ML19294C278: Difference between revisions

From kanterella
Jump to navigation Jump to search
Created page by program invented by StriderTol
StriderTol Bot change
 
Line 16: Line 16:


=Text=
=Text=
{{#Wiki_filter:O smuun Northern Indiana Public Service Company General Offices l 5 65 Hohman Avenue l Hammond. Indiana 46325 l Tel: 853-5200 (219)
{{#Wiki_filter:O Northern Indiana Public Service Company smuun General Offices l 5 65 Hohman Avenue l Hammond. Indiana 46325 l Tel: 853-5200 (219)
EUOrNE M. SHO AB na.r v.c c a c s.oc '
EUOrNE M. SHO AB na.r v.c c a c s.oc '
February 14, 1980 M r. James G. Keppler, Regional Director U. S. Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, Illinois 60137 Re:     NRC IE Bulletin 79-28, "Possible Malfunction of NAMCO Model EA180 Limit Switches At Elevated Temperatures,"
February 14, 1980 M r.
James G. Keppler, Regional Director U. S. Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, Illinois 60137 Re:
NRC IE Bulletin 79-28, "Possible Malfunction of NAMCO Model EA180 Limit Switches At Elevated Temperatures,"
dated December 7,1979 - Docket No. 50-367
dated December 7,1979 - Docket No. 50-367


==Dear Mr. Kepple r:==
==Dear Mr. Kepple r:==
This letter is in response to IE Bulletin No. 79-28 dated December 7,1979. We have determined, through correspond-ence with our NSSS vendor and architect / engineer, that NAMCO Model EA-180 limit switches described in the referenced IE Bulletin have not been and will not be installed on any safety-related equipment located inside or outside containment, including valve position indicating circuitry related to contain-ment isolation valves.
This letter is in response to IE Bulletin No. 79-28 dated December 7,1979. We have determined, through correspond-ence with our NSSS vendor and architect / engineer, that NAMCO Model EA-180 limit switches described in the referenced IE Bulletin have not been and will not be installed on any safety-related equipment located inside or outside containment, including valve position indicating circuitry related to contain-ment isolation valves.
Very truly yours, M
Very truly yours, M
                                                        /g -
/g a
a EMS:cg s
EMS:cg s cc:
* cc:   U. S. Nuclear Regulatory Commission Office of Inspection & Enforcement Division of Reactor Construction Inspection Washington, D. C.           20555 FEB 151980 8o03100035}}
U. S. Nuclear Regulatory Commission Office of Inspection & Enforcement Division of Reactor Construction Inspection Washington, D. C.
20555 FEB 151980 8o03100035}}

Latest revision as of 08:10, 2 January 2025

Responds to IE Bulletin 79-28, Possible Malfunction of Namco Model EA180 Limit Switches at Elevated Temps. Switches Have Not Been & Will Not Be Installed on Any safety-related Equipment Inside or Outside Containment
ML19294C278
Person / Time
Site: Bailly
Issue date: 02/14/1980
From: Shorb E
NORTHERN INDIANA PUBLIC SERVICE CO.
To: James Keppler
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
IEB-79-28, NUDOCS 8003100035
Download: ML19294C278 (1)


Text

O Northern Indiana Public Service Company smuun General Offices l 5 65 Hohman Avenue l Hammond. Indiana 46325 l Tel: 853-5200 (219)

EUOrNE M. SHO AB na.r v.c c a c s.oc '

February 14, 1980 M r.

James G. Keppler, Regional Director U. S. Nuclear Regulatory Commission Region III 799 Roosevelt Road Glen Ellyn, Illinois 60137 Re:

NRC IE Bulletin 79-28, "Possible Malfunction of NAMCO Model EA180 Limit Switches At Elevated Temperatures,"

dated December 7,1979 - Docket No. 50-367

Dear Mr. Kepple r:

This letter is in response to IE Bulletin No. 79-28 dated December 7,1979. We have determined, through correspond-ence with our NSSS vendor and architect / engineer, that NAMCO Model EA-180 limit switches described in the referenced IE Bulletin have not been and will not be installed on any safety-related equipment located inside or outside containment, including valve position indicating circuitry related to contain-ment isolation valves.

Very truly yours, M

/g a

EMS:cg s cc:

U. S. Nuclear Regulatory Commission Office of Inspection & Enforcement Division of Reactor Construction Inspection Washington, D. C.

20555 FEB 151980 8o03100035