ML19261C806
| ML19261C806 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 03/20/1979 |
| From: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Linder F DAIRYLAND POWER COOPERATIVE |
| References | |
| NUDOCS 7904030026 | |
| Download: ML19261C806 (1) | |
Text
I ven W!D 2' Docket No. 50-409 Dairyland Power Cooperative ATTN:
Mr. F. W. Linder General Manager 2615 East Avenue - South La Crosse, WI 54601 Gentlemen:
The enclosed Information Notice No. 79-05 is forwarded to you for information. No specific action is requested and no writter response is required. If you desire additional information regarding this matter, please contact this office.
Sincerely, James G. Keppler Director
Enclosure:
IE Information Notice No. 79-05 cc w/ enc 1:
Mr. R. E. Shimshak, Plant Superintendent Central Files Director, NRR/DPM Director, NRR/ DOR PDR Local PDR NSIC TIC I
Anthony Roisman, Esq.,
l Attorney 7904030026 l
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l NRC Form 318A (RIII) (5-76) NRCM 02040
- U. S. GOVE RNMENT PRINTING OFFICE:
1978-253-818
U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMEN:
REGION III March 21, 1979 IE Information Notice No. 79-05 USE OF IMPROPER MATERIALS IN SAFETY-RELATFJ COMPONENTS Two instances of the addition of improper materials to safety-related components during maintenance have recently been identified by NRC inspections.
Materials on valve Seating Surfaces An NRC inspector found that maintenance personnel at the Surry nuclear power plant had added wax or grease to certain valve seating surfaces.
These valves included the containment spray and recirculation spray isolation valves.
This material could have affected the measured leak rate through these containment penetrations.
VEPCO personnel said that the caterial was believed to have been added to prevent damage to the valve seating surfaces during dry valve testing.
It had not been removed following completion of the maintenance procedure.
VEPCO personnel also reported that a lack of any definitive administrative guidance as to what lubricants, if any, could be used during valve maintenance, contributed to this problem.
The corrective action included modifica-tion of the precedures to include more precise inspection by quality control personnel following valve maintenance.
Crease in Snubbers An NRC inspector found that maintenance personnel at the Browns Ferry nuclear power plant had added grease to the hydraulic fluid reservoirs of eight Bergen-Paterson snubbers. The grease had mistakenly been added, during a scheduled lubrication procedure, through the alemite type fittin's.used for normal fluid addition. A similar error involving g
thirteen snubbers had previously been made at this facility. At that time the decision had been made to install a different type of fitting on the snubbers. However, the replacement parts had not arrived in time for installation prior to the more recent lubrication.
At the time of the earlier occurrence, TVA personnel nad removed the affected snubbers and tested them for lock-up and bleed rate.
The results had been within specification. Nevertheless, the units had been disassembled and cleaned prior to reinstallation. NRC inspectors witnessed the disassembly of one of the later set of greased snubbers (a four-inch unit). Approximately one cubic inch of grease was found in the reservoir. Although the grease 7 9 0 3 3 0 018 Q)sN 7903300180
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IE Information Notice No. 79-05
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March 21, 1979 Grease in Snubbers (continued) had been in the reservoir for only four days, and stroking of the snubbers was limited to that which occurred during its re= oval, grease was found in the control valve assembly and the snubber cylinder.
All of the recently greased snubbers were replaced by spare units.
These two occurrences illustrate the necessity of controlling construction and =aintenance practices through the use of care-fully developed procedures designed to prevent errors, such as the introduction of foreign =aterials into safety-related components.
This infor=ation is provided as a notification of a possibly significant
=atter.
It is expected that recipients will review the infor=ation 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 reco==end or request specific licensee actions.
If you have questions regarding this catter, please contact the Director of the appropriate NRC Regional Office.
Enclosure:
Listing of IE Information Notices Issued in 1979 m
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IE Infor=ation Notice No. 79-05 March 21, 1979 LISTING OF IE INFO'e'.ATION ' IICES ISSUED IN 1979 Infor=ation Subject Date Issued To Notice No.
Issued 79-01 Bergen-Pc arson Hydraulic 2/2/79 All power reactor Shock and Sway Arrestor facilities with an OL or a CP 79-02 Attempted Extortion -
2/2/79 All Fuel Facilities Low Enriched Uraniu 79-03 Limitorque Valve Geared 2/9/79 All power reactor Limit Switen Lubricant facilities with an OL or a CP 79-04 Degradation of 2/16/79 All power reacter Engineered facilities with an Safety Features CL or a CP u
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