ML19256E704

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Forwards IE Bulletin 79-17,Revision 1, Pipe Cracks in Stagnant Borated Water Sys at PWR Plants. No Response Required
ML19256E704
Person / Time
Site: 05000363
Issue date: 10/29/1979
From: Grier B
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To: Finfrock I
JERSEY CENTRAL POWER & LIGHT CO.
References
NUDOCS 7911150039
Download: ML19256E704 (1)


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UNITED STATES y 7-) s- ( 3 g NUCLEAR REGULATORY COMMISSION

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631 PARK AVENUE

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KING OF PRUSStA, PENNSYLVANIA 19406 Docket No. 50-363 OCT 2 9 ;33 Jersey Central Power & Light Company ATTN:

Mr. I. R. Finfrock, Jr.

Vice President 260 Cherry Hill Road Parsippany, New Jersey 07054 Gentlemen:

The enclosed IE Bulletin 79-17, Revision 1, is forwarded to you for information.

No written response is required.

If you desire additional information regarding this matter, please contact this office.

Sincerely, M'

f n

oyce H. Grier

' Directnr

Enclosures:

1.

IE Bulletin No. 79-17, Revision 1 w/ Attachment 2.

List of IE Bulletins Issued in the Last Six Months CONTACT:

L. E. Tripp 215-337-5282 cc w/encls:

M. K. Pastor, Project Manager 1337 292 7911150 0 37 9

ENCLOSURE 1 UNITED STATES SSINS No.:

6820 NUCLEAR REGULATORY COMMISSION Accession No.:

0FFICE OF INSPECTION AND ENFORCEMENT 7908220147 WASHINGTON, D.C.

20555 d

IE Bulletin No. 79-17 fiavision 1 Date:

October 29, 1979 Page 1 of 5 PIPE CRACKS IN STAGNANT BORATED WATER SYSTEMS AT PWR PLANTS Description of Circumstances:

IE Bulletin No. 79-17, issued July 26, 1979, provided information on the R1 cracking experienced to date in safety-related stainless steel piping R1 systems at PWR plants.

Certain actions were required of all PWR R1 facilities with an operating license within a specified 90-day time R1 frame.

After several discussions with licensee owner group represeatatives and R1 inspection agencies it has been determined that the requirements of Item 2, R1 particularly the ultrasonic examination, may be impractical because of un-R1 availability of qualified personnel in certain casas to complete the in-R1 spections within the time specified by the Bulletin. To alleviate this R1 situation and allow licensees the resources of improved ultrasonic inspec-R1 tion capabilities, a time extension and clarifications to the bulletin have R1 been made.

These are referenced to the affected items of the original R1 bulletin.

During the period of November 1974 to February 1977 a number of cracking incidents have been experienced in safety related stainless steel piping systems and por-tions of systems which contain oxygenated, stagnant or essentially stagnant tar-ated water.

Metallurgical investigations revealed these cracks occurred in the weld heat affected zone of 8-inch to 10-inch type 304 material (schedule 10 and 40), initiating on the piping I.D. curface and propagating in either an inter-granular or transgranular mode typical of Stress Corrosion Cracking.

Analysis indicated the probable corrodents to be chloride and oxygen contamination in the affected systems.

Plants affected up to this time were Arkansas Nuclear Unit 1, R. E. Ginna, H. B. Robinson Unit 2, Crystal River Unit 3, San Onofre Unit 1, and Surry Units 1 and 2.

The NRC issued Circular No. 76-06 (copy attached) in view of the apparent generic nature of the problem.

During the refueling outage of Three M cfthisyear,visualinspectionsdi;scl DUPLICATE DOCUMENT in the soent fuel cooling system pipin removal system.

These cracks were fou Entire document previously and later confirmed by liquid penetran entered into system under:

cracking was reported to the NRC in a 1979.

A preliminary metallurgical ana 79dfhMd[57 ANO section of cracked and leaking weld Jo

-'-w" I'f 1337 293 No. or gases:

R1 - ldentifies those additions or rev