ML19262A137

Forwards Addl Info Re IE Bulletin 79-01,in Response to 790919 Request.Info Pertains to Ancillary Components

ML19262A137
Person / Time
Site:	Cooper
Issue date:	10/02/1979
From:	Pilant J NEBRASKA PUBLIC POWER DISTRICT
To:	Heishman R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
References
NUDOCS 7910260418
Download: ML19262A137 (4)

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October 2, 1979 U.S. Nuclear Regulatory Commission Attention: R. F. lleishman, Chief Reactor Operations and Nuclear Support Branch Region III 799 Roosevelt Road Glen Ellyn, Illinois 60137

Subject:

IE Bulletin 79-01

" Environmental Qualification of Class lE Equipment" Cooper Nuclear Station NRC Docket No. 50._29,8, DPR-46

Dear Mr. lleishman:

Per your letter of September 19, 1979, attached is the additional infor-mation requested relative to the subject bulletin.

If you have any questions, or require additional information, please do not hesitate to contact me.

Sincerely, N

. . Pilant Director of Licensing and Quality Assurance JDW/cmk Attachment 1217 151 j4 7910260 Y/ 7

Cooper Nuclear Station RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION IE BULLETIN 79-01 Item No. 1 ,

Your response does not include how ancillary components or parts, were qualified, e.g. lubricants, gaskets, hermetic seals, splicing materials, tapes, coatings, "0" rings, etc.

Identify safety related ancillary components or parts by manufacturer, model and/or type, and generic name, e.g. tape, lubricant, etc.

Provide written evidence, e.g. test report number, to substantiate qualification of the equipment. If an ancillary component was tested with a major component, indicate if that same component or a sub-stitute is being utilized in your facility.

Response

As identified in Table 1 of our response to IEB 79-01, the safety-related electrical equipment for which qualification data was required at CNS includes NAMCO Limit Switches, Automatic Valve Co. Solenoid Valves, Limitorque Motor Operated Valves, GE Electrical Penetrations and Electrical Cable. These components do not have ancillary components or parts which were not originally qualified with the major component.

Replace =ent parts and lubricants are the same as those qualified with the major components.

Cable splices at Cooper Nuclear Station were addressed in FSAR Amendment No. 35, response to Question 7.4. There are no Power Cable or Circuit Cable splices within the drywell. All control cable splices within the drywell are done by means of termination boxes with protective covers and gaskets.

Item No. 2 Your response does not include limit switches used for indication of position. Our position is that power operated containment isolation valves, irrespective of system classification, must provide the control room. operator with indication of valve position during and following a LOCA.

Determine if the types of limit switches described in IE Bulletins 79-01 and 78-0?. are being used or planned for use as position in-dication on safety related valves which are located inside containment.

Also, for limit switches not included in the IE Bulletins, provide written evidence, e.g. test report number, to substantiate qual-ification of the switches. In addition, any items which you identify as not meeting requirements for service intended shall be reported in accordance with paragraph 4 of IE Bulletin No. 79-01.

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Response

The limit switches described in IE Bulletins 79-01 and 78-04 used on safety related valves were addressed in our June 22, 1979 response to IEB 79-01. These switches were replaced with qualified models durirg the April 1979 refueling outage.

The new NRC position that limit switches on isolation valves for non-essential systems within the containment be qualified, affects one valve at CNS. The 3/4" reactor water sample valve inside the drywell does not have qualified limit switches. These limit switches will be replaced with qualified models during the March-April 1980 refueling outage. Since these limit switches are only for position indication, and were not required to be qualified for a LOCA environment before the new NRC position on this matter was revealed, they do not fall under the reporting requirements specified in paragraph 4 of IEB 79-01.

These switches meet the service requirements for which they were orig-inally intended.

For purposes of this response and as discussed with the NRC Region III office, the testable check valves in the containment are not considered to be containment isolation valves.

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