ML19211C055
| ML19211C055 | |
| Person / Time | |
|---|---|
| Site: | 05000580, 05000581 |
| Issue date: | 12/27/1979 |
| From: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Mcwhorter R OHIO EDISON CO. |
| References | |
| NUDOCS 8001100018 | |
| Download: ML19211C055 (1) | |
Text
nn arou UNITED STATES o,'n NUCLEAR REGULATORY COMMISSION
.r REGION I!!
k 799 ROOSEVELT ROAD g
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GLEN ELLYN, ILLINOIS 6o137 DEC 2 71979 Docket No. 50-580 Docket No. 50-581 The Ohio Edison Company ATTN:
Mr. R. J. McWhorter Vice President Engineering 76 South Main Street Akron, OH 44308 Gentlemen:
This Information Notice is provided as an early notification of a possibly significant matter.
It is expected that recipients will review the infor-mation for possible applicability to their facilities. No specific action or respense is requested at this time.
If further NRC evaluations so indi-cate, an IE Circular or Bulletin will be issued to recommend or request epecific licensee actions.
If you have questions regarding this matter, please contact the Director of the appropriate NRC Regional Office.
Sincerely, James G. k'[er -
1 Kepp Director Enclorure:
IE Information Notice No. 79-34 cc w/ encl:
Central Files Director, NRR/DPM Director, NRR/ DOR 1739 OM PDR Local PDR NSIC TIC Harold W. Kohn, Power Siting Commission 8001100 OTIT
UNITED STATES SSINS No.:
6870 NUCLEAR REGULATORY COMMISSION Accession No.:
0FFICE OF INSPECTION AND ENFORCEMENT 7910250517 WASHINGTON, D.C.
20555 m'
D A
m December 27, 1979 IE Information Notice No. 79-34 INADEQUATE DESIGN OF SAFETY-RELATED HEAT EXCHANGERS Tennessee Valley Authority (TVA) submitted an initial 50.55(e) report on October 25, 1979, that identified defects in the four Containment Spray (CS) heat exchangers at the Sequoyah facility.
The heat exchanger tube bundles were damaged by excessive vibrations of the tubes against each other.
These vibrations were caused by a support arrangement that allows excessive unsupported tube lengths.
The large a plitude tube vibration has resulted in reductier.: in wall thickness and some tube leakage.
The CS heat exchangers at Sequoyah had onl'y been in operation for a short period of time prior to the failure being detected.
These heat exchangers were manufactured by Industrial Process Engineers, Inc.,
(IPE), a vendor now out of business.
The Component Cooling Water (CCW) heat exchangers at the Sequoyah facility were also made by IPE.
TVA has identified some reduction in wall thickness and minor tube leakage in the CCW heat exchangers.
The licensee plans to plug the damaged tubes on the CS heat exchangers and " stake" (support) the tube bundles to prevent further damage.
Further corrective action is under review by the licensee.
The following data applies to the CS heat exchangers:
Manfacturer:
Industrial Process Engineers, Inc.
Type:
CFU (Special)
Size:
55-342 Serials:
6662-1; 6662-2 6663-1; 6663-2 This Information Notice is proviJed as an early notification of a possibly signi-ficiant matter that is still under review by the NRC staff.
It is expected that recipients will review the information for possible applicability to their facilities.
No specific action or response is requested at this time.
If NRC evaluations so indicate, further licensee actions may be requested or required.
No written response to this Information Notice is required.
If you have any questions regarding tnis matter please contact the Director of the appropriate NRC Regional Office.
Enclosure:
List of Recently Issued IE Information Notices 1739 02.9
4 IE Information Notice No. 79-34 Enclosure December 27, 1979 RECENTLY ISSUED IE INFORMATION NOTICES Information Subject Date Issued To Notice No.
Issued 79-33 Improper Closure of 12/21/79 All power reactor facilities Primary Containment holding OLs and cps Access Hatches 79-32 Separation of Electrical 12/21/79 All power reactor facilities Cables for HPCI and ADS holding OLs and cps 79-31 Use of Incorrect Amplified 12/13/79 All holders of power reactor Response Spectra (ARS)
OLs and cps 79-30 Reporting of Defects and 12/6/79 All power reactor facilities Noncompliance, 10 CFR Part 21.
holding OLs and cps and vendors inspected by LCVIP 79-29 Loss of Nonsafety-Related 11/16/79 All power reactor facilities Reactor Coolant System holding OLs or cps Instrumentation During Operation 79-28 Overloading of Structural 11/16/79 All power reactor facilities Elements Due to Pipe Support with an OL or CP Loads 79-27 Steam Ger.erator Tube 11/16/79 All power reactor facilities Ruptures At Two PWR ho Eing OLs and cps Facilities79-12A Attempted Damage To New 11/9/79 All Fuel Facilities, Fuel Assemblies research reactors, and power reactors with an OL or CP 79-26 Breach of Containment 11/5/79 All power reactor facilities Integrity holding OLs and cps 79-25 Reactor Trips At Terkey 10/1/79 All power facilities with Point Units 3 And 4 an OL or a CP 1739 030