ML18085A451

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Forwards Suppl 1 to IE Info Notice 80-29, Broken Studs on Terry Turbine Steam Inlet Flange. No Written Response Required
ML18085A451
Person / Time
Site: Salem  
Issue date: 11/26/1980
From: Grier B
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To: Maier J
Public Service Enterprise Group
References
NUDOCS 8101070418
Download: ML18085A451 (3)


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 631 PARK AVENUE KING OF PRUSSIA, PENNSYLVANIA 19406.

Docket Nos. 50-272 50-311 Public Service Electric and Gas Company ATTN:

Mr. F. W. Schneider Vice President - Production 80 Park Plaza - lSA Newark, New Jersey 07101

.Gentlemen:

November 26, 1980 r!er; ;r;;£ I~ f.u The enclosed IE Information Notice No. 80-29, 11Broken Studs on Terry Turbine Steam Inlet Flange, 11 Supplement No. 1, is forwarded to you for information.

No written response is required.

If you desire additional information regarding this matter, please contact this office.

Sincerely, Grier

Enclosures:

1.

IE Information Notice No. 80-29, Supplement No. 1

2.

List of Recently Issued IE Information Notices CONTACT:

0. L. Caphton (215-337-5266) cc w/encls:

F.. P. Librizzi, General Manager - Electric Production E. N. Schwalje, Manager - Quality Assurance R. L. Mittl, General Manager - Licensing and Environment H. J. Midura, Manager - Salem Generating Station R. A. Uderitz, General Manager - Fuel Supply Department

\\.*..,.

/

.e UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.

20555 November 26, *1980

~SIN~ No.:

6835 Accession No.:

8006190028 IN 80-29 Supplement N.o. 1 IE Information Notice No. 80-29 (Supplement No. 1):

BROKEN STUDS ON TERRY TURBINE STEAM INLET FLANGE Description of Circumstances:

In the original Information Notice the failed Terry Turbine steam inlet flange studs were identified as probably manufactured from ASTM-A193-Grade B7 steel.

Subsequently, the vendor has informed the NRC that the bolting material used at AN0-1 was AISI C-1117 steel.

Independent laboratory analyses by the NRC and Arkansas Power and Light have verified that the bolting material was a re-sulphurized, re-phosphorized cold drawn carbon steel.

From the analysis performed, the 'failure was caused by high overload which resulted in a primarily brittle transgranular fracture (cleavage) in probably less than 10 cycles. This is consistent with.the operating experience (water slugging) and the inherent low toughness of the bolting material used.

Licensees are encouraged to review the materials selected for safety-related bolting applications considering especially those situations where impact loadings could occur.

The use of low toughness carbon steel (re-sulphurized free machining plain carbon steel) for bolting is discouraged by the NRC; particularly in situations where possible high loading conditions could be anticipated.

This Information Notice is provided as an early notification of a possibly significant matter that is still under review by the NRC staff. It is expected that recipients will review the information for possible applicability to their facility.

No specific action or response is requested at this time.

If you have any questions regarding this matter, please contact the Director of the appropriate NRC Regional Office.

IE Information Notice No. 80-29, Supplement No. 1 November 26, 1980 Information Notice No. 80-41 80-40 80-39 80-38 80-37 80-36 80-35 80-34 80-33 RECENTLY ISSUED IE INFORMATION NOTICES Subject Date Issued Failure of Swing theck 11/10/80 Valve in the Decay Heat Removal System at Davis-Besse Unit No. 1 Excessive Nitrogen 11/6/80 Supply Pressure Activates Safety-Relief Valve Operation to Cause Reactor Depressurization Malfunctions of 10/31/80 Solenoid Valves Manufactured by Valcor Engineering Corporation Cracking in Charging 10/30/80 Pump Casing Cladding Containment Cooler 10/24/80 Leaks and Reactor Cavity Flooding at Indian Point Unit 2 Failure of Steam 10/10/80 Generator Support Bolting Leaking and Dislodged 10/10/80 Iodine-125 Implant Seeds Boron Dilution of 9/26/80 Reactor Coolant During Steam Generator Decontamination Determination of 9/15/80 Teletherapy Timer Accuracy Issued.to All holders of a power reactor OL or CP All holders of a power reactor OL or CP All holders of a power reactor OL or CP All holders of a PWR power reactor OL or CP All holders of a power reactor OL or CP All holders of a power reactor OL or CP All holders of a Category G or Gl Medical License All holders of a PWR Power Reactor OL All holders of a teletherapy license