ML19317E847

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Discusses Facility Steam Generator Leak.Steam Generator B Tube Leak on 771007 Caused by Cracked Lane Tube C77-T25. Tube Plugged & Power Returned.Leakage Rate Monitoring Contines
ML19317E847
Person / Time
Site: Oconee  Duke Energy icon.png
Issue date: 02/01/1978
From: Shao L
Office of Nuclear Reactor Regulation
To: Eisenhut D
Office of Nuclear Reactor Regulation
Shared Package
ML19317E846 List:
References
NUDOCS 8001031011
Download: ML19317E847 (2)


Text

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D. Eisenhut, Assistant Director for Operational i

MEMDPJdiD'J!4 l'OR:

Technology, DDR L. C. Shao, Chief. Engineering Branch, DDR TP.0M:

OCO' EE U!i1T 2 STEA. GENERATOR LEAK

SUBJECT:

I On October 7,1977 Oconee Unit 2 was shut down to locate a 0.

tube leak in stectr. generator B.

to locate the leak and the unit was returned to 70% power.on October.

After returning to power operation,.the leak dcveloped again nt a stable rate of 0.03 GPM until November 3,1977 when the 27, 1977.

lect rcle increased to 0.65 GP" during cn atte:r.pt to incrcase power.

The unit uts coain shut down end a second unsuccessful inspection On I ovtr.:ber 11, 1977 the unit returned to for the leLL was rce.de.

28,1977 when power nd operated it reduced ;;ower until Decer.berit un it was reported that the source of the leak was 10, 1975 On Janacry The crack was discovered to be a crack in lane tube C77-T25.

inspectcf using fiber optics imd was described by the licensee e.s The e 50 cirtur.ferentir.1 crack incr.r.ed at th? upper tube no detectable leaki.ge in the unit.

A similcr occurrence in July 1577 involved tube C77-T2 in generator.3-B.

Although this crcck had not propt-to 9:l' circumfere.titi crack.

gated fully around tr.e tube in a short tine as ucs the case in cther lane tubes it was feit tMt this was a phenomenon aff ectint; only peripher.1 tuucs where lor:er cross flow. velocities supplied less kinetic energy for crcck prop:s tion.

The recently plugg:.d tube, C77-T25;however, is not a peripheral t ut is lon.t e:' nct.r ti.e rr:ddle oi' the open tube lare in en Ho.iever, since the unit m s tub:

area 'of higher cron flow velocity.

operating et reduced power levels (less than 70'/) the flow velo and in turr, ti.e e:.9rgy tvtilLblTna efore.the'crati. s.ould tend to stabilir R

decreated.

this recent event is consistent with lie believe tht:

Further-

. power levels.

past experience for lane tubes and is not a new phenomenon.

more, close manitoring of the leakage rate in confonr.ance with the 90

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2 FEB 011973 D. Eisenhut 4

technical specifications will continue to ensure safe operation of the unit.

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A L. C. Shao, Chief

  • Engineering trar!ch Division of Operating Reactors

Contact:

J. Strosnider 49-20050 cc:

V. Stello J. Guibert R. Cudlin R. V.ntisen J. Kr.ight S. Pawlici:i R. Dosnal:

B. Turovlin R. Stuart B. D. Liau l

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