ML19296A738
| ML19296A738 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 11/09/1979 |
| From: | William Jones OMAHA PUBLIC POWER DISTRICT |
| To: | Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| References | |
| IEB-79-13, NUDOCS 8002150351 | |
| Download: ML19296A738 (2) | |
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NSIC Or'.aha Public Power District STATE 162? HARNEY OMAHA. NEBRASMA 68102 1
TELEPHONE 536 4000 AREA CODE 402 November 9, 1979 Mr. K. V. Seyfrit, Director U. S. Nuclear Regulatory Co= mission Office of Inspection and Enforcement Region IV 611 Ryan Plaza Drive Suite 1000 Arlington, Texas 76011
Reference:
Docket No. 50-285 IE Bulletin 79-13, Revision 2, October 17, 1979
Dear Mr. Seyfrit:
In response to the above-referenced bulletin, non-destructive testing of certain steam generator nozzle-to-pipin6 velds was per-formed, and piping supports and snubbers associated with the main feedwater system piping were examined, during the Fort Calhoun Station outage which co=menced on October 31, 1979 The results of these examinations are provided by attachment to this letter.
Sincerely,
/;
i W. C. Jones Division Manager Production Operations WCJ/KJM/BJH:jnm Attachment ec:
U. S. Nuclear Regulatory Commission Office of Inspection and Enforcement Division of Reactor Operations Inspection Washington, D. C.
20555 LeBoeuf, Lamb, Leiby & MacRae 1333 New Hampshire Avenue, N. W.
Washington, D. C.
20036 r
8002150
ATfACF2GT Feedvater System Examinations in Response to IE Bulletin 79-13, Revision 2 Item 1.a.
Perform radiographic examination, supplemented by ultrasonic examination as necessary to evaluate indications, of all feedvater nozzle-to-piping velds and of adjacent pipe and nozzle areas (a distance equal to at least two vall thicknesses).
Evaluation shall be in accordance with ASME Section III, Subsection NC, Article NC-5000. Radiography shall be performed to the 2T penetrameter sensitivity level, in lieu of Table NC-5111-1, with systems void of water.
Resconse Radiographic examinations were performed on November 2 and 3, 1979 The radiography was performed on the steam generator nozzle-to-safe end velds and on the safe end-to-piping velds (h velds, total) for a distance of at least two vall thicknesses each side of the velds. The radiography was performed and evalu-ated according to the requirements of IE Bulletin 79-13 as stated in Item 1.a.
The results of the examinations show that no crack-ing or unacceptable code discontinuities exist in the veld loca-tions.
Item 1.b.
If cracking is identified during examination of the nozzle-to-piping veld, all feedvater line velds up to the first piping support or snubber and high stress points in contain=ent shall be volumetrically examined in accordance with 1.a. above. All un-acceptable code discontinuities, other than cracking, shall be subject to repair unless justification for continued operation is provided.
Response
No cracking or unacceptable code discontinuities were found.
Item 1.c.
Perform a visual inspection of feedvater system piping sup-ports and snubbers in containment to verify operability and con-formance to design.
Resconse On November 3, 1979, all main feedvater supports in contain-ment were visually examined. All supports conformed with their original design, with the exception of three. The as-built condi-tien of these three was analyzed and the supports were found to be capable of performing their design function.
Surveillance tests performed in accordance with Technical Specification 3.1h, Shock Suppressors (Snubbers), confirmed the operability of all feedvater piping system snubbers in contain=ent.