ML20086J081

AO 75-3:on 750105,small Crack Indications Detected by Ultrasonic Testing Techniques on Recirculation Loop B 4-inch Bypass Pipeline.Cause Under Investigation.New Pipe Spool Installed & Welds Successfully Radiographed

ML20086J081
Person / Time
Site:	Peach Bottom
Issue date:	01/15/1975
From:	Cooney M PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	Giambusso A Office of Nuclear Reactor Regulation
Shared Package
ML20086J083	List: ML20086J081 ML20086J086
References
AO-75-3, NUDOCS 8401230152
Download: ML20086J081 (2)

Text

-

3 C\ f~3 U v PHILADELPHIA ELECTRIC COMPANY 4W:

'N i v. ~ ~ %4 1

2301 MARKET STREET ," '"$%, '

, ' ,/

, ,. O ',7 i

PHILADELPHIA. PA.19101 r

-cup $ -

1215) 841-4ooo

~' * - 'I ,I-[,,

January 15, 1975 9., gg;. '2 , sij

@ c'%pyg, Mr. A. Giambusso Ng /

Deputy Director of Reactor Projects United States Atomic Energy Conmission Directorate of Licensing Washington, DC 20545

Subject:

Abnormal Occurrence and DRO Bulletin 74-10A The following occurrence was reported to Mr. Walt Baunack, A.E.C. Region 1 Regulatory Operations Office on January 5,1975 Written notification was made to Mr. James P. O'Reilly, Region 1 Regu- <

1atory Operations Office on Januai y 6,1975 In accordance with Section 6 7 2.A of the Technical Specifications, Appendix A of DPR-56 for Unit 3 Peach Bottom Atomic Power Station, the following report is being submitted to the Directorate of Licensing as an Abnormal Occurrence.

This report is also intended to satisfy Philadelphia Electric Company's response to DRO Bulletin 74-10A in the mei.ici vi Unit 3

Reference:

License Number DPR-56 Technical Specification

Reference:

1.0.D.5 Report No.: [50-278-75-D Report Date: ' January 15, 1975 Occurrence Date: January 5,1975 Facility: Peach Bottom Atomic Power Station R.D. 1, Delta, Pennsylvania 17514 Identification of Occurrence:

Small crack indications were detected by ultrasonic testing

. techniques on the 'B' recirculation loop 4" bypass pipdline. - - -

• Conditions Prior to Occurrence:

Unit 3 shutdown.- Primary coolant temperature approximately 150 F.

Description of Occurrence: '

As a result of the ultrasonic inspection of the 4 inch piping associated with the recirculation pump discharge valve on the Unit 3 r,c ac tor , three indications of cracks on the internal surface of the 4 inch piping were noted. The-small cracks on the upstream end of the 0 I

~ PDR 84012301{2 ADOC 0

PDR CCC S

Mr. A. Giambusso (^3 Jrnu;ry 15, 1975 k / 'Pcg3 2

({')

pipe spool were confirmed by liquid penetrant examination of the I.D.

following removal of the speol. The U.T. indications on the downstream end of the spool could not be confirmed by liquid penetrant examination.

There was no through-wall f ailure of, or leakage from the pipe.

Designation of Apparent Cause of Occurrence:

Unknown at this time. Investigation is in progress.

Analysis of the Occurrence:

This occurrence did not result in any primary coolant leakage.

The pipeline containing the crack indications was capable of prompt iso-lation. There was no release of radioactivity. Safety implications are minimal.

Corrective Action:

The section of piping containing the suspected defects was removed and is undergoing metallurgical examination. A new pipe spool was installed and the welds were successfully radiographed, ultrason-ically tested, and liquid penetrant tested. A hydrostatic test at normal operating pressure was witnessed by an ASME code inspector.

Failure Data:

hone.

Very truly yours, H. . Cooney /

Ass!t Gen't Superintendent Generation Division cc: Mr. J. P. O'Reilly Director, Region i United States Atomic Energy Commission 631 Park Avenue King of Prussia, PA 19406 Ass't Director for Construction and Operations k Directorate of Regulatory Operations United States Atomic Energy Commission Washington, DC 20545 '

y I

t t

l 3

I f

i

\ t p __ ___ 2