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	{{#Wiki_filter:~~NIAGARA MOHAWK POWER~~ CORPORATION/300 ERIE ~~BOULEVARD WEST~~. SYRACUSE, N.Y. 13202/TELEPHONE (315) 474-1511 September 4, 1984 Director of Nuclear Reactor Regulation Attention: Mr. Domenic B. Vassallo, Chief Operating Reactors Branch No. 2 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Re: Nine Mile Point Unit 1 Docket No. 50-220 DPR-63		{{#Wiki_filter:NIAGARAMOHAWKPOWER CORPORATION/300 ERIE BOULEVARDWEST. SYRACUSE, N.Y. 13202/TELEPHONE (315) 474-1511 September 4,
			1984 Director of Nuclear Reactor Regulation Attention: Mr. Domenic B. Vassallo, Chief Operating Reactors Branch No.
			2 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D.C.
			20555 Re:
			Nine Mile Point Unit 1
			Docket No. 50-220 DPR-63

	==Dear Mr. Vassallo:==		==Dear Mr. Vassallo:==
			Our {{letter dated\|date=April 30, 1984\|text=April 30, 1984 letter}} provided information and schedules related to the generic implications of the Salem Anticipated Transient Without Scram events (Generic Letter 83-28).
			Attached is information regarding Sections 2.1 and 2.2.2 of your generic letter for Nine Mile Point Unit l.
			Sincerely, NIAGARA MOHAWK POWER CORPORATION PM/bd Attachment C.
			V. Manga Vice President Nuclear Engineering and Licensing 8409100189 840904 PDR ADOCK, 05000220 PDR go~
			))i

	Our April 30, 1984 letter provided information and schedules related to the generic implications of the Salem Anticipated Transient Without Scram events (Generic Letter 83-28). Attached is information regarding Sections 2.1 and 2.2.2 of your generic letter for Nine Mile Point Unit l.		~
	Sincerely, NIAGARA MOHAWK POWER CORPORATION C. V. Manga Vice President Nuclear Engineering and Licensing PM/bd Attachment 8409100189 840904 PDR ADOCK, 05000220 PDR go~		E p
	~~))i~~

	~~~ E p~~		ADDITIONAL INFORMATION REGARDING GENERIC LETTER 83-28 I.
			E ui ment Classification Methodolo Section 2.1 In our initial response to Generic Letter 83-28, dated November 8,
	ADDITIONAL INFORMATION REGARDING GENERIC LETTER 83-28 I. E ui ment Classification Methodolo Section 2.1 In our initial response to Generic Letter 83-28, dated November 8, 1983, Niagara Mohawk stated that a review of General Electric's equipment classification methodology would be conducted and appropriate Engineering Procedures would be revised if necessary. Niagara Mohawk has reviewed General Electric's methodology, as stated in NEDC-30505, and has concluded that general agreement exists with the appropriate engineering procedures. Therefore, procedure revisions are not warranted.		: 1983, Niagara Mohawk stated that a review of General Electric's equipment classification methodology would be conducted and appropriate Engineering Procedures would be revised if necessary.
	However, at this time, Niagara Mohawk has a project underway which involves a review of our equipment classification list (g-List). The present g-List delineates the applicable quality requirements on a system basis, with updates for individual components. This project will convert the 9-List to a component level list. This list, when completed, will include the mechanical, electrical, instrumentation and control, and structural portions of Nine Mile Point Unit 1. The criteria being used for the component classification are those listed in the Nine Mile Point Unit 1 Final Safety Analysis Report, dated June 1967, and its Second, Supplement, dated October 1968. Additional guidance is being utilized from ANSI/ANS 52.1-1983, "Nuclear Safety Criteria for the Design of Stationary Boiling Water Reactor Plants," and appropriate industry codes and standards (i.e. ASME, IEEE, etc.). This project will provide a clear definition to those structures and components, subject to the requirements of our guality Assur ance program and consistent with General Electric's criteria and the Nine Mile Point Unit 1 licensing basis.		Niagara Mohawk has reviewed General Electric's methodology, as stated in NEDC-30505, and has concluded that general agreement exists with the appropriate engineering procedures.
	II. Vendor Interface Pro ram (Section 2.2.2)		Therefore, procedure revisions are not warranted.
	As indicated in our previous correspondence, Niagara Mohawk was an active participant in the Nuclear Utility Task Action Committee formed to address control and utilization of information regarding safety related components. At the outset the Committee recognizeed that individual utilities have the greatest experience with, and are most cognizant of, the application of safety related equipment. Based on this recognition, the Committee investigated the mechanisms currently available to facilitate information exchange among utilities. These included the routine utility/vendor and utility/regulator interchanges and the Significant Event Evaluation and Information Network (SEE-IN) and Nuclear Plant Reliability Data System (NPRDS) programs managed by the Institute of Nuclear Power Operations (INPO). The Committee concluded that these existing activities, coupled with a coordinated program within each utility, constituted an overall program to ensure the dissemination and utilization of technical information regarding reliability of safety related equipment. Additional information describing this overall program was provided to the Nuclear Regulatory Commission in March 1984 by the Committee.		However, at this time, Niagara Mohawk has a project underway which involves a review of our equipment classification list (g-List).
			The present g-List delineates the applicable quality requirements on a system basis, with updates for individual components.
			This project will convert the 9-List to a component level list.
			This list, when completed, will include the mechanical, electrical, instrumentation and control, and structural portions of Nine Mile Point Unit 1.
			The criteria being used for the component classification are those listed in the Nine Mile Point Unit 1 Final Safety Analysis Report, dated June
			: 1967, and its Second, Supplement, dated October 1968.
			Additional guidance is being utilized from ANSI/ANS 52.1-1983, "Nuclear Safety Criteria for the Design of Stationary Boiling Water Reactor Plants,"
			and appropriate industry codes and standards (i.e.
			: ASME, IEEE, etc.).
			This project will provide a clear definition to those structures and components, subject to the requirements of our guality Assur ance program and consistent with General Electric's criteria and the Nine Mile Point Unit 1 licensing basis.
			II.
			Vendor Interface Pro ram (Section 2.2.2)
			As indicated in our previous correspondence, Niagara Mohawk was an active participant in the Nuclear Utility Task Action Committee formed to address control and utilization of information regarding safety related components.
			At the outset the Committee recognizeed that individual utilities have the greatest experience with, and are most cognizant of, the application of safety related equipment.
			Based on this recognition, the Committee investigated the mechanisms currently available to facilitate information exchange among utilities.
			These included the routine utility/vendor and utility/regulator interchanges and the Significant Event Evaluation and Information Network (SEE-IN) and Nuclear Plant Reliability Data System (NPRDS) programs managed by the Institute of Nuclear Power Operations (INPO).
			The Committee concluded that these existing activities, coupled with a coordinated program within each utility, constituted an overall program to ensure the dissemination and utilization of technical information regarding reliability of safety related equipment.
			Additional information describing this overall program was provided to the Nuclear Regulatory Commission in March 1984 by the Committee.

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	A key element of the vendor equipment technical information program is a utility program to contribute information to the NPRDS and SEE-IN programs and to use the results of these programs. The administrative controls currently being implemented at Nine Mile Point Unit 1 contain procedures and data collection requirements related to these programs. These requirements provide assurance that information regarding safety related equipment is handled in an efficient, timely manner. No specific change to these existing administrative controls is deemed necessary at this time. However, to increase the effectiveness of the NPRDS an additional individual has been added to the Nine Mile Point Technical Staff to coordinate the activities of this program. This action, coupled with the existing administrative controls, meets the intent of Section 2.2.2 of Generic Letter 83-28 addressing vendor information and interface.		A key element of the vendor equipment technical information program is a
			utility program to contribute information to the NPRDS and SEE-IN programs and to use the results of these programs.
			The administrative controls currently being implemented at Nine Mile Point Unit 1 contain procedures and data collection requirements related to these programs.
			These requirements provide assurance that information regarding safety related equipment is handled in an efficient, timely manner.
			No specific change to these existing administrative controls is deemed necessary at this time.
			However, to increase the effectiveness of the NPRDS an additional individual has been added to the Nine Mile Point Technical Staff to coordinate the activities of this program.
			This action, coupled with the existing administrative controls, meets the intent of Section 2.2.2 of Generic Letter 83-28 addressing vendor information and interface.

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