ML20086C122

Interim Deficiency Rept Re 3/4-inch Pipe Failure in RHR Sys. Addl Review Revealed That Although Sys Installed Met Design Criteria,Abnormal Vibration During Hot Functional Test Caused Failure

ML20086C122
Person / Time
Site:	Salem
Issue date:	04/20/1976
From:	Schwalje E Public Service Enterprise Group
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20086C120	List: ML20086C117 ML20086C122
References
10CFR-050.55E, 10CFR-50.55E, NUDOCS 8311220578
Download: ML20086C122 (2)

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PublicService ElectricandGasCompany 80ParkPlace Newark N.J. 07101 Phonc201/622-7000

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April 20, 1976 .

"li Mr. Jamec P. O'Reilly, Director i U.S. Nuclear Regulatory Commission Office of Inspection and Enforcement ~[

Region 1 C 631 Park Avenue King of Prussia, Pennsylvania 19406

Dear Mr. O'Reilly:

SUPPLEMENTARY INFORMATION '

SIGNIFICANT REPORTABLE ITEMS 10CFR50.55(e)

LETTERS OF MARCH 16 AND 31, 1976 NO. 1 UNIT SALEM NUCLEAR GENERATING STATION Reports of March' 16', 1976 "3/4 Pipe Failure - RHR Systems" and March 31, 1976 "CvCS No. 13 Charging Pump Suction Header" were.

submitted in compliance with 10CFR50.55(e) . The following is offered as supplementary information to these'two reports and to provide further assurance of the adequacy of similar piping in other systems.

Operating experience of No. 1 Unit, Salem during the hot-functional test afforded the opportunity to. observe expansions, '

vibrations and other characteristics of the piping- systems.

Although these systems as installed met the design criteria,.

abnormal vibration during hot functional test was the cause of the two reported subject failures. As a result of~these

occurrences, a review was initiated of similar piping instal-la tions in other safety-r. elated systems.

This analysis consisted of drawing reviews plus physical-examination oflthe installed piping systems. This-inves.tigation which took into account the hot functional. test operating.

experience will result in revisions to add 1 additional conser-

.vatism in selected areas above - that needed to meet the original-design criteria. Pipe replacement, test, inspection and verification controls will-be . equivalent lto 'that of the ' original installation.

I 8311220578 760316 PDR ADOCK 05000272 PDR g

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Mr. J.P. O'Reilly -2* ' ' h/20/y6*~ f-l

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! The work is scheduled to be. completed by core loading and y,311 ,

provide the added. assurance to prevent the recurrence of th29 "? D

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type-of failure. N

-- . s Very truly yours, '

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h' <-- ,r,_

1. m E. N. Schwa 1 J e Manager of Quality Assurance Engineering and Construction.

• Department '

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CC: Director, U.S. NRC '

m Bethesda, Md. ,

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