ML19256E754
| ML19256E754 | |
| Person / Time | |
|---|---|
| Site: | Brunswick, Harris  |
| Issue date: | 10/29/1979 |
| From: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Jackie Jones CAROLINA POWER & LIGHT CO. |
| References | |
| NUDOCS 7911150142 | |
| Download: ML19256E754 (2) | |
Text
'o UNITED STATES b
8 NUCLEAR REGULATORY COMMISSION o
.E REGION 11
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\\ ***** o #
101 MARIETTA ST., N.W., SulTE 3100 ATLANTA, GEORGIA 30303 OCT 2 91979 In Reply Refer To:
RII:JPO 50-325, 50-324 50-400, 50-401 50-402, 50-403 Carolina Power and Light Company Attn:
J. A. Jones, Senior Executive Vice President and Chief Operating Officer 411 Fayetteville Street Raleigh, North Carolina 27602 Gentlemen:
The enclosed Bulletin No. 79-17, Revision 1 is forwarded to you for information. No written response is required.
However, the potential corrosion behavior of safety-related systems as it regards your plant over the long-term should be taken into consideration.
If you derire additional information concerning this matter, please contact this office.
Sincerely,
(*
James P. O'Reilly Director
Enclosure:
IE Bulletin No. 79-17, Revision I w/encls.
N 1337 006 l
7911150
OCT S 9137; Carolina Power and Light Company -
cc w/o ic1:
A. C. Tollison, Jr.
Plant Manager Box 458 Southport, North Ca;olina 28461 R. Parsons, Site Manager Post Office Box 101 New Hill, North Carolina 27562 1337 007
UNITED STATES SSINS No.:
6820 NUCLEAR REGULATORY COMMISSION Accession No.:
OFFICE OF INSPECTION AND ENFORCEMENT 7908220137 WASHINGTON, D.C.
20555 3
October 29, 1979 IE Bulletin No. 79-17 Revision 1 PIPE CRACKS IN STAGNANT BORATED WATER SYSTEMS AT PWR PLANTS P
Description of Circumstances:
IE Bulletin No. 79-17, issued July 26, 1979, provided information on the cracking R1 experiented to date in safety-related stainless steel piping systems at PWR R1 plants. Certain actions were required of all PWR facilities with an operating R1 license within a specifiec' 90-day time frame.
R1 After several discussions with licensee owner group representatives and inspection R1 agencies, it has been determined that the requirements of Item 2, particularly R1 the ultrasonic examination, may be impractical because of unavailability of R1 qualified personnel in certain cases to complete the inspections within the time R1 specified by the Bulletin. To alleviate this situation and allow liccusees the R1 resources of improved ultrasonic inspection capabilities, a time extension and R1 clarifications to the bulletin have been made. These are referenced to the R1 affected items of the original bulletin.
R1 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 bor-ated water. Metallurgical investigations revealed these cracks occurred in the weld heat affected zone of 8 _nch to 10-inch type 304 material (schedule 10 an1 40), initiating on the piping I.D. surface and propagating in either an inter-granular or transgranular mode typical of Stress Corrosion Crdking. Anslysis
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indicated the prcoable 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 Suery Units 1 and 2.
The NEC issued Circular No. 76-06 (copy enclosed) in view of the apparent generic nature of the problem.
Durite the refueling outage of Three Mile Island Unit I which began in February of thi 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 sere found as a result of local boric acid buildup 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 the section of cracked and leaking weld join DUPLICATE DOCUMENT R1 - Identifies those additions or revis Entire document previously entered into system under:
ANO 1337 008
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