ML19246C547

From kanterella
Jump to navigation Jump to search
Forwards IE Info Notice 79-19, Pipe Cracks in Stagnant Borated Water Sys at PWR Plants. No Action Required
ML19246C547
Person / Time
Site: Arkansas Nuclear  
Issue date: 07/17/1979
From: Seyfrit K
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To: Cavanaugh W
ARKANSAS POWER & LIGHT CO.
References
NUDOCS 7907260325
Download: ML19246C547 (1)


Text

  1. p "' %jo CENTRAL FILES UNITED STATES

,8 'j,

(g NUCLEAR REGULATORY COMMISSION pg PDR:HQ g

M

.. c REGION IV g {il

[

G11 RYAN PLAZA DRIVE, SUITE 1000 U${C

%, ' '-iL+ /

AR LINGToN, TEX AS 76012 July 17, 1979 Docket Nos.

50-313 50-368 Arkansas Power and Light Company ATTN:

Mr. William Cavanaugh III Vice President of Generation and Construction P. O. Box 551 Little Rock, Arkansas 72203 Gentlemen:

This IE Information Notice is provided as an early notification of a possibly significant matter.

It is expected that recipients will review the information for possible applicability to their facilities. No response is requested at this time however licensees should be aware that the NRC is evaluating the issuance of a Bulletin to operating PWR's requesting information on previous inservice inspections of stagnant borated water systems and requesting inspection of systems which have not been inspected recently.

If you have questions or comments regarding this matter, please contact the Director of.the appropriate NRC Regional Office.

Sincerely, c w k y)-

/ 'g r

Q Karl V. Seyfrit Director

Enclosures:

1.

IE Information "utice No. 79-19 2.

L4 i IE Information Notice

.suued in 1979 James P. O'Hanlon, Plant Manager cc:

Arkat.sas Nuclear One P. O.

Box 608 Russellville, Arkansas 72801 L. Alexander, QC Supervisor Q> {f].

C 790'72603 17

UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D. C.

20555 IE Information Notice No. 79-19 Date: July 17, 1979 Page 1 of 2 PIPE CRACKS IN STAGNANT BORATED WATER SYSTEMS AT PWR PLAh"fS Description of Circumstances:

During the period of November 1974 to February 1977 a number of cracking incidents have been experienced in safcty-related stainless steel piping systems and portions of systems which contain oxygenated, stagnant or essentially stagnant borated 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. surface and propagating in either an intergranular 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 One 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 IE Circular 76-06 (copy attached) in view of the apparent generic nature of the problem.

During the refueling outage of Three Mile Island Unit I which began in February of this year, visual inspections disclosed five (5) through-wall cracks at welds in the spent fuel cooling system piping and one (1) at a weld in the decay heat removal system. These cracks were found as a result of local boric acid build-up and later confirmed by liquid penetrant tests. This initial identification of cracking was reported to the NRC in a Licensee Event Report (LER) dated May 16, 1979.

A preliminary metallurgical analysis was performed by the licensee on a section of cracked and leaking weld joint from the spent fuel cooling system.

The conclusion of this analysis was that cracking was due to Intergranular Stress Corrosion Cracking (IGSCC) originating on the pipe I.D.

The cracking was localized to the heat affected zone where the type 304 stainless steel is sensitized (precipitated carbides) during welding.

In addition to the main through-wall crack, incipient cracks were observed at several locations in the weld heat affected cone including the weld root fusion area where a miniscule lack of fusion had occurred. The stresses respont' le for cracking are believed to be primarily residual welding stresses inasmuch s the calculated applied stresses were found to be less than code design limits.

There is no conclusive evidence at this time to identify those aggressive chemical species which promoted this IGSCC attack.

Further an 7 " ~ ~

~

- - ~"

w%-

other system welds are being pursued.

jDUPLICATE DOCUMENT

,; Entire document previously entered ainto system under:

7907230/64 L20110 l

ANO No. of pages:

%em; IMJ G

l/ m y

,