ML19353A198
| ML19353A198 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 11/26/1980 |
| From: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Counsil W NORTHEAST NUCLEAR ENERGY CO. |
| References | |
| NUDOCS 8101070425 | |
| Download: ML19353A198 (1) | |
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631 PARK AVENUE KING OF PRUSSIA, PENNSYLVANIA 19406 ve er 26, 1980 Docket Nos. 50-245 50-336 50-423 Northeast Nuclear Energy Company ATTN:
Mr. W. G. Counsil Senior Vice President - Nuclear Engineering and Operations P. O. Box 270 Hartford, Connecticut 06101 Gentlemen:
The enclosed IE Information Notice No. 80-29, " Broken Studs on Terry Turbine Steam Inlet Flange," 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, cm Hl.
(faov 8 yce H. Grier
>irector
Enclosures:
1.
IE Information Notice No. 80-29, Supplement No. 1 2.
List of Recently Issued IE Information Notices CONTACT:
D. L. Caphton (215-337-5266) cc w/encls:
J. F. Opeka, System Superintendent Nuclear Operations E. J. Mroczka, Station Superintendent D. G. Diedrick, Manager of Quality Assurance J. R. Himmelwright, Licensing Safeguards Engineer K. W. Gray, Supervisor of Construction Quality Assurance H. R. Nims, Director of Nuclear Projects 3
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SSINS No.:
6835 Accession No.:
UNITED STATES 8006190028 NUCLEAR REGULATORY COMMISSION IN 80-29 0FFICE OF INSPECTION AND ENFORCEMENT Supplement No. 1 WASHINGTON, D.C.
20555 November 26, 1980 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 prcu 51y manufactured from ASTM-A193-Grade B7 steel.
Subsequently, the vendor has informed the NRC that the bciting material used at ANO-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 providea 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.
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O IE Information Notice No. 80-29, Supplement Na 1 November 26, 1980 RECENTLY ISSUED IE INFORMATION NOTICES Information Subject Date Issued to Notice No.
Issued I!0-41 Failure of Swing Cteck 11/10/80 All holders of Valve in the Decay Heat a power reactor Removal System at OL or CP Davis-Besse Unit No. 1 80-40 Excessive Nitrogen 11/6/80 All holders of Supply Pressure a power reactor OL Activates Safety-Relief or CP Valve Operation to Cause Reactor Depressurization 80-39 Malfunctions of 10/31/80 All holders of a Solenoid Valves power reactor OL or CP Manufactured by Valcor Engineering Corporation 80-38 Cracking in Charging 10/30/80 All holders of Pump Casing Cladding a PWR power reactor OL or CP 80-37 Containment Cooler 10/24/E6 All holders of i Leaks and Reactor power rea: tor,L r
Cavity Flooding at or CP Indian Point Unit 2 80-36 Failure of Steam 10/10/80 All holders of a Generator Support power reactor Bolting OL or CP 80-35 Leaking and Dislodged 10/10/80 All holders of a Iodine-125 Implant Category G or G1 Seeds Medical License 80-34 Boron Dilution of 9/26/80 All holders of a Reactor Coolant During PWR Power Rabator OL Steam Generator Decontamination 80-33 Determination of 9/15/80 All holoers of Teletherapy Timer a teletherapy Accuracy license b