ML19340C497

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LER 80-037/01T-1:on 801027,cracks Discovered in 4-inch Reactor Water Cleanup Suction Line.Cause Undetermined. Samples of Cracked Pipes Sent to Lab for Analysis
ML19340C497
Person / Time
Site: Vermont Yankee Entergy icon.png
Issue date: 11/08/1980
From: Murphy W
VERMONT YANKEE NUCLEAR POWER CORP.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19340C496 List:
References
LER-80-037-01T, LER-80-37-1T, NUDOCS 8011170500
Download: ML19340C497 (2)


Text

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NRc FORM ass ^ u's.~ NUCLEAR REGULATORY COMMISSION (7 771 q -

LICENSEE EVENT REPORT- LER 80-37/1T

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(PLEASE PRINT CR TYPE ALL REQUIRED INFORMATION) l l@

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DOCKET NUM8 E R EVENT OESCRIPTION ANO PROBA8LE CONSEQUENCES h 10121 lDuring performance of Inservice Inspection while shut down for refueline. crnek=  !

Io lal lwere discovered in the 4" Reactor Water Cleanuo Suction Line. Of 13 velds in e:nocrod l lo141.-15 had cracks in the weld heat-affected zone. One of these was a throusth-wall crack- l 1

Ioisl lin a non-isolable section of the line. Another through-wall crack was foune on the I l o is I Ithroat of the 20" X 4" sweenolet which connects the clonnun Ructinn T.i no en tha J l 0 i 7 I l20" RHR Suction Line . also non-isolable. I 10181I l 7 8 9 80

, DE . ODE SU C E COMPONENT CODE SL8C OE S E l0l9l lC lG lh y@ lC l@'lP lI lP lE lX lX lh W@ y @

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,_ SEQUENTIAL OCCURRENCE REPORT REVISION LER EVENT YEA R REPORT NO. CODE TYPE N O.

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40 41 42 - 43 47 CAUSE OESCRIPTION ANO CORREC+"T ACTIONS 11 101l I li ;i l l SEE ATTACHED SHEET. I i

li 12 1 I 11 131 l l u_L4 I I I 7 8 9 - So SA S  % POWER OTHER STATUS DIS O Y OISCOVERY DESCmPTION h y W @ l010l0l@l -NA l lBl@l Inservice Inspection l AfTivtTY CO TENT RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE l 1 l8 69 l l Z l @D OF RELEASE 7 to 13 NA

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PERSONNEL EXPOSURES NUMBER TYPE ISCRIPTION li 17110101 Ol@M@L -

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LOSS OF CR CAMAGE TO FACILITY l TvPE DESCRIPTION li191 7- 8 9 W @lto NA l 80 1

  • g hSUED@l E CRIPTION Press release dated 11/7/80 l l l l l l l l t I l ! I l j.-

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- N'AME OF PREPARER Warren P. Murchv psong; @U WWH {

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  • VTVYS1 05000271 LER 80-37/lT CAUSE DESCRIPTION AND CORRECTIVE ACTIONS A decision has been made to replace the Reactor Water Cleanup Suction Line with conforming material per NUREG 0313, Rev.1 from the RIIR branch con-nection to the cutboard isolation valve. Existing materials are ASTM-A-312, Type 304 pipe, ASTM-A-182, Type 304 sweepolet, and ASTM-A-403, Type 304 elbows.

Samples of the cracked piping will be sent to a laboratory for analysis of the failure mode, and the results of this analysis will be provided in a subsequent report.

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