ML20084S777

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AO 50-265/75-38:on 751014,weld Exams Indicated Crack on B Loop of Rx Recirculation Discharge Bypass Line.Caused by Intergranular Stress Assisted Corrosion.Both Bypass Lines Will Be Removed
ML20084S777
Person / Time
Site: Quad Cities 
Issue date: 10/24/1975
From: Kalivianakis N, Vahrenwald J
COMMONWEALTH EDISON CO.
To:
Office of Nuclear Reactor Regulation
Shared Package
ML20084S780 List:
References
NJK-75-525, NUDOCS 8306170247
Download: ML20084S777 (4)


Text

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Telephone 309/654-2241 NJK-75-525 October 24, 1975 Dir'ector Of Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 IE FILE COPY Refe rence: Quad-Ci ties Nuclear Power Station Docket No. 50-265, DPR-30, Unit 2 Appendix A, Sections 1.0.A.5, 6.6.B.I.a Enclosed please find Abnormal Occurrence Report No. A0 50-265/75-38 for Quad-Ci ties Nuclear Power Station. This occurrence was previously reported to Region lil, Of fice of Inspection and Enforcement by telephone on Octo-ber 13,1975 and to you and Region 111, Office of inspection and Enforce-ment.by telecopy on October 14, 1975

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This report is submitted to you in accordance with the requirements of Technical Speci fica tion 6.6.B. I.a.

Very truly yours, COMMONWEALTH EDISON COMPANY QUA'D-CITIES NUCLEAR POWER STATION

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$l'.f ay,N '4f(9N N. J. Kalivianakis 3

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REPORT NUMBER: A0 50-265/75-38 REPORT DATE: October 24, 1975 OCCURRENCE DATE: October 14, 1975 FACILITY:

Quad-Ci ties Nuclear Power Station Cordova, Illinois 61242 IDENTI FICATION OF OCCURRENCE:

C' rack indications in Unit 2 "B" reci rculation loop discharge valve bypass line upper weld-o-let.

CONDITIONS PRIOR TO OCCURRENCE:

Uni t 2 was in the cold shutdown condition.

DESCRIPTION OF OCCURRENCE:

In accordance with the provisions of NRC R.O. Bulletin 74-10A, ultrasonic testing of accessible welds in the bypass piping lines around the recirc-ulation pump discharge valves.was performed during the Uni t 2 core main-tenance outage.

On October 14, 1975 a crack indication was confirned on the "B"

loop at the junction of the bypass line with the 28 inch discharge header on the down-stream side of the bypass valve.

The crack indication was in the heat affected zone.on the pipe side of the pipe-to weldolet weld.

DESIGNATION OF APPARENT CAUSE OF OCCURRENCE:

Equipment Fai lu re The mode of failure and thus the cause of this occurrence has not been established as of the date of this report.

The apparent cause is believed to be the same as that which has caused similar cracks in recirculation bypass lines in the past, that is, intergranular-stress assisted corrosion.

ANALYSIS OF OCCURRENCE:

Early detection of the crack prevented violation of the leak rate limits set forth in the Technical Specifications and as modified by 1.E. Bulletin 74-10B.

No radioactivity was released to the environs nor was any health t

hazard.to the public or plant personnel posed.

Thus, the safetp implications of this occurrence were mininal.

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A0 50-265/75-38 October 24, 1975 CORRECTIVE ACTION:

The existing recirculation pump discharge valve bypass piping on both loops A and B will be removed.

The removal will be accomplished by installing 16 inch 304 L low carbon stainless steel spool pieces with pipe end caps.

This work is documented by Quad-Ci ties Modi fication M-4-2-75-27 An in-formation letter describing the details of the. modi fication will be pro-vided in the near future.

This modification has been discussed and reviewed with various Region 111 NRC representatives.

FAILURE DATA:

On September 16, 1974 Quad-Ci ties Uni t 2 experienced a crack at weld 2BB-F 10 on the B loop.

Corrective action at that time was to replace the weld and a short section of pipe.

A second ultrasonic inspection, conducted on Quad-Cities Unit 2 on Dec-ember 23, 1974 revealed two indications on bypass loop A and one additional indication on bypass loop B.

Corrective action at that time was to replace both the A and the B loop recirculation pump discharge valve bypass piping.

On Januarv 10, 1975 an examination of quad-Ci ties Uni t I recirculation pump discharge valve bypass piping revealed a crack on the A loop weldolet running along the 4 inch side of the weld and an indication of a crack on the.B loop weldolet running 1/2 inch to 3/4 inch from the weld head.

Corrective action was to replace both the A and the B loop recirculation pump discharge valve bypass piping.

Similar cracks were also found at Dresden and Millstone stations.

The pipe that failed in all cases was 304 stainless steel, four inch diameter with a wall thickness of 0.377 inches nominal.

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