ML19344D942
| ML19344D942 | |
| Person / Time | |
|---|---|
| Site: | Sterling |
| Issue date: | 08/07/1980 |
| From: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Arthur J ROCHESTER GAS & ELECTRIC CORP. |
| References | |
| NUDOCS 8008260414 | |
| Download: ML19344D942 (1) | |
Text
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NUCLEAR REGULATORY COMMISSION
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c 631 PARK AVENUE KING OF PRUSSIA, PENNSYLVANIA 19406 August 7, 1980 Docket No. 50-485 Rochester Gas and Electric Corporation ATTN: Mr. J. E. Arthur Chief Engineer 89 East Avenue Rochester, New York 14649 Gentlemen:
The enclosed IE Information Notice No. 80-29," Broken Studs on Terry Turbine Steam Inlet Flange," is forwarded to you for infor ation.
No written response is required.
If you desire additional information regarding this catter, please contact this office.
Sincerely, Boy e H. Grier Director
Enclosures:
1.
IE Information Notice No. 80-29 2.
List of Recently Issued IE Infor:ation Notices CONTACT:
D. L. Capnton (215-337-5266) cc w/encls:
C. R. Anderson, Manager, QA Lex K. Larson, Esquire N. A. Petrick, Executive Director, SNUPPS Gerald Charnoff, Esquire 8008260%\\i u
1 ENCLOSURE 1 SSINS No.: 6835 UNITED STATES Accession No.:
NUCLEAR REGULATORY COMMISSION 8006190028 0FFICE OF INSPECTION AND ENFORCEMENT WASHINGTCN, D.C.
20555 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 3-1/2 in.
long and are thought to be of ASTM-A-193 grade B7 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 ANO-1 is a type G turbine manufactured by the Terry Steam Turbine Company of Hartford, Connecticut.
The turbine is ratt" 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 and vibrations which may have been caused by slugs of water from the piping.
Licensees are encouraged to carefully examine insulation in the flange to turbine casing region for evidence of leakage and consider inspection of the turbine steam inlet flange bolting.
Further, during careeillance testing, care should be taken to observe if abnormal vibration or rther transients occur which could promote loss of bolting integrity.
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 que:tions regarding this matter, please contact the Director of the appropriate NRC Regional Office.
+.
IE Information Notice No. 80-29 Ecclosure 2 August 7, 1950 RECEhTLY ISSUED IE INFC M TION NOTICES Information Subject Date Issued To Notice No.
Issued Supplement to Notificatica of 7/23/80 All holders of power 80-06 Significant Events at reacter OLs and near Operating Pcwr Reactor ters OL applicants Facilities 80-28 Proept Reporting Of 6/13/80 All a:plicants for and Required Infernatica hciders of pcwer To NRC reacter constructica permits 80-27 Degradatien of Reactor 5/11/50 All he'ders of Coolant Pump Studs pressurized water pcmer reactor OLs or cps 80-25 Evaluation of Contracter 6/10/80 All holders of QA Prograss a Part 50 License 80-25 Transportatica cf 5/30/80 Material Licensees in Pyrophcric Uranius Priority / Categories II-A, II-0, III-I and IV-DI; Agreement State Licensees in equivalent categcries 50-24 Lew Level Radicactive 5/30/50 All holders of an Waste Burial Criteria NRC cr NRC Agreesent State License 80-23 Loss of Sectica 5/29/50 All holders of to Emergency Feeowater pcwer reacter Pumps CLs er cps 50-22 Breakdcwn In Centanina-5/28/50 All holde-s cf tien Centrol Prograas pcwer reactor OLs and cear ters GL a:plicants 80-21 Anchorage and Support of 5/15/SO All holders cf Safety-Related Electrical pcwer reacter Ecuipment OLs er C?s S0-20 Loss of Decay Heat 5/S/50 All holders cf Reacval Capability at gewer reactor Davis-Sesse Unit 1 Wile Ots or cps in a Refueling Mede
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