ML18082A965
| ML18082A965 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 08/07/1980 |
| From: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Schneider F Public Service Enterprise Group |
| References | |
| NUDOCS 8008260426 | |
| Download: ML18082A965 (3) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 631 PARK AVENUE KING OF PRUSSIA, PENNSYLVANIA 19406.
Docket No. 50-272 50-311 Public Service Electric and Gas Company ATTN:
Mr. F. W. Schneider Vice President -* Production 80 Park Place
- Newark, New Jersey 07101 Gentlemen:
August 7, 1980 The enclosed IE Information Notice No. 80-29/'Broken Studs on Terry Turbine Steam Inlet Flange, 11 is forwarded to you for information.
No written response is required.
If you desire additional foformation regarding this matter, please contact this office.
Sincerely, k:.~~
Director*
Enclosures:
- 1.
IE Information Notice No. 80-29
- 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*
ENCLOSURE.1 UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION*AND ENFORCEMENT
, WASHINGTON, 0. C.
20555 SSINS No.: 6835 Accession No.:
8006190028 IE Information Notice No. 80-29 Date:
August 7, 1980 Page 1 of 1 BROKEN STUDS ON TERRY TURBINE STEAM INLET FLANGE When removing the governor and stop valve on the Unit 1 steam driven emergency feedwater pump at Arkansas Nuclear One for repair of a steam leak at the steam inlet flange, Arkansas Power and Light discovered that five of the eight studs securing the flange were broken.
The cause of the stud failure is unknown at this time.
Metallurgical evalua-tion of the failed bolting will be performed to identify the mode of failure.
The failed studs are 3/4 in.. diameter by 3-112 in.
long and are thought to be of ASTM-A-193 grade 87 steel.
The turbine flange bolting is generally covered with insulation and not visible for inspection.
From the information available, the bolting has not been removed or inspected since installation seven to eight years ago.
The steam driven emergency feedwater pump turbine at AN0-1 is a type G turbine manufactured by the Terry Steam Turbine Company of Hartford, Connecticut.
The turbine is rated at 680 BHP and 3560 RPM.
The turbine operates at a reduced steam pressure of 270 psig and temperature of 400°F and has previously experienced overspeed trips arid vibrations which may have been caused by slugs of water from the piping.
Licensees are encouraged to carefully examine insulat:ion in the flange to turbine casing region for evidence of leakage and consider inspection of the turbine steam inlet flange bolting.
Further, during surveillance testing, care should be taken to observe if abnormal vibration or other translents occur which could promote loss of bolting integrity.
- This Information Notice is provided a*s 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 the-ir 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 August 7, 1980 Information Notice No.
Supplement to 80-06 80-28 ao-21 80-26 80-25 80-24 80-23 80-22 80-21 80-20
. RECENTLY ISSUED IE INFORMATION NOTICES Subject
- Date Issued Notification of 7/29/80 Significant Events at Operating Power Reactor Facilities Prompt Reporting Of 6/13/80 Required Information To NRC Degradation of Reactor 6/11/80 Coolant Pump Studs Evaluation of Contractor
- 6/10/80 QA Programs Transportation of 5/30/80 Pyrophori'c Uranium Low Level Radioactive 5/30/80 Waste Burial Criteria Loss of Suction 5/29/80 to Emergency Feedwater Pumps Breakdown In Contamina-5/28/80 tion Control Programs Anchorage and Support of 5/16/80 Safety-Related Electrical Equipment Loss of Decay Heat 5/8/80 Removal Capability at Davis-Besse Unit 1 While in a Refueling Mode Enclosure *2 Issued To All holders of power reactor Ols and near term OL applicants All applicants for and holders of power reactor construction permits
- All holders of pressurized water power reactor Ols or CPs All holders of a Part 50 License Material Licensees in Priority/Categories, II-A, II-0, III-I and IV-DI; Agreement State Licensees in equivalent categories
.All holders of an NRC or NRC Agreement State License All holders of power reactor Ols or CPs All holders of power reactor OLs and near term OL applicants All holders of power reactor OLs or CPs All holders of power reactor Ols or CPs