ML19257A803
| ML19257A803 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 12/27/1979 |
| From: | Engelken R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | Goodwin C PORTLAND GENERAL ELECTRIC CO. |
| References | |
| NUDOCS 8001080608 | |
| Download: ML19257A803 (1) | |
Text
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v UNITED STATES
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NUCLEAR REGULATORY COMP."lSSION C
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.I REGION V 0, -
a 1990 N. CALIFORNI A BOULEVARD
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SUITE 202, WALNUT CREEK PLAZA
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WALNUT CREE K, CALIFORNI A 94596 December 27, 1979 Docket No. 50-344 Portland General Electric Campany 121 S. W. Salmon Street Portland, Oregon 97204 Attention: Mr. Charles Goodwin, Jr.
Assistant Vice President 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 questions regarding this matter, please contact the Director of the appropriate NRC Regional Office.
Sincerely, mLEh~
R. H. Engelken Director
Enclosures:
1.
IE Information Notice No. 79-34 2.
List of Recently Issued IE Information Notices cc w/ enclosures:
C. P. Yundt, PGE F. C. Gaidos, PGE 1705 029 b
8001080
s UtlITED STATES SSIflS f!o. :
6870 flUCLEAR REGULATORY COM!ilSSION Accession f!o.:
0FFICE OF IflSPECTION Afl0 E!!FORCEf1ENT 7910250517 WASHI*iGT0ft, D.C.
20555 Decenber 27, 1979 IE Infornation flotice flo. 79-34 INADEQUATE DESIG'l 0F SAFETY-RELATED HEAT EXCHAf;GERS Tennessee Valley Authority (TVA) submitted an initial 50.55(e) report on October 25, 1979, that identified defects in the four Containnent 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 reductier.c in wall thickness and some tube leakage. The CS heat exchancers at Sequoyah had only been in operation for a short period of tine prior tu 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 ninor 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 danage.
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 flotice is provided as an early notification of a possibly signi-ficiant matter that is still under review by the f!RC staff.
It is expected that recipients will review the infornation for possible applicability to their facilities. No specific action or response is requested at this time.
If NRC evaluations so indicate, further licensee actiors may be requested or required.
No written response to this Information flotice is required.
If you have any questions regarding this matter please contact the Director of tha appropriate NP,C Regional Office.
1705 030
d 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 CP; 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 1705 031