ML19262B880
| ML19262B880 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 12/27/1979 |
| From: | Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | Cavanaugh W ARKANSAS POWER & LIGHT CO. |
| References | |
| NUDOCS 8001160002 | |
| Download: ML19262B880 (1) | |
Text
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CEtiTRAL FILES UNITED STATES
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NUCLEAR REGULATORY COMMISSION PDR:HQ
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REcloN IV LPDR 7 ( s,*, '
,1 611 RY AN PLAZA DRIVE,5UITE 1000 mily 0
ARLINGTON, TEXAS 76012
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December 27, 1979 Docket Nos.
50-313 50-368 Arkansas Power and Light Company ATTN:
Mr. William C vanaugh III Vice President of Generation and Construction P. O. Box 551 Little Rock, Arkansas 72203 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, Karl V. Seyfrit /j f
Director
Enclosures:
1.
IE Information Notice No. 79-34 2.
List of Recently Issued IE Information Notices cc:
James P. O'Hanlon, Plant Manager Arkansas Nuclear One P. O. Box 606 Russellville, Arkansas 72801 1754 224 8 0 01 l eo 001
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 DCSIGN 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 Containmc.nt 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) h. eat 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 respocse to this Information Notice is required.
If you have any questions regarding this matter please contact the Director of the appropriate NRC Regional Office.
(754 225
IE Information Notice No. 79-34 December 27, 1979 LISTING OF RECENTLY ISSUED IE INFORMATION NOTICES Info rmation 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 (0L) 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 s
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