ML20032C647
| ML20032C647 | |
| Person / Time | |
|---|---|
| Site: | Yellow Creek  |
| Issue date: | 11/04/1981 |
| From: | Mills L TENNESSEE VALLEY AUTHORITY |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| REF-PT21-81 10CFR-050.55E, 10CFR-50.55E, NUDOCS 8111100686 | |
| Download: ML20032C647 (2) | |
Text
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'I TENNESSEE VALLEY AUTHORl] fMRC s
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CH ATTANOOGA, TENNESSEE 37401 400 Chestnut Street Tower II
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November 4, 1981 a 0. p YCRD-50-566/81-06 m
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S-tioyo IbO I b -11 Mr. James P. O'Reilly, Director Office of Inspection and Enforcement M*grou Q 9
U.S. Nuclear Regulatory Commission p
l Region II - Suite 3100 b
i 101 Marietta Street
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Atlanta, Georgia 30303
Dear Mr. O'Reilly:
YELLOW CREEK NUCLEAR PLANT UNITS 1 AND 2 - DEFICIENT WELDS ON COMPONENT COOLING WATER HEAT EXCHANGERS - YCRD-50-566/81-06, YCRD-50-567/81 REVISED FINAL REPORT The subject deficiency was initially reported to NRC-0IE Inspector J. Crlenjak on March 6,1981, in accordance with 10 CFR 50.55(e) as NCR YC-160. This was followed by our first interim report dated April 7,1981 and our final report dated October 6,1981. As discussed with R. V. Celenjak on October 28, 1981, enclosed is our revised final report. This revision is necessary to clarify the report's corrective action section. We consider 10 CFR Part 21 to be applicable to this deficiency.
If you have any questions concerning this matter, please get in touch with R. H. Shell at FTS 858-2688.
1 Very truly yours, TENNESSEE VALLEY AUTHORITY i
L. M. Mills, ager Nuclear Regulation and Safety Enclosure cc:
Mr. Victor Stello, Jr., Director (Enclosure)
Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, DC 20555 1121 8111100686 811104 PDR ADOCK 05000566 OMg S
PDR Te An Equal Opportunity Employer
m ENCLOSURE YELLOW CREEK NUCLEAR PLANT UNITS 1 AND 2 DEFICIEE WELDS ON COMPONENT COOLING WATER HEAT EXCHANGERS YCRD-50-566/81-06, YCRD-50-567/81-04 10 CFR 50.55(e)
REVISED FINAL REPORT Description of Deficiency During an NRC inspection of the component cooling water heat exchangers at 3
the Yellow Creek Nuclear Plant, it was reported that various welding deficiencies existed on the welds and base metal for the 24" stainless steel nozzles and manhole to exchanger welds. The various deficiencies noted were arc strikes, weld splatter, slag, overlap, lack of fusion, undercut and excessive weld metal. The component cooling water heat exchangers were manufactured by the Joseph Oat Corporation, Camden, New Jersey, and purchased by TVA from Combustion Engineering, Windsor, Connecticut.
Safety Implications The Component Cooling System (CCS) is designed to remove heat from the reactor auxiliary components and ' engineered safety features components to the Essential Raw Cooling Water System. The component cooling water heat exchangers represent an important part of the CCS. Failure or partial failure of these heat exchangers would decrease the efficiency and effectiveness of the CCS, thus affecting the proper operation of auxiliary as well as Engineered Safety Feature (ESP) system components.
Corrective Action On March 19, 1931, a field inspection was conducted of the component cooling water heat exchangers. The areas reported as having deficient welds were inspected by members of TVA, the Authorized Nuclear Inspector, and the representatives of the Combustion Engineering Company and the Joseph Oat Company.
Cracks or other linear indications (lack of fusion) rejected by visual examination shall be proven acceptable by liquid penetrant or magnetic partical examination after excavation. The defects appear to be confined to the surface and will be removed by grinding. After grinding, a visual examination of the weld will be performed.
If there are no cracks or indications evaluated as being linear (for example, lack of fusion), no liquid penetrant or magnetic particle testing will follow. However, if linear indications are visually detected, a liquid penetrant or magnetic particle examination will be performed and the welds reworked as necessary.
At this time there is no evidence that extensive (base metal) repairs will be necessary. However, if any base metal indications are discovered they will be handled as appropriate under 10 CFR 50.55(e).
All action on this item will be completed by January 8, 1982.
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