ML17053B311
| ML17053B311 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 12/27/1979 |
| From: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Rhode G NIAGARA MOHAWK POWER CORP. |
| References | |
| NUDOCS 8001080652 | |
| Download: ML17053B311 (6) | |
Text
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Docket No. 50-410 UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 631 PARK AVENUE KING OF PRUSSIA, PENNSYLVANIA19406
.DEC 2 7 1979 Niagara Mohawk Power Corporation ATTN:
Mr.
G.
K.
Rhode Vice President System Project Management 300 Erie Boulevard, West
- Syracuse, New York.
13202 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 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, oyce H. Grier rector
Enclosures:
1.
IE Information Notice No. 79-34 2.
List of'ecently Issued IE Information Notices CONTACT:
L.
E. Tripp (215-337-5282) cc w/encls:
Eugene B. Thomas, Jr.,
Esquire
]to/f 8 0 0 1 08 6
'ig6 Z.
- 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 age 1 of 1 p
INADEQUATE DESIGN OF SAFETY-RELATED HEAT EXCHANGERS 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 dama'ge.
Further corrective action is under review by the licensee.
The following data applies to the CS 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.
Manfacturer:
Type:
Size:
Serials:
Industrial Process Engineers, Inc.
CFU (Special) 55-342 6662"1; 6662-2 6663-1; 6663-2 I
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.
ENCLOSURE 2 0
IE Information Notice No. 79-34 Date:
December 27, 1979 Page l of 1 RECENTLY ISSUED IE INFORMATION NOTICES Informati on Notice No.
79-25 79-26
.79-12A 79"27 Subject Reactor Trips at Turkey Point Unit 3 and 4 Breach of Containment Integrity Attempted Damage to New Fuel Assemblies Steam Generator Tube Ruptures at Two PMR Facilities Date Issued 10/1/79 11/5/79 11/9/79 11/16/79 Issued to All Power Reactor Faci-lities with an Operating License (OL) or Construc-tion Permit (CP)
All Power Reactor Facil-ities with an OL or CP All Fuel Facilities, Research Reactors and Power Reactors with an OL or CP All Power Reactor Faci-lities with an OL or CP 79"28 Overloading of Structural ll/16/79 Elements Due to Pipe Support Loads All Power Reactor Faci-lities with an OL or CP 79"29 Loss of Nonsafety Related ll/19/79 All Power Reactor Faci-Reactor Coolant System In-lities with an OL or CP strumentation During Operation 79"30 Reporting af Defects and Noncompliances, 10 CFR Part 21
'2/6/79 All Power Reactor Faci-lities with an OL 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 79-33 Separation of Electrical 12/21/79 Cables for HPCI and ADS Improper Closure of Primary 12/21/79 Containment Access Hatches All Power Reactor Faci-lities with an OL or CP All Power Reactor Faci-lities with an OL or CP
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