ML19254F381
| ML19254F381 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse, Arkansas Nuclear, Crystal River, Rancho Seco  |
| Issue date: | 10/03/1979 |
| From: | Stewart W FLORIDA POWER CORP. |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| Shared Package | |
| ML19254F382 | List: |
| References | |
| IEB-79-17, NUDOCS 7911090141 | |
| Download: ML19254F381 (2) | |
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Rodda Power C O R PO m A T SO se October 3, 1979 File:
3-0-3-a-3 Mr. J. P. O'Reilly Director U.S. Nuclear Regulatory Commission Office of Inspection & Enforcement Suite 3100 101 Marietta Street Atlanta, Ga 30303 Subjecti Crystal River Unit 3 Docket No. 50-302 Operating License No. DPR-72 I.E.Bulletin 79-17
Dear Mr. O'Reilly:
On September 5,1979, the Babcock & Wilcox (B&W) Owners Group Subec. 'mittee on Pipe Cracking, submitted to Mr. Norman C. Mosley a formal request for a 90-day extension of the implementation of Item 2 of IE Bulletin 79-17.
The utilities on whose behalf this request was made were Florida Power Corporation, Arkansas Power & Light, Toledo Edison, and Sacramento Municipal Utility District. A copy of this request is enclosed for your information.
As stated in the September 5, 1979 letter, recent data obtained from Three Mile Island Unit 1 indicates that the extent of Intergranular Stress Corrosion Cracking (IGSCC) experienced at that facility in 304 stainless steel piping is much more limited than it was originally thought to be.
Of 1902 welds inspected originally, 350 contained indications.
These 350 welds have been reinspected with a procedure which better discriminates between actual cracks and geometrical reflectors. Many of the 350 welds (including those in High Pressure Injection and Decay Heat Drop Line) have been shown to contain only geometric reflectors.
It is now estimated that approximately 30 welds of the 1902 welds inspected will be shown to contain IGSCC.
- It was the uncertainty and changing nature and scope of the IGSCC data base at Three Mile Island I that prompted our request for the 90-day extension for the implementation of Item 2 of I.E.Bulletin 79-17.
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. J. P. O'Reilly Page 2 October 3, 1979 In our September 5th request, we identified several technical and procedural items which needed clarification and identified six (6) activities that Florida Power Corporation and the members of the B&W Owners Group plan to pursue during the extension period in order to identify the cause of cracking and to itemize and standardize the inspection processes.
(See attached September 5,1979 letter for details.)
This letter is to reiterate Florida Power Corporation's support of the September 5,1979 request for the '0-day extension and to identify our commitment to.evelop a sound prcgram and procedures d ring this time which are based on an evaluation of all available data.
Your prompt consideration and reply to this matter will be greatly appreciated in order that a sound inspection program can be developed and implemented at CRf 3.
If you have any questions, please contact this office.
Very truly yours, FLORIDA POWER CORPORATION r 4 " /p a
W. P.
tewart Manager, Nuclear Operations WPSemhWO2 D77 1309 264 I
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