ML19331C384
| ML19331C384 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 08/07/1980 |
| From: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Burstein S WISCONSIN ELECTRIC POWER CO. |
| References | |
| NUDOCS 8008180210 | |
| Download: ML19331C384 (1) | |
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UNITED STATES
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799 ROOSEVELT ROAD GLEN ELLYN, ILLINOIS 60137 o
AUG 7 880 Docket No. 50-266 Docket No. 50-301 Wisconsin Electric Power Company ATTN:
Mr. Sol Burstein Executive Vice President Power Plants 231 West Michigan Milwaukee, WI 33201 Gentlemen:
This Information Notice is provided as 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, and IE Circular or Bulletin will be issued to recommend or request specific licensee actions.
If you have questions regarding this matter, please contact the Director of'the appropriate NRC Regional Office.
Sincerely, w bO*
ames G. Keppler Director
Enclosure:
IE Information Notice No. 80-29 cc w/ enc 1:
Mr. G. A. Reed, Plant Manager Resident Inspector, RIII Central Files Director, NRR/DPM l
Director, NRR/ DOR l
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C. M. Trammell, ORB /NRR PDR Local PDR NSIC TIC Sandra A. Bast, Lakeshore l
Citizens for Safe Energy Mr. John J. Duffy, Chief Boiler Inspector, Department of Industry, Labor and Human Relations 8008180SiO
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%w SSINS No.: 6835 Accession No.:
UNITED STATES 8006190028 NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 August 7,"I980 IE Information Notice No. 80-29 BROKEN STUDS ON TERRY TURBINE STEAM INLET FLANGE When removing the goverr.or and stop valve on the Unit 1 steam driven emergency feedwater pump at Arkansas Nuclear One for repair of a steam Icak at the steam inlet flange Arkansas Power and Light discovered that five or 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.
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The failed studs are 3/4 in. diameter by 3-1/2 in.
long and are thought to be of ASTM-193 grade B7 steel..The turbine flange bolting is generally covered i
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 turbins 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 previcusly experienced overspeed trips and vibrations which may have been caused by slugs of water from the piping.
Licensees are encouraged to carefu113. 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 surveillance testing, care should be taken to observe if abnormal vibration or other 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 questions regarding this matter, please contact the Director of the appropriate NRC Regional Office.
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i IE Information Notice No. 80-29 Enclosure August 7, 1980 RECENTLY ISSUED IE INFORMATION NOTICE Information Subject Date Issued To Notice No.
Issued Supplement to Notification of 7/29/80 All holder of Reactor 80-06 Significant Events at OLs and to near Operating Power Reactor operating license Facilities applicants 80-28 Prompt Reporting Of 6/13/80 All applicants for and Required Information holders of nuclear power To NRC reactor construction 80-27 Degradation of Reactor 6/11/80 All Pressurized Water Coolant Pump Studs Reactor Facilities holding power reactor OLs or cps 80-26 Evaluation of Contractor 6/10/80 All Part 50 Licensees QA Programs 80-25 Tri.nsportation of 5/30/80 Material Licensee in Pyrophoric Uranium Priority / Categories II-A, II-D, III-I and IV-DI; l
Agreement State Licensees l
in equivalent categories
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80-24 Low Level Radioactive 5/30/80 All NRC and Agreement Waste Burial Criteria State Licensees 80-23 Loss of Suction to 5/29/80 All power reactor j
to Emergency Feedwater facilities with an l
80-22 Breakdown In Contamina-5/28/80 All power reactor tion Control Programs Ols and near term cps 80-21 Anchorage and Support of 5/16/80 All power reactor i
Safety-Related Electrical facilities with an I
Equipment OL or CP 80-20 Loss of Decay Heat 5/8/80 All light water reactor Removal Capability at facilities holding l
Davis-Besse Unit 1 While power reactor OLs or cps l
in a Refueling Mode y-g
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