ML19262B882
| ML19262B882 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 12/27/1979 |
| From: | Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | Pilant J NEBRASKA PUBLIC POWER DISTRICT |
| References | |
| NUDOCS 8001160005 | |
| Download: ML19262B882 (1) | |
Text
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,8 December 27, 1979 i
Docket No.
50-298 Nebraska Public Power District ATTN:
J. M. Pilant, Director Licensing & Quality Assurance Post Office Box 499 Columbus, Nebraska 68601 Gentlemen:
This IE Information Notice is provided as an early notification of a possibly significant matter.
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 further NRC evaluations so indicate, an IE Circular or Bulletin will be issued to recommend or request specific licensee actions.
If you have questions regarding this matter, please contact the Director of the appropriate NRC Regional Office.
Sincerely, l
r1 V. Seyfrit' Director
Enclosures:
1.
IE Information Notice No. 79-34 2.
List of Recently Issued IE Information Notices cc:
L. C. Lessor, Superintendent Cooper Nuclear Station Post Office Box 98 Brownville, Nebraska 68321 (754 228 8001160 OOE
s UNITED STATES SSINS No.:
6870 NUCLEAR REGULATORY COMMISSION Accession No.:
OFFICE OF INSPECTION AND ENFORCEMENT 7910250517 WASHINGTON, D.C.
20555 IE Information Notice No. 79-34 Date: December 27, 1979 Page 1 of 1 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 amplitude tube vibration has resulted in reductions in wall thickness and some tube leakage. The CS heat exchangers at Sequoyah had only 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 provided 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 this matter please contact the Director of the appropriate NRC Regional Office.
f754 229'
IE Information Notice No. 79-34 December 27, 1979 LISTING OF RECENTLY 1sSUED IE INFORMATION NOTICES Information Subject Date Issued To Notice No.
Issued 79-28 Overloading of Structural 11/16/79 All power reactor facilities Elements Due to Pipe Support with an Operating License (OL) or Construction Permit (CP) 79-29 Loss of NonSafety-Related 11/16/79 All power reactor facilities Reactor Coolant System holding Operating Licenses Instrumentation During (OLs) or Construction Operating Permits (cps) 79-30 Reporting of Defects and 12/6/79 All power reactor Noncompliance, 10 CFR facilities holding Part 21.
Operating Licenses (OLs) and Construction Permits (cps) and vendors inspectors inspected by LCVIP 79-31 Use of Incorrect Amplified 12/13/79 All power reactor Response Spectra (ARS) facilities holding Operating Licenses (OLs) and Construction Permits (cps) 79-32 Separation of Electrical 12/21/79 All power reactor Cables for HPCI and ADS facilities holding Operating Licenses (OL) and Construction Permits (cps) 79-33 Improper Closure of 12/21/79 All power reactor Primary Containment facilities holding Access Hatches Operating Licenses (OL) and Construction Permits (cps)
Enclosure
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