ML19332B220
| ML19332B220 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 08/07/1980 |
| From: | Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | Pilant J NEBRASKA PUBLIC POWER DISTRICT |
| References | |
| NUDOCS 8009260291 | |
| Download: ML19332B220 (1) | |
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CENTRAL FILES UNITED STATES NUCLEAR REGULATORY COMMISSION PDR:HQ 3~
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August 7, 1980 Docket No.
50-298 Nebraska Public Power District ATTN:
J. M. Pilant, Director Licensing & Quality Assurance Post Office Box 499 Columbus, Nebraska 68601 Gentlemen:
This IE 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, an 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, i,
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Karl V. Seyfrit I Director
Enclosures:
1.
II Infor=ation Notice No. 80-29 2.
List of Recently Issued IE Information Notices cc:
L. C. Lessor, Superintendent Cooper Nuclear Station Post Office Box 98 3rownville, Nebraska 68321
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U SSINS No.: 6835 Accession No.:
UNITED STATES 8006190028 NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, 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, Arkaasas 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 inch diameter by 3-1/2 inch long and are thought to be of ASTM-193 grade B7 steel. The turbine flange bolting is generally covered with insulation and not visible for inspection.
From the information available, the boltir:; hau not been removed or inspected since installation seven to eight years ago.
The steam duven 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 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 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 tegion 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 abnortal vibration or other transients occur which could promote loss of bolting integrity.
This Information Notice is provided as an early notification of a possibly s..gnificant 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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IE Information No. 80-29 August 7, 1980 LISTING OF RECENTLY ISSUED IE INFORMATION NOTICES Information Subject Date Issued To Notice No.
Issued 80-23 Loss of Suction to 5/29/80 All power reactor to Emergency Feedwater facilities with an Pumps Operating License (OL) or Construction Permit (CP) 80-24 Low Level Radioactive 5/30/80 All NRC and Agreement Waste Burial Criteria State Licensees 80-25 Transportation of 5/30/80 Material Licensee Pyrophoric Uranium in Priority / Categories II-A, II-D, III-I and IV-DI; Agreement State Licensees in equivalent categories 80-26 Evaluation of Contractor 6/10/80 All Part 50 Licensees QA Programs 80-27 Degradation of Reactor 6/11/80 All Pressurized Water Coolant Pump Studs Reactor Facilities holding power reactor Operating License (OL) or Construction Permits (cps) 80-28 Prompt Reporting Of 6/13/80 All applicants for and Required Information holders of nuclear power to NRC reactor construction permits Supp. to Notification of 7/29/80 All holders of Reactor 80-06 Significant Events at Operating Licenses (OLs)
Operating Power Reactor and to near term Facilities operating license applicants Enclosure l
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