ML19291C478
| ML19291C478 | |
| Person / Time | |
|---|---|
| Site: | Perkins, Cherokee  |
| Issue date: | 12/27/1979 |
| From: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Dail L DUKE POWER CO. |
| References | |
| NUDOCS 8001240474 | |
| Download: ML19291C478 (2) | |
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UNITED 5TATES 8'S NUCLEAR REGULATORY COMMISSION T1EMAO_
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,I REGION 11 o
101 M ARIETTA ST N.W.. SUITE 3100 o
ATLANTA, G EORotA 30303 i)QR;.1 In Reply Refer To:
DEC 2 71979 RII:JP0 50-488, 50-489 50-490 M ;
@ ) Q0-493 )
Duke Power Company Attn:
L. C. Dail, Vice President Design Engineering Post Office Box 33189 Charlotte, North Carolina 28242 Gentlemen:
This 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 questior.s regarding this matter, please contact the Director of the appropriate hTC Regional Office.
Sincerely, t
~.3 James P. O'Reilly Director
Enclosures:
1.
IE Information Notice No. 79-3'e 2.
List of Recently Issued IE Information Notices 1794 266 -
8001'240Y2Y
DEC 2 71979 Duke Power Company.
cc w/ encl:
J. T. Moore, Project Manager Post Office Box 422 Gaffney, South Carolina 29340 1794257
UNITED STATES SSINS No.:
6870 NUCLEAR REGULATORY COMMISSION Accession No.:
OFFICE OF INSPECTION AND ENFOCEMEN" 7910250517 WASHINGTON, D.C.
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~ eQ 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) beat 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) beat 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.
Manufacturer:
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 significant 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.
e 1794 2168
IE Information Notice No. 79-34 Enclosure December 27, 1979 6
RECENTLY ISSUED IE INFORMATION NOTICES Information Subj ect Date Issued To Notice No.
Issued 79-34 Inadequate Design of Safety-12/27/79 All holders of power reactor Related Heat Exchangers OLs and cps 79-33 Improper Closure of Primary 12/21/79 All holders of power reactor Containment Equipment Access OLs and cps 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 power reactor facilities Response Spectra (ARS) holding OLs and cps 79-30 Reporting of Defects and 12/6/79 All power reactor facilities Noncompliances, 10 CFR holding OLs and cps and Part 21 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 Generator Tube 11/16/79 All power reactor facilities Ruptures At Two PWR holding 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 Turkey 10/1/79 All power facilities with Point Units 3 And 4 an OL or a CP 79-24 Overpressurization Of 10/1/79 All power reactor facilities Containment Of A PWR Plant with a CP After A Main Steam Line Break 1794 269