ML18081A872
| ML18081A872 | |
| Person / Time | |
|---|---|
| Site: | Salem, Hope Creek  |
| Issue date: | 12/27/1979 |
| From: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Martin T Public Service Enterprise Group |
| References | |
| NUDOCS 8001080666 | |
| Download: ML18081A872 (3) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION
. REGION I 631 PARK AVENUE KING OF PRUS~IA, PENNSYLVANIA 19406
. Docket Nos. 50-354 50-'"-3.5_5~
- C*
50-31'1 *~,)
-~*
OEG 2 7 1979 Public Se.rvice Electric & Gas Company ATIN:
Mr~ T. J. Martin
- Vice President Engineering and Construction 80 Park Place Newark,, New Jersey 07101 Gent l emeri :.
This Infbrmation Notice is provided ~s 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 acti6ns.
.. If you have questions. regarding this matter, please contact this office.
Sincerely, Grier
Enclosures:
L IE Info.rmation.Notice No. 79-34
- 2.
List of Recently Issued IE Information Ndtices CONTACT:
L E. Tripp (215-337-5282) cc w/encls:
E. N. Schwalje, Manager - Quality Assurance, Engineering and Construction Department
ENCLOSURE 1 UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION ANO ENFORCEMENT WASHINGTON, O.C.
20555 SSINS No.:
6870 Accession No. :
7910250517 IE Information Not.ice 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 c:iefects 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 exchanger~ 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. tne 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 11 stake 11 (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:
Manf acturer:
Type:
Size:
Serials:
Industrial Process Engineers, Inc.
CFU (Special) 55-342 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.
~_,-...
Information Notice No. 79-25 79-26
.79-12A 79-27 79-28 79-29 79-30 79-31
- 79-32 79-33 ENCLOSURE 2 IE Information Notice No. 79-34 Date:
December 27, 1979 Page 1 of 1 RECENTLY ISSUED IE INFORMATION NOTICES Subject.
Reactor Trips at Turkey Point Unit 3 and 4 Breach of Containment Integrity Attempted Damage to New Fuel Assemblies Date Issued to Issued 10/1/79 All Power Reactor Faci-lities with an Operating License (OL) or Construc-tion Permit (CP) 11/5/79 All Power Reactor Facil-ities with an OL or CP 11/9/79 All Fuel Facilities, Research Reactors and Power Reactors with an OL or CP Steam Generator Tube 11/16/79 All Power Reactor Faci-Ruptures at Two PWR 1 iti.es with an OL or CP Facilities Overloading of Structural 11/16/79 All Power Reactor Faci-Elements Due to Pipe Support lities with an OL or CP Loads Loss of Nonsafety Related 11/19/79 All Power Reactor Faci-Reactor Coolant System In-lities with an OL or CP strumentation During Operation Reporting of Defects and N~ncompliances, 10 CFR Part 21 Use of.Incorrect Amplified Response Spectra (ARS)
- 12/6/79 All Power Reactor Faci-lities with an OL or CP 12/13/79 All Power Reactor Faci-lities with an OL or CP Separation of Electrical 12/21/79 All Power Reactor Faci-Cables for HPCI and ADS lities with an OL or CP Improper Closure of Primary 12/21/79 A 11 Power Reactor Faci-Contai nment Access Hatches lities with an OL or CP
_I_