ML20009C544
| ML20009C544 | |
| Person / Time | |
|---|---|
| Site: | Cherokee |
| Issue date: | 07/14/1981 |
| From: | Dail L DUKE POWER CO. |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| 10CFR-050.55E, 10CFR-50.55E, IE-81-01-5PS-49, IE-81-1-5PS-49, NUDOCS 8107210216 | |
| Download: ML20009C544 (2) | |
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UFFICIAL copy DUH ic POWEH COMPANY p.oaosast" liMNEltAL OFFI('ES sis.co 422 SOUTH CHURCN $IRI(I CliJ nLo1TI:. N. C. 2H242
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July 14, 1981 Qq
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TOR DEP L
y Ojpg Mr. J. P. O'Reilly, Director
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^NT TO 0; RECTOR DIR C'
I U. S. Nuclear Regulatory Com liss oni
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D'R 101 Marietta Street, suite 3' 00 ENF/INV
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4 Atlanta, GA 30303 D;R CTO ' g PURLIC AFFA!RS oppuq Re: Cherokee Nuclear Statio I, Unit 1 Docket No. S0-491 IE 81/01-SPS-491 flSSS. Shutdown Heat Exch inger Duke Files: P81-1201.0 1, P81-1201.06
Dear Mr. O'Reilly:
Attached is Duke's progress eport on the r'aferencei 10CFR 50.55(e) reportable item. Another report will b e submitted by October 1, 1981 Initial notification was made by telephone to Mr. Rausch of your office on December 17, 1980.
An interim report was submitted to your office on January 15, 1981, Very truly yours,
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(
L. C. Dail Vice-President Design Engineering Departmer t GDR/pam Attachment cc: Director of Inspection & Enforcement U. S. Nuclear Regulatoi y Comission 3gy)
Washington, DC 20S55 s
/I 8107210216 810714 PDR ADOCK 05000491 S
PDR I
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DUKE POWER CO.
CHEROKEE NUCLEAR STATION Report Number:
IE 81/01-5PS 491, (Progress Report)
Report Date:
January 15,1911 (initial)
Facility: Cherokee Nuclear itation - Unit #1 Re_ statement of DefIclency:
Apparent breakdowns in manuf icturing, cleaning, and Inspection processes on Shutdown Heat Exchangers (SDIX's)
Description of Deficien_cy:
On December 17, 1980, Mr. R. E. Miller and Mr. W. H. Bradley Informed Mr. John Rausch, NRC of potential def ciencies in the Shutdown Heat Exchangers, supplied by Combustion Engineering as part of the NSSS contract, along the following lines.
1.
Due to problems enci>untered on the WPPSS Unit #3 SDHX, and since the Duke SDHX's were maliufactured by the same vendor (Ametek), CE advised Duke that heat excN ngers were suspect of similar deficiencies.
2.
Duke Unit #1 SDHX's were inspected at the site, and were found to have problems with he stainless steel cladding and contamination of tube side material : urfaces.
Analysis of Safety implicatlins:
Refer to initial report.
Upda_te on Corrective Actions Duke removed the Unit lA and IB SDHX's from the Reactor Building, and returned them to the original supplici for examination and repair.
Results of the examina-tion of the SDHX's are as fo lows:
Unit IA:
(1)
Unacceptable haidness readings and cracking will equire reciadding of the tube shes t, tubesheet to channel weld, and channel cover.
Acceptable clad thickness wlit be verified by ultrasonic inspection (UT).
(2) Minor unacceptat le PT indications lie arear not to be reciad will be corrected anc re-PT'd.
(3)
Complete retubir g will be required due to recladding of the tube sheet.
New tubing will be eddy current tested (ET) per revised CE procedure to assure no unacceptable defects.
(4)
Reworked heat e> changers will be cleaned, dried, and inspected following hydrot est to assure absence of surfac'e contamination.
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