ML19257A807
| ML19257A807 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 12/27/1979 |
| From: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Lundvall A BALTIMORE GAS & ELECTRIC CO. |
| References | |
| NUDOCS 8001080624 | |
| Download: ML19257A807 (1) | |
Text
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NUCLEAR REGULATORY COMMISSION
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Kit ', OF PRUSSIA, PENNSYLVANIA 19406 Docket Nos. 50-317 50-318 DEC 2 71979 Baltimore Gas and Electric Company ATTN:
Mr. A. E. Lundvall, Jr.
Vice President, Supply P. O. Box 1475 Baltimore, Maryland 21203 Gentlemen:
This Information Notica 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 Cir-cular or Bulletin will be issued to recommend or request specific licensee actions.
If you have questions regarding this matter, please contact this office.
Sincerely, sM7. $#a~
oyce H. Grier ector
Enclosures:
1.
IE Information Notice No. 79-34 2.
List of Recently Issued IE Information Notices CONTACT:
L. E. Tripp (215-337-5282) cc w/encls:
R. M. Douglass, Manager, Quality Assurance L. B. Russell, Chief Engineer W. Cibson, General Supervisor, Operational QA R. C. L. Olson, Senior Engineer K. H. Sebra, Principal Engineer 1705 044 8001080 $1
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ENCLOSURE 1 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 tt.be 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.
1705 045
ENCLOSURE 2 IE Information Notice No. 79-34 Date:
December 27, 1979 Page 1 of 1 RECENTLY ISSUED IE INFORMATION NOTICES Information Subject Date Issued to Notice No.
Issued 79-25 Reactor Trips at Turkey 10/1/79 All Power Reactor Faci-Point Unit 3 and 4 lities with an Operating License (OL) or Construc-tion Permit (CP) 79-26 Breach of Containment 11/5/79 All Power Reactor Facil-Integrity ities with an OL or CP 79-12A Attempted Damage to New 11/9/79 All Fuel Facilities, Fuel Assemblies Rcsearch Reactors and
'ower Reactors with an OL oe CP 79-27 Steam Generator Tube 11/16/79 All Power Reactor Faci-Ruptures at Two PWR lities with an OL or CP Facilities 79-28 Overloading of Structural 11/16/79 All Power Reactor Faci-Elements Due to Pipe Support lities with an OL or CP Loads 79-29 Loss of Nonsafety Related 11/19/79 All Power Reactor F;;i-Reactor Coolant System In-lities with an OL or CP strumentation During Operation 79-30 Reporting of Defects and 12/6/79 All Power Reactor Faci-Noncomoliances, 10 CFR lities with an OL Part 21 or CP 79-31 Use of Incorrect Amplified 12/13/79 All Power Reactor Faci-Response Spectra (ARS) lities with an OL or CP 79-32 Separation of Electrical 12/21/79 All Power Reactor Faci-Cables for HPCI and ADS lities with an OL or CP 79-33 Imprcper Closure of Primary 12/21/79 All Power Reactor Faci-Containment Access Hatches lities with an OL or CP 1705 046