ML19305D412
| ML19305D412 | |
| Person / Time | |
|---|---|
| Site: | Bailly |
| Issue date: | 04/02/1980 |
| From: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Shorb E NORTHERN INDIANA PUBLIC SERVICE CO. |
| References | |
| NUDOCS 8004150048 | |
| Download: ML19305D412 (1) | |
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1 UNITED STATES t'
NUCLEAR REGULATORY COMMISSION 4
' o REGION lil 799 ROOSEVELT ROAD g
GLEN ELLYN, ILLINOIS 60137 Docket No. 50-367 APR 2 gg Northern Indiana Public Service Company ATTN:
Mr. Eugene M. Shorb Senior Vice President 5265 Hohman Avenue Hammond, IN 46325 Gentlemen:
This Information Notice is provided as an early notification of a possibly significant matter.
It is expected that recipients will review the infor-mation for possible applicability to their facilities. No specific action or response is requested at this time; however, an IE Circular or Bulletin will be issued to recommend or request specific licensee actions, if re-quired.
If you have questions regarding this matter, please contact the Director of the appropriate NRC Regional Office.
Sincerely, O
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wD ames G. Kepp e Director
Enclosure:
IE Information Notice No. 80-13 cc w/ encl:
Central Files Director, NRR/DPM Director, NRR/ DOR PDR Local PDR NSIC TIC Mr. Dean Hansell, Office of Assistant Attorney General 80041500d
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SSINS No.: 6870
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Accession No.:
UNITED STATES 8002280650 NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT I
WASHINGTON, D.C.
20555
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April 2, 1980 IE Information Notice No. 80-13 GENERAL ELECTRIC TYPE SBM CONTROL SWITCHES DEFECTIVE CAM FOLLOWERS Description of Circumstances:
This Information Notice alerts licensees and holders of construction permits of a potential defect in the cam followers of General Electric (GE) Type SBM control switches.
Based on preliminary information, it appears that the defect is limited to switches manufactured prior to 1976 with cam followers of polycarbonate material, such as Lexan.
In brief, the problem is initiated by exposing such polycarbonate material to hydrocarbons.
Such exposure leads to severe cracking having a rock salt appearance which ultimately could progress t
to mechanical failure.
It has been de'. ermined that such exposure has occurred during fabrication and could occur while performing maintenance (e.g. cleaning the contacts).
On February 22 and March 10, 1980 we were informed that SBN switches with defect 5 e cam followers had been found at Diablo Canyon Unit 1 and at the Cooper Station, respectively.
Although the information was preliminary and sketchy, the problem is a long-standing one for which GE har issued " Service Information Letters" to its BWR customers. The problems associated with such switches, however, are not restricted to GE custorars as evidenced by the Diablo Canyon case.
Furthermore, these switches have a broad range of applica-tion.
For example, the defective switches at the Cooper Station were used principally as hand control switches, most of which were located in the control In contrast, those at Diablo Canyon Unit 1 were used as auxiliary room.
contacts on the 4KV and 12KV "Magna Blast" circuit breakers, with three SBM switches used per breaker: (1) a breaker mounted auxiliary switch, (2) a cell mounted auxiliary switch, and (3) a cell interlock switch.
This information is provided as 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 facilities.
No specific action or response is requested at this time.
If you have questions regarding this matter, please contact the Director of the appropriate NRC Regicnal Office.
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1 IE Information Notice No. 80-13 Enclosure
'I April 2, 1980 RECENTLY ISSUED IE INFORMATION NOTICES
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Information Subject Date Issued To Notice No.
Issued 80-12 Instrument Failure Causes 3/31/80 All holders of Power Opening of PORV and Block Reactor OLs and cps Valve 80-11 General Problems with ASCO 3/14/80 All holders of Reactor Valves in Nuclear Application OL, CP, fuel fabrica-Including Fire Protection tion and processing Systems facilities 80-10 Partial Loss of Non-Nuclear 3/7/80 All power reactor Instrument System Power facilities holding Supply During Operation OLs and cps 80-09 Possible Occupational 3/7/80 All holders of Health Hazard Associated power reactor OLs with Closed Cooling Systems and near term cps 80-08 The States Company Sliding 3/7/80 All power reactor Link Electrical Terminal facilities with an OL Block or a CP 80-07 Pump Shaft Fatigue Cracking 2/29/80 All Light Water Reactor Facilities holder power reactor OLs and cps 80-06 Notification of Significant 2/27/80 All holders of Reactor Events OLs and to near term OL applicants 80-05 Chloride Contamination 2/8/80 All licensees of nuclear of Safety Related Piping powar reactor facilities and applicants and holders of nuclear power reactor cps 80-04 BWR Fuel Exposure in 2/4/80 All BWR's holding a Excess of Limits power reactor OL or CP 80-03 Main Turbine Electro-1/31/80 All holders of power Hydraulic Control System reactor OLs and cps l
80-02 8X8R Water Rod Lower 1/25/80 All BWR Facilities End Plug Wear holder power reactor l
OLs or cps J
s.
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