHER STATUS Ots O RY DISCOVERY DESCE PTION y d@

  • l Ol g l 4 l@l NA l l B l@l Operator Observation l

.ltiviTY CO'e RENT RELEASED OF RELE ASE AMOUNT OF ACTIVITY LOCATION OF RELEASE W ' 'd' @ W@l NA I l NA l

PERSONNR nPOSSES NUM.ER TYPE DESCRiPT,0~ @

R I0l0lOl@

d @l" NA 8

l PtRSONNd'i~JJ,ES NUYBER DESCRsP TION l.'.h.I8 109 10 10 l@l1211 NA l 7 80 LOSS OF OR D AM AGE TO F ACILITY TYPE D E SCRIP TION li19l d @l 7 $ 1 10 NA l 80

o rhSurn@DESCRIPTiONVermont l Yankee Daily Status Report (12/30/80) l [] l1Ill1ll l1lj 7 s 3 to 68 69 80 5 8108200354 810805
  • PARER
  • PDR s ADOCK 05000271 pon j

VTVYS1 Correction to UPDATE REPORT 7/8/81 O 00 Previous Report 1/28/81 L 80 41/3X Cause Descriptica and Corrective Actions:

The Reactor Cicanup Line was isolated and the affected portion of the pipe was replaced with a low carbon stainless steel pipe. The pipe material f rom the regenerative to the Non Regenerative Heat Exchanger was ASTM-A-312. Type 304.

An examination by Battelle Laboratories revealed branching, trans-granular cracks originating f rom pitted areas on the outside diameter surface of the pipe. Scanning electron microscope and metallographic examinations confirmed the transgranular nature of the cracks. X-ray defraction revealed high amounts of chloride in the corrosion product on the outside surface of the pipe. The corrodent indicated the cracks were a result of chloride-stress-corrosion cracking. It appears that the long-term leaching of the asbestos insulation by a high purity water leak f rom a faulty fitting brought i a sufficient amount of chlorides to sne surface of the not pipe (575"F) to f result in Stress Corrosion Cracking.

,